ML20012A073

Supplemental Effluent & Waste Disposal Semiannual Rept for Second Half 1989

ML20012A073
Person / Time
Site:	Sequoyah
Issue date:	12/31/1989
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20012A072	List: ML20012A071 ML20012A073 ML20012A075
References
NUDOCS 9003080246
Download: ML20012A073 (32)

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{{#Wiki_filter:I i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMA110N 2nd HALF 1989 1c Regulatory Limits a. Fission and Activation Gases: 1 (1) Instantaneous - Nuclide Dependant (all release points) i Shield Building Exhaust Auxiliary Building Exhaust Condenser Vacuum Lxhaust 8 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 flowrate. lechnical Specification will not be exceeded until the sum of individual isotope release rate per release rate limit exceeds 1.0.

b. and c.

lodines and particulates, 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 i 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: IMPCs1.0 (reference 100FR20, Appendix B, note

30. Table 11, column 2).

e. Tritium (1) Liquid - s3.0E-3 uti/ml (ref.10CFR20 Table 11, column 2) (2) Airborne - (reference 100FR20, Table II, column 1) Shield Building Exhaust s3.09E+03 uti/sec Auxiliary Building Exhaust s2.52E+04 uti/sec Service Building Exhaust s1.65E+03 uti/sec Condenser Vacuum Exhaust s4.95E+00 uti/sec NOTE: These limits are established by TVA based on each vent's design flowrate. 9003000246 900301 ~ ADDCK050g7 DR

EFFLUENT AND WASTL DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMA110N Lnd. HALF 1989 n 2. Maximum Permissible Concentrations a. Fission and Activation Gases: Not Applicable j b. lodines: Not Applicable i c. Particulates, half-lives 18 days: Not Applicable d. Liquid effluents: sum of indv. MPC ratios $1.0 (ref.100FR20, Appendix B, Note 1) 3. Average Energy - Not Applicable 4. Measurements and Approximations of Total Radioactivity N010: Every ef fort is made to ensure that all ef fluents f rom Sequoyah are conducted such that all Technical Specification LLDs are met. Whenever an analysis does not identif y 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 f rom 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 1-131 concentration in the primary coolant has increased more than a f actor of 3 and the noble gas activity monitor shows that the containment activity has increased more than a factor of 3). The vent flowrates for the shield building, auxiliary building, service building, and l condenser vacuum exhausts are determined and recorded once a shif t. 1 l t ' i

b If EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT T SUPPLEMENTAL INFORMATION 2nd HALF 1989 4 '. Measurements and Approximation of Total 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 suming all of the activity released f rom each vent for all sampling periods, the activity released from purging or venting of containment, and the activity released f rom waste gas decay tank (s),

b. and c. lodines and Particulates lodine and particulate activity is continuously monitored and recorded. Charcoal and particulate samples are taken f rom the shield and auxiliary building exhausts and analyzed at least 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 f rom the auxiliary and shield building exhausts once per 24 hours for 2 days f ollowing 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 from 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 shield and auxiliary building exhautts for all sampling periods, d. Liquid Effluents (1) Batch (Radwaste and condensate regenerants to cooling tower blowdown) L Total gama isotopic activity concentrations are determined on 4 each batch of ihuid ef fluent 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 SEM1 ANNUAL REPORT SUPPLEMENTAL INFORMATION 2nd HALF 1989 '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 gamne isotopic activity concentration is determined daily on a 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 3rd 4th a. Liquid 9 1. Number of batches released (Radwaste only) 143 176-Each 2. Total time period for batch releases 20,958 26,072 Minutes 3. Maximum time psriod f or a batch release 238 265 Minutes 4. Average time period for batch releases 147 148 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 21 5 211 Each

2..

Total time period for batch releases 24,405 28,268 Minutes 3. Maximum time period for a batch release 1,440 1,440 Minutes 4. Average time period for batch releases 114 134 Minutes 5. Minimum time period for a batch release 7 9 Minutes :

k EFFLUENT AND WASTE DISPOSAL SEMIANNUAL' REPORT - - -c. SUPPLEMENTAL INFORMATION Rnd HALF 1989 6.- ' Abnormal. Releases Value Units Quarter Quarter - 3rd 4th a. -Liquid (1) Number of Releases-0 0-(2) Total Activity Released 0.00E-01 0.00E-01 Ci b.- Gaseous (1) . Number of Releases __0 0-(2) lotal Activity Released-0.00E-01 0.00E-01 Ci 7. Offsite Dose C'leulation Manual (ODCM) Were any changes made to the ODCM during the reporting period? X Yes No If yes, add an attachment at the end of-report. (Attachment 2)

s EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT 2nd HALF 1989 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 3rd 4th s Fission and Activation Unit Otr % Error Otr % Error A. Products 1. Total Released Curies 4.84E-02 +1. 8 E+01 2.05E-01 11.8E+01 2. Average Diluted Conc. During Period of All Identified Isotopes pCi/ml 2.12E-08 9.49E-08 3. Percent of Applicable i limit (IMPCs1) 4.08E-02 4.57E-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 i 1 1. Total Released Curies 3.37E+02

11. 8E+01 5.30E+02 11.8E+01 2.

Average Diluted pCi/ml 1.48E-04 2.45E-04 Conc. During Period 3. Percent of Applicable Limit (3.0E-03 pCi/ml) 4.93E+00 8.18E+00 C. Dissolved and Entrained Gases '2. Average Diluted pCi/ml 3.57E-08 -+3.9E+01 1.59E+00 13.9E+01 1. Total Released Curies 8.15E-02 7.38E-07 Conc. During Period 3. Percent of Applicable Limit (2.0E-04 pCi/ml) 1.79E-02 3.69E-01 D. Gross Alpha Radioactivity 1. Total Released Curies 0.00E-01 12.0E+01 0.00E-01 12.0E+01 E. Volume of Waste Released (Before Oilution) Liters 3.85E+08 14.0E+00 2.04E+07 14.0E+00 F. Volume of Dilution Liters 1.89E+09 11.1E+01 2.14E+09 11.1E+01 Water for Period mi EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT 2nd HALF 1989 LIQUID EFFLUENTS TOTAL PLANT DISCHARGE G. _ lsotope Summary. (Note: Refer to Table A for values reported as 0.00E-01) Required by Technical Specification /Others Fission and Activation' Products Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4 t h., 1. Strontium-89 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 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 1.53E-02 4.. Manganese-54 Ci 0.00E-01 0.00E-01 2.54E-04 4.97E-03 5.- Cobalt-58 Ci 0.00E-01 0.00E-01 1.23E-02 7.93E-02 6. Iron-59 Ci 0.00E-01 0.00E-01 3.14E-05 1.65E-04 7. Cobalt-60 Ci 1.64E-03 0.00E-01 9.15E-03 3.59E-02. 8. Zinc-65 Ci 0.00E-01 0.00E-01 0.00E-01 2,96E-05 -9. Molybdenum-99 Ci 0.00E-01 0.00E-01 9.04E-03 6.42E-03 10. lodine-131 Ci 0.00E-01 0.00E-01 2.88E-05 1.58E-03

11. Cesium-134 -

Ci 0.00E-01 1.39E-05 1.46E-04 6.26E-03 12. Cesium-137 Ci 6.45E-05 7.16E-05 5.43E-04 2.02E-02

13. Cerium-141 Ci 0.00E-01 0.00E-01 3.28E-05 1.52E-03

14. Cerium-144 Ci 0.00E-01 0.00E-01 0.00E-01 1.14E-04 Others (Specify)

'15. ' Antimony-125 Ci 5.39E-05 0.00E-01 1.24E-05 6.99E-03 16. Cobalt-57 Ci 0.00E-01 0.00E-01 6.84E-05 1.97E-04

17. Chromium-51 Ci 0.00E-01 0.00E-01 2.39E-03 1.11E-02

18. Niobium-97 Ci 0.00E-01 0.00E-01 1.05E-05 2.97E-06

19. -Niobium-95 Ci 0.00E-01 0.00E-01 1.85E-04 1.53E-03

_7-

EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT 2nd HALF 1989 LIQUID EFFLUENlS - TOTAL PLANT DISCHARGE (CONTINUED) Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd _ 4th

20. Barium-140 Ci 0.00E-01 0.00E-01 4.43E-04 2.10E-04

21. lodine-133 Ci 0.00E-01 0.00E-01 4.04E-06 1.52E-04

22. Zirconium-95 Ci 0.00E-01 0.00E-01 9.17E-05 4.56E-04

23. ~ Technetium-99m Ci 0.00E-01 0.00E-01 1.12E-02 5.74E-03

24. Ruthenium-103 Ci 0.00E-01 0.00E-01 9.27E-05 1.01E-03

25. Tellurium-132 Ci 0.00E-01 0.00E-01 1.36E-05 7.60E-06_

26. Antimony-122 Ci 0.00E-01 0.00E 2.77E-06 0.00E-01

27. Zinc-69m Ci 0.00E-01 0.00E-01 5.34E-06 0,00E-01

28. Lanthanum-140 Ci 0.00E-01 0.00E-01 4.38E-04 2.64E-03

29. Cerium-143 Ci 0.00E-01 0.00E-01 4.56E-05 1.04E-04

30. Tungsten-187 Ci 0.00E-01 0.00E-01 4.05E-05 0.00E-01 31. Barium-139 Ci 0.00E-01 0.00E-01 0.00E-01 2.70E-05

32. Bromine-82 Ci 0.00E-01 0.00E-01 0.00E-01 3.93E-05

33. Cesium-136 Ci 0.00E-01 0.00E-01 0.00E-01 6.02E-05

34. Rubidium-86 Ci 0.00E-01 0.00E-01 0.00E-01 8.47E-05

35. Antimony-124 Ci 0.00E-01 0.00E-01 0.00E-01, 6.66E-05

36. Yttrium-91 Ci 0.00E-01 0.00E-01 0.00E-01 2.98E-03 Total for Period Ci 1.76E-03 8.55E-04 4.66E-02 2.05E-01

- l

7: 9 [ EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 1989 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE (CONTINUED) G. Isotcoe Summary '(NOTE: Refer to Table A for values reported as 0.00E-01) l Required by_-Technical Specification /Others Dissolved and Entrained Noble Gases Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th 1. Krypton-87 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 f 2. Krypton-88 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 3. Xenon-133 C1 3.82E-05 0.00E-01 7.09E-02 1.55E+00 4. Xenon-133m Ci 0.00E 0.00E-01 6.79E-04 1.24E-02 5. Xenon-135 Ci 7.88E-0(i 0.00E-01 4.31E-04 7.19E-03 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 1.58E-06 0.'00E-01

8.. Krypton-85 Ci 0.00E-01 0.00E-01 9.34E-03 3.02E-04 9.

Xenon-131m Ci 0.00E-01_ 0.00E-01 1.53E-04 2.22E-02 10. Xenon-135m Ci 0.00E-01 0.00E 6.16E-12 0.00E-01 Total for Period Ci

4. 61 E-05 0.00E-01 8.15E-02 1.59E+00 I

_g _

EFFLUENl AND WASlE DISPOSAL SEM1 ANNUAL REPORT 2nd HALF 1989 TABLE A LIQUID " TYPICAL LLD" EVALUATION (1) at(2) Nuclide Tech. Spec. LLD 15 min 30 min 1 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-07 1.62E-08 1.62E-08 1.62E-08 1.62E-08 Cobalt-60 5.0E-07 1.08E-08 1.08E-08 1.08E-08 1.08E-08 Zint-65 5.0E-07 2.14E-08 2.14E-08 2.14E-08 2.14E-08 Molybdenum-99 5.0E-07 5.24E-08 5.25E-08

5. 28E -08 5.34E-08 Cesium-134 5.0E-07 9.82E-09 9.82E-09 9.82E-09 9.82E-09 Cesiun-137 5.0E.-07 9. 31 E -09 9.31E-09

9. 31 E -09 9.31E-09 Ceriuo-141 5.0E-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-08 lodine-131 1.0E-06 7.28E-09 7.28E-09 7.30E-09 7.32E-09 Krypton-87 1.0E-05 1.62E-08 1.85E-08 2.43E-08 4.20E-08 Krypton-88 1.0E-05 2.13E-08 2.27E-08 2.56E-08 3.27E-08 Xenon-133 1.0E-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 2.55E-07 4.79E-06

k'm - 6 s EFFLUENT AND WASTE DISPOSAL. SEMIANNUAL REPORT-~ 2nd HALF -1989 g';' E TABLE A LIQUID."1YPICAL LLD" EVALUATION (1) -(Continued)- "Huclide . Tech. Spec LLO Typical LLO t (Others)'(s)' t - 1.0E-05' 1.0E-06 -Tritium Gross Alpha-1.0E 2.0E-08 Strontium-89. 5.0E-08 2.0E Strontium-90 5.0E 1.0E-08 l Iron-55 1.0E-06 3.0E-07 'll analyses-are performed to ensure

NOTES:

(t) All evaluations are in pCi/ml. A that Technical-Specification LLO. limits are met, and these are: typical LLD values. l (a) at'is the time between sample collection and counting time. (s). -All of these analyses are required to meet Technical Specification LLD- -. limits,_and~are individually-evaluated to ensure compliance, i L f l A u b l !- l w

En 4 EFFLUENT AND WASTE. DISPOSAL SEMIANNUAL REPORT-sjj. Lv 2nd HALF 1989 GASEOUS EFFLUENTS-SUMMA 110N OF ALL RELEASES (GROUND LEVEL RELEASES) 3rd 4th Summation of All Releases Unit Otr % Error Otr % Error-LA. Noble Gases 1. Total Released Ci 6.61 E+02 11.1E+01 2.68E+03-11.1E+01 2. Average Release [ Rate of, Period uti/sec 8.32E+01 3.38E+02 i 3. Percent of Technical Specification Limit 3.23E-02 1.17E - ~B.- lodines 1. lotal Iodine-131 Ci 0.00E-01

11. 3E+01 1.38E-07 11.3E+01 L

2. Average Release Rate'for Period uti/sec 0.00E-01 1.73E-08 3. Percent of Technical Specification Limit -(1.60E-01 uCi/sec)' 0.00E-01 1.08E-05 C. Particulates 1. Particulates with Ci 5.72E-06 -+1. 6 E+01 1.19E-05 +1.6E+01 ~ half-lives 18 days 2. Average Release Rate for Period UCi/sec 7.19E 1.49E-06 3. Percent of Techni-cal Specification 2.43E-05 4.18E-05 Limit 4. Gross Alpha Radio-Ci 0.00E-01 12.1 E+01 0.00E-01 12.1E+01 activity 0-Tritium

1. l Total Release Ci 3.68E+01

11. 5E+01 1.17E+01 11.5E+01 2.

Average Release Rate for Period. uCi/sec 4.63E+00 1.47E+00-3. Percent of Technical -Specification Limit 1.40E-02 4.46E-03 (3.3E+04 uti/sec) W

( ,a {: EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT-2nd HALF 1989 GASEOUS EFFLUENTS-SUMMA 110N OF ALL RELEASES-(GROUND LEVEL RELEASES)' Continuous Mode 8atch Mode Unit Quarter Quarter Quarter Quarter 1 3rd 4th 3rd' 4th Ec Noble Gases a Required by Technical Specification /0thers-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-01 3.13 E-01 9.58E-01 3. Xenon-133 Ci L94E+01 9.68E+02-6.07E+02-1.62E+03 4. Xenon-133m Ci-h00E-01 0.00E-01

1. 02 E +01 2.00E+01 5.

Xenon-135 : Ci 0.00E-01 2.00E+01

1. 28E+01 3.01E+01 6.

Xenon-138 -Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Others (Specify) 7. ' Krypton-85 Ci 0.00E-01 0.00E-01 1.54E+00 -1.96E+00 i 8. Argon-41 _ Ci 0.00E-01 0.00E-01 4.26E+00 3.20E+00 9. Krypton-85m' Ci 0,00E-01 0.00E-01 -1.01E+00 2.43E+00 10.- Xenon-131m Ci 0.00E-01 0.00E-01 4.79E+00

1. 33 E +01 Total for Perio'd Ci 1.94E+01 9.88E+02 6.42E+02 1.69E+03 F.-

lodines 1. lodine-131 [1 0.00E-01 1.37E '2. lodine-133 C_1 0.00E-01 0.00E-01 3. lodine-135 [1 0.00[-01 0.00E-01 Total for Period Ci 0.00E-01 1.37E-07 NOTE: Refer to Table 8 for values reported as 0.00E-01. -

-n +.- EFFLUENT AND WASTE DISPOSAL-SEMIANNUAL REPORT 2nd HALF 1989 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)- - G '. Particulates c Required by Tet;hnical. Specification /Others Nuclide: Unit Continuous Mode Quarter Quarter 3rd 4th

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 14. Cobalt-60 Ci 3.10E-06 '5.39E ' 5. Zinc-65 Ci 0.00E-01 0.00E-01 4 6. Manganese-54 Ci 0.00E-01 0.00E-01 7.- Cobalt-58 C1 2.62E-06 3.49E-06 8. Molybdenum-99 Ci 0.00E-01 1.49E-06 9. Cesium-134 Ci 0.00E-01 0.00E-01

10. Cesium-137 Ci 0.00E-01 0.00E-01

11. Cerium-141 Ci 0.00E-01 0.00E-01

12. -Cerium-144.

Ci 0.00E-01 0.00E-01 Others (Specify) 1

13. Technetium-99m Ci 0.00E 1.49E-06 Total for Period Ci 5.72E-06 1.19E-05 NOTE: Refer to. Table B for values reported as 0.00E-01.

W I i i '

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF ~1989 TASLE B GASEOUS " TYPICAL" LLO EVALVATION (1) Noble Gas-at(*) Nuclide Tech. Spec. LLD 15 min 30 min 1 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. 51 E-07 Xenon-133 1.0E-04 1.97E-07 1.98E-07 1.98E-07 1.99E-07 Xenon-133m 1.0E-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 Xenon-138 1.0E-04 4.93E-07 1.03E-06 4.46E 8.38E-05 Particulate Sample

~ Manganese-54 1.0E-10 3.88E-14 3.88E-14' 3.88E-14

3. 88E-14

3. 88E-14 Cobalt-58 1.0E-10 3.49E-14 3.49 E-14 3.49 E-14

3. 50E-14

3. 50E-14 Iron-59

1. 0E-10

7. 25E-14

7. 2 5E 7. 25 E-14

7. 26E-14 7.26E-14 Cobalt-60 1,0E-10 4.95E-14

4. 9 5 E-14 4.95 E-14 4.95E-14 4.95E-14 Zinc-65 1.0E-10

9. 54E-14 9.54E-14

9. 54 E-14 9.54E-14

9. 54 E-14 Molybdenum-99

1. 0E-10 2.49E-13

2. 49 E-13

2. 51 E-13

2. 53E-13

2. 56E-13 Cesi um-134 -

1.0E-10 4.15E-14 4.15E-14 4 ' 15E-14 4.15 E-14 4.15E-14 _ Cesium-137 1.0E-10 3.85E-14 3.85E-14

3. 85E-14

3. 85 E-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 1.32E-13 1.32E-13 1.32E-13 1.32E-13

1. 32E-13 lodine-131 1.0E-10

3. 09 E-14 3.09E-14 3 09E-14 3.11 E-14 3.12 E-14 Strontium-89(3) 1.0E-11 Strontium-90 (3) 1.0E-11 Gross Alpha (3)

1. 0E-11 g,_.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 1989 TABLE B GASE0VS'" TYPICAL" LLD EVALUATION (1) (continued) at(2) I Charcoal -Sample lech. Spec. LLD 15 min __30 min 1 hr 2 hr 3 hr Iodine-131 1.0E-11 . 4. 31 E -14

4. 32 E-14 4,32E-14 4.34E-14 4.36E-14 OTHERS Tritium (3) 1.0E-06 NOTEju (1) All evaluations are in uCi/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 sampling to analysis, at for-charcoal and particulate samples is the time f rom filter removal f rom sampling apparatus to analysis, assuming an average flow of 2 CFM for a 24-hour sampling period. (3) These isotopes are individually evaluated to ensure compliance with: l Technical Specification LLD limits. For tritium, a typical LLD is l'.0E-11 uti/cc..For strontium and gross alpha, a typical LLD is 1. 0E-15 uCi/cc. l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 1989 SOLID WASTE (RAD 10AC11VE SHIPMENTS) A. Solid Waste Shipped Of fsite for Burial.or Disposal (not Irradiated Fuel) 6 Month Est. Tot. 1.- Type of Waste Unit Period Error % 3 3.58E+1 11.00E-1 a. Spent resins, filter sludges, m evaporator bottoms, etc. Ci 7.47 E +1 .11. 50E+1 b. Dry Active Waste,-Compressible Waste-m3 1.59E+2 11.00E-1 Contaminated Equipment, etc. Ci 1.16 E+1

11. 50E+1 c.

Irradiated Components, m3 None N/A Control Rods, etc. Ci None N/A d-Other (describe) m3 1.93E+1 11.00E-1 Composite liners (containing wet rags, Ci 3.98E+0 il.50E+1 resin, mechanical filters and metal oxides in boric acid concentrates) and oil liners 2. Estimate of Major Nuclide Composition (by type of waste) a. Spont resin, filter sludges, evaporator bottoms, etc. (nuclides determined by measurement) Curies-Percent 1. Iron-55 2.32E+1 3.11 E +1 2. Nickel-63 8.56E+0 1.15 E+1 3. Cobalt-60 2.30E+1 3.08E+1 4. Cesium-134 1.72E+0 2.30E+0 5. Cesium-137 4.89E+0 6.55E+0 6. Cobalt-58

1. 27 E +1 1.70E+1 b.

Dry active waste, compressible waste,-contaminated equipment etc. (nuclides determined by estimate) 1. Iron-55 8.01E+0

6. 89 E+1 2.

Cobalt-58 2.89E-1 2.49E+0 3. Cobalt-60 2.21E+0 1.90E+1 4. Nickel-63. 1.01E+0 8.69E+0 c. Irradiated Components N/A N/A d. Other (describe) N/A N/A -Composite Liners (containing resin, wet rags, mechanical filters and metal oxides in boric acid concentrates) and oil liners. 1. Iron-55 1.56E+0

3. 91 E +1 2.

Cobalt-58 1.57E-1 3.94Et0 3. Cobalt-60 1.34E+0

3. 37 E+1 4.

Nickel-63 7.89E-1 1.98E&1 5. Cesium-137

8. 61 E-2 2.16E+0 EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT 2nd HALF 1989 SOLID WASTE (RADIDACTIVE SHIPMENTS)

-3.; Solid Waste Disposition Number of Shipments Type Ouantity Mode of Transportation Destination a) Spent resin, filter sludges, evaporator bottoms, etc. 6 A-LSA Motor Freight Barnwell, SC 1 B-LSA Motor Freight Barnwell, SC Number of Shipments Type Quantity Mode of Transportation Destination b) Dry active waste, compressible waste, contaminated equipment, etc. 40 A-LSA Motor Freight Barnwell, SC Number of Shipments Type Quantity Mode of Transportation Destination c) Irradiated components, control rods, etc. None Number of ShiDments Type Quantity Mode of Transportation Destination d) Composite liners-(containing wet rags, resin, mechanical filters and oxides on boric acid) and oil liners 2 A-LSA Motor Freight Barnwell, SC 1 A-LSA Motor Freight Richland, WA 4. Irradiated Fuel Shipments (Disposition) Number of Shipments Type Ouantity 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 made to the procesi control program? Yes X 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 Administration Control 6.15. Y EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT 2nd HALF 1989 ATTACHMENT 1 INOPERABLE INSTRUMENTATION 1 Pursuant to Technical Specification LC0 3.3.3.10,. the following information is provided concerning radioactive effluent monitoring instrumentation which was inoperable for greater than 30 consecutive days durinq the period July 1,1989 through December 31, 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 L 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 above 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, f rom which daily Turbine Building Sump discharge volumes are obtained, was inoperable during the third quarter of 1989. This instrumentation was damaged by a lightning strike in July 1988, and has been . inoperable intermittently since then. During periods of inoperability, daily Turbine Building sump discharge volumes are estimated as the average of the last three daily volumes recorded before inoperability. During the fourth quarter of 1989, this instrument was not used since procedure changes no

longer required a daily sump discharge volume when radioactivity was absent.

V EFFLUEN1 AND WAS1E DISPOSAL SEMIANNUAL REPORT l 2nd HALF 1989 ATTACHMENT 2 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL Following are descriptions of changes made to the Sequoyah Offsite Dose Calculation Manual (ODCM) during the period July 1,1989, to December 31, 1989, and the affected pages (Revision 23), h 'fgjhjh p N_ =f TJtle: Handling of Changes to the SQN Offsite Dose Calculation Manual RARC OP 8: (: Revision O' Page 5 of 5 Appendix 1 SON 00CM Change Description form Description of change: God RETS reooimennh act inteenord) irrlo g Ot ODcA in a teoria nu wl A 9 % R ntete. LeMo-99-o1 / e Pages affected: 7 eomnun d d;on 6a A/R / /n (,en,rie Justification for change: 3 htOu-99-01. % is ctoIsinn Es hon - M on A rEny, plan ko irvso\\tnud bis bonoff e - }rhte. = Analysis of effect of change on dose calculations, projections, or setpoint calculations: N his th an a t. will hatx eMe d on de sa co I e do M/%. no 1 O co dt'ons 6docinb Cdcubicm3 Air \\ et or no o co u s e, or n_au'tanud i s c ho no od. b ) Attach marked-up pages from the current revision of the SQN 00CM which show

(-

the change. G RARC Review: Date: 9/ RARC Chairman / 0679o/COC4 tva m,c e..i.m

1 et ( O I O$ 7

Title:

Handling of Changes to the SQN Offsite Dose [. Calculation Manual RARC OP 8 Revision 0 Page 5 of 5 Appendix 1 SQN ODCM Change Description form Description of chango:Td is adAtl b dis t ri bt %t Ca steu s a ni llooid t eM\\ud rdua co;nh_uj e, lta a wolin a b .j Pages affected: ) ok lo s 29 e4-log, go d (qq Justification for change:_0hnet 's Le v_ r t r> +i, a 4 on t., no i mt4hodc[eaa i5 hei n a e v k tid b re n e e_ n o u;s43 i c_etli-sn b 3 f is 6 A u 'i e J \\,( D t I Analysis of effect of change on dose calculations, projections, or setpoint' calculations: %i s chan e uill nh ahsc-d ost e al wlldt on 5 ) ncW t cbn s 4 t h o oi n k e a.Ic u l M i n n A. \\ er ..] A p. Attach marked-up pages from the au ]: the change, ent revision of the SQN OOCH which show RARC Review: /N" Date: P RARC Chairman / / ~ 06790/C0C4 . TV A 1929C (ONP l.8U

t

Title:

Handling'of Changes to the SQN Offsite Oose Calculation Manual RARC OP 8 '(- ' Revision'0 Page 5 of 5 i Appendix 1 4 SON ODCM Change Description form Description of change: 6c4tm 12 h slid itsen N n, 9 k nd beldoin k k t>r l b rhltemin:ni o awrxs rnonl4or.sadmieths e w oli4 n ts > c s 4 4 % h. S tr 3.11. 2.1. k ardpin4 hn6ul ort 2 N.t ede,td,ll k, p in\\cui14el Le och edub ab Lennart) -ho U nlh edmiN' n ad 4o A -b hm d % odoal mon Ac udm:n4 u,l// A, ed bast) ors thi s Lo%pa.ris o n. Pages affected:_ te E to s d rooch 5:J los J Justification for change: W3 Li.Il eru hb ectf m :Ms ho - ht d, hren M t ba6t3 on dou redi n5tu) M /t hech- 0 let LMil [oturtonces di nltosi rN Ii m 'd. ~ Analysisofeffectofchangeondosecalculat}9ns, projections,or~setpoint calculations:%is ch a u t. will ' ham no e%, M on riou Mle ola.fion s Q ot orda, c.k ons (%h, mind eeletddicns,. W / / be e A a ndLukthon%kor U LW ttl tW tU $ hMstA nn A mnn atLucthe ( Alr t Idinn ho4L (4h)_ , art r/ rau $ lu Yb, on Mad 4 eAink w:ll no4 chmt Ac,40#in J u enos+ uns YL 0 ) AL O CL SL Qin 5 or 9 fnOne OM L Ik no f hnop b u f.. Attach marked-up pages from the c r the-change, nt revision of the SQN ODCM which show s RARC Review: Date: M RARC Chairman ~ 06790/C0C4 TVA 7929C (ONp.18 5)

~ -- w 3 g WO 1 N.' & s Title. Handling of Changes to the SQN Offsite Oose Calculation Manual RARC OP 8 (f Revision 0 Page 5 of.'5 Appendix 1 SON 00CM Change Description Form Description of change:tStc.4tm 1.t ;s c( nin e, J lx a. distrir>/ ten 4 elera /> __ g Acmed A e s u c)r. c2J c uta4re s 4 b, e 3 Lew pI;o n u. w. A Td,. % e A f l. 2. l Tkh e c lc ul a_4: e n s w; ll rcth er 9h t re keq ralt hm:4 ru%h6u thsr46ulin A <urce,d obed J)~ Pages affected:_14 los 4hemai b 5 -d - lo s a Justification for change: kAou red c alc u ledimw taill enabh Alcock td, dwTch Sru t. bmb rdhen Mn di racnd in a _ Cam oo r i sm, on n. h6 e_k C rd et 1A.M,nn nM re ba,&. redt ~Th e rtlude. ce c., l u n In 6 1A bx 5 ow c-sn se cdh.t tu d e om6 esom, Nt (lea ed or J0 cde ddien R mur h si m r L e-3nd dc4 e,b4 bem u r.) Analysis of effect of change on dose calculations, projections, or setppint calculations: % is eknno i otil he m no <% c4 on dm.o cJe u Lt-H en.s i ne nenuc4hn s - 6bn4 e aleula4;nna m; il ht. c6a'n a t2 - % u wi \\ not.O he. ?- I hastd on NL calcui t) dose _ ^ vbe. e tL S t c. $an boe N-t o lc ulRN eb tu e erve)-ive veLos c eA hen;-b h tJ ce so s i m r/ a4nn.nl 6 td renh she. Lehdelton. On c( more Attach marked-up pages from the c ( the change, ent revision of the SQN 00CM which show s RARC Review: / Date:[ ? RARC Chairman / ~ 06790/C0C4-E^naccow.im

[ kJO .TJ tle: Handling of Changes to the SON Offsite Dose Calculation Manual RARC OP 8 '(4 Revision 0 Page 5 of 5 Appendix 1 SON 00CM Change Description form 1 - Description of change: Tk eonoemb rn-n%la Itu Congygfiut bv-t more. rpsN deu cede s 124;u a m ocaous t no6,1 La r~-ww==ce a e&vkb at dos te <A eduk%is reJr14g or te ll c n si e c il ide#4;bd wo <l;hs m3 k e.xdorme ) her <_lf cabus. o -- esk & k tti L

7 oranns ft ANuo 5 t

OLL 5 litf Itt&OrbidA f O i^ or 3 T v i % m ordL L e ortche M u 0< d Anni 3/Ll Mds R nl L~% r3a rtl o TS bmNS, \\' b b d )os Occeeh I9,d lo A Pages affected: l J -l Justification for change: %s tha w ta ; l l e netMt t (L hS.c t om on clsset - 4o T.s.L; A 6 aj en mor e. ohu retfe_.3Lss unarg d,te dou a m i f 5 d t.L4.n. I4 w:ll etise thm;nn-k A nad fer & " rul:34:e" _ueb ksc n k &cxAend A hen;ks a rt unsd a l Analysis of eff ct of change on dose calculations, p+rojections 3 1 calculations: Q4r>M c4 ccJoutzt4iens w;ll m or tetpoint h elfr e cttJ hv On chonae. edtvIcMion5 cad oco achs har TT. } ou .) J hpIItt n LA idiIl N l-c. H fan 9rV<tbvc.. j, I h 1 Attach marked-up pages from the qu rent revision of the SQN 00CM which s 'i ( the change. / RARCReview:/ Date: M RARC Chairman _/ / ~ i 06790/C0C4 W A 2929c gono.3,g g3 ; - - - - - - - - - - -- ~ - j

p 5f to. Tule: Handling of Changes to the SQN Offsite Dose [- Calculation Manual RARC OP 8 Revision 0 l Page 5 of 5. I 4 Appendix 1 l-SON ODCM Change Descriptton Form Description of change: 6;cMm

l. 3 L, ru ni 3rnbtre) o s (Si < 4'ri /. ( a rtl i

N tlnai ' t il toldi m t o odlena in Medim f.9 aa in c O [t n N t._ d a s c.rI o hi o n. Y e b h iA c!n ri h',td b 6tchien IM lt ArlltM M sMA & nu,.neu e4 %, voo rh ela ele ethv/&4/ms 0 j H Pages affected: lLnn) 13 d loq is jib, a n) 17 o@ lo i c Justification for change: %is c h a tu r ' n i inl i + < r7e re uM on i b % doc aleJ dim ooind rudelole, n And or

C.'

h e r<. eaviecs no '\\a5k&esbirm >o> o et o ' Analysis of effect of change on dose calculations, projections, or setp calculations: %' 4 ch a nJt has c Ne <h o n dak c al c u l4 S N fj pro')<dlM<_ no Or & Eo oinT e cJ c.m i14ie ns. .i A W Attach marked-up pages from the c rrent revision of the SQN ODCH which s the change. RARC Chalrman / / 06790/C0C4 - TVA 7929C (CNAl 441

n ( k/} Handling of, Changes to the SQN Offsite Oose 73t:3.- Calculation Manual RARC OP 8 f (' Revision 0 Page 5 of 5-Appendix 1 SON 00CM Change Description Form Description of change: 6 utinn t d is i re.n o mhe ct2 f, I. 5 ) o md At o,ckrebd d n e., 1;m d s a rt tla r;hir d as o.7 m c J ctr o n.+ b eamme Aw

0) rn ea l atr u n 4 koc bdA dmt awd 0.h 9

0 tr 3 3 ni b b a nu m r t_ rn n r em an. 3 3 Pages affected:_ o,w I6 ' d-lo s t. 3 Justification for change: Thi3 ec carc.u wds tha <u t ln ruf6d4,. nn b d er-t 'u3 shS ;, di en is wn ntu na ru 3 (I. J \\ t Analysis of effect of change on dose calculations, projections, or setpoint calculations: %% t%n ue tJJ3 km na d] r A on dau_ eelesid;m< oca o i b s ada6M cel c ol d on s. ne i ) i p t Attach marked-up pages from the cu rent revision of the SQN 00CH which show i (. the change. RARC Review: /h Date:[ RARC Chairman / / ~ 0679o/C0C4 ~~ @ A 2929C (Chp l 451

4.g 14m y-- T'itle. Handling of Changes to the $QN Offsite Oose Calculation Manual RARC OP 8 ((. Revision 0 Page 5 of 5 Appendix 1 SQN 00CM Change Description Form Description of change: % <_ du c e lg ien,5 li e ni 2 d(I A d mnnkr_,, 4 & Y nb is u n u lul 'h,4a:l ol u oa hnns D etet et u Nee L d.t c:sua bi e o f .s a kneik o o ~ Pages affected: t,o ad si d lor Justification for change:__Th i s c h we 's d e se cim4 tor _ on)_., i no Twt h Aal %, is kin e rtvis,d, Mt et foet ws ne' sos l rallsn 's cu oin d a . (..- i D Analysis of effect of change on dose calculations-projections, or setpoint calculations: T%1 s cbn nr c. w I) kna (LUt d o n r\\ ose_ < al c ulalims no yedstcdi es o c e.d e>oi M c.a.le vlA di m 4 Attach marked-up pages from the c trent revision of the SQN CDCM which show (_. the change. RARCReview:/)w 62-W h Date: / ( RARC Chairman // ~ 0679o/C0C4 TVA 1929c gcNp,g,g gg

9 r{ lo yng : Handling of Changes to the SON Offsite Dose Calculation Manual RARC OP 8 . (. Revision 0 Page 5 of 5 Appendix 1 SQN ODCM Change Description Form Description of change: The contmia4M mnn41, lieu;A dnu t2tu/M:ms bdr mort reMi36 (Le t cen\\aLtb k A. (t% Lsnothk.*tt.Lt]evIOfen,9+ ksit kor I e e Im i g a reluu ~f% rdeklise ta:ll La sllte cY 'dmbh d nr < eIUM a d h1 p ehne,ud C-c c_l{ ne n ns a nd tut anvm Me Waas <t o o d e d ' O \\ 0 a re he w w mEL t.unektels et s) annard Odels a n d e n,nn col h Ts llin,'fs, T O __32 dbreoe)k n J lo A. 4 4 ed m R l Pages affected: o Justification for change: % is eha me wilI e nSe hMtc e w m else r. do 'T.S. - Li m A h e4 al o n !, "et. reedist)i rn x-e et ou e J c v U;m c. {~. G w:l\\ d;m:n A % ntta lac +Le 6tuul tel eJ44/* 4, _k or kvus a

( h m 'h a r<t u e eAdud Analysis of effect of change on dose calculations, projections, or'setpoint calculations

6tdodin4 eed,J11' ens t0lll n5f k CN<cdul Ois d et,o bon Celtv\\1h w and r>rk e c.h w kor 'TS. W ol,% o 3 ,a;ll ke 4 L%$ W 8eri Ity _ NtnLL Yty \\All 06 %t CD h_ m nre ) n dNi. dou co_lculdinn-t I(. Attach marked-up pages from the c r the change. t revision of the SQN ODCM which show RARC Review:_/ N Date:[ II RARC Chairman / / ~ i-06790/C0C4 p -,,, _....,, .i

k r' I O TJtic Handling of Changes to the SQN Offslte Dose . Calculation' Manual. RARC OP 8 (y Reviston 0: s Page 5 of 5' ' Appendix 1-SQN 00CM Change Description Form Description of change: ' t6e elim s M '

2. 3. 3

2. 3. 3. /

Z.3.3 2 2. 3.3.3]

i. 3. 3N a J

z. 3. 3. c, ae ansak<a2 4, t.4

2. J 1,t4y, 2 M.'s,

z.4A asd z.d 5 ke eArm 2.4.b adit > d h c lA e;(> re m d:a ok e o n che ela de 0 ) l Pages affected: 37 M ; 39; Vn -4 to c, Justification for change: do mend oloc u e kna Sk, e fm nn ')ush*birebw (< ruoiced b ~ - (... r Analysis of effect of change on dose calculations, projections, or setpo calculations: This e h a wa, u;Il het< edbM on dou (E colekm f - ,i ho b _OcA t eki m< a d o cink e eJ e uln k; m t o n e-(- Attach marked-up pages from the c nt revision of the SQN 00CM which show the change. RARC Review Date: ' RARC Chairman / 06790/C0C4 hv A]329C (Chp l.e S e

(O W IO

Title:

Handling of Chan9es to the SQN Offsite Oose Calculation Manual RARC OP 8 er l L. - Revision 0 l l Page 5 of 5 Appendix 1 SON ODCM Change Description form Description of change: 6cdi e 7) is re n um becef do .7. 5 on2 retAoelu) c_lari hk :a h4 b lim;4s und n et ()e e o q whe 4'i m

2. A is et n u m beced ko

2. 6 Pages'affected:

t/ Z oh 10 5 43 J mg Justification for change: This cb^ at e rtui u s no % 4 g(, 'os4Oenlim c< a vt r,; 3 0'

• OK no

) (, D Analysis of effect of change on dose calculations, projections, or setpoint calculations: DIS c hu, M ll - hn e dfy o^ g'w caJ e sta4;m no o ?"k 8Ch N 4d p;d e1/cu[off,,3 or } 5 .the change. Attach marked-up pages from the current revision of the SQN 00CM w { ( ~ RARC Chairman // 06790/C0C4 7_ NA. 79??C (CNo lit %t

=

Title:

Handling of Changes to the SON Offsite Dose Calculation Manual RARC OP 8 7E Revision 0 Page 5 of 5 Appendix T SON ODCM Change Description form Description of change: Em nb n e, ia Nh he rem 4;n4 cte a;c, nu uh h 10 LFR co 79 (Eil2Y. Vii Ab u;II bt A Me-mint ht (L h e A3nn sh %t P ilt ul dt3 A san erhe Nt A ose rI hm:4 af 600 m n m /,, u <- l 4 doet lim l4 A> a nui4c - o ~ E We %% \\\\ r-Skckib i 10 C FN 20 Pages affected: ) htL R M lO R b O ~ Justification for change:.1 500 mundtua r lim;4 is Oc hasis inc-Or YYi 90 s in Anm<nd;y is Tral, #>r u Ah, go., 2, {" rLonr4 ko h m,M E-dims.s l A bl 77 t o n u Mca /h,, e_ ,ui l 1t c;s o, m d do; e, Sco mut) txu e d, s e -n cekt_ s o Analysis of effect of change on dose calculations, projections, or setpoint calculations: bLiocin s rw n a (AA M t. Mno bu 14 R et baded in .h, st n n d mos$ IAr;<-L 82 n l, e s, ras o ru. ' tile k te \\ Lu\\Lka b -(emm 500 meemlaae &d on t t d'i ced b kro Ot f490 Vnl} bouw tu r', 4tb,oo' inks hn l k m y SkM bt oik htleno Iiml<,[taSIAt v /h d, k /tc h o r b N o 5 ) ensucu, L b ~ A c hn;4 u;l}0 uNdad NbLJ t t4tt2ia# bc eM,3oiM. q ( tach e rked-up pages from the nt revision of the SQN 00CM which show RARC Review / r. RARC Chairman / / 06790/COC4 iv M m eer:....... l

a l SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL i l i 1 l f Teessen vaune unaMY I h

I 88000 mf NUCLEAR PLagT 0FFSITE DORE PAf1VLATION " JAL DATES OF REVISIONS Original ~0DCN 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** l Revision 8 12/16/83** 2 Revision 9 03/07/84** I Revision 10 04/24/84** Revision 11 08/21/84** Revision 12 02/19/05** Revision 13 12/02/85 Revision 14 04/14/86 i Revision 15 11/05/86*** Wevision 16 01/16/87** Revision 17 10/28/87** Revision 18 01/05/88** l Revision 19 03/30/88** ) i Revision 20 07/19/86** t l Revision 20A 12/14/88** Revision 21 02/15/89** Revision 22 I 06/01/89** Revision 23 6/28/89 & 9/15/89**** i 5ch Mn ,p,,oved 8, RARCCtgrimli / Approved bye WASU Date on.See, = 0e0. .i Low Power license for Sequoyah unit 1

• • RARC Meetint date Date opproved by RARC Chairisan
    • • Revision 23 Laplements the Nuclear Data Effluent Manatoment Software. This ODCM revision and the software will be implemented concurrently on October 9, 1989. Releases ande during the month of i

October prior to the software implementation will be backfitted to comply with this revision. 00101

~... _ -. _. _ - REQUDYAH MUCLEAR PLANT OFFEITE D0AE CALCULATIDE M&HUAL EFFECTIVE PACE LISTIBC Revision 23 { taga Revision Listing of Dates and Revisions Revision 23 Table of Contents (all pages) Revision 23 All Pages Revision 23 l i i l t r i l I h o i IPL-1 i-l 00101

l SE000YAH NUCLEAR PbANT pFrSITE DDSE CALcutATIDs MANUAL TABLE OF CONTENTS Revision 23 Fase 1.0 GASEOUS EFFLUEHTS 1 l 1 1.1 RELEASE P01RTS DESCRIP110N 1 1.2 D0BS RATE 2 j i 1.2.1 REQUIRENENTS 2 l 1.2.2 REPORTIltG LIMITS 3 i 1.2.3 20BLE GAS DCRE RATES 3 i 1.2.3.1 Total ant ~ Dona mata 3 1.2.3.2 Skin Dona Rata 4 1.2.4 1-111, 1-113. TRITIUM AND ALL RADIONUCLIDER 1R PARTICULATE l FORit WITH RALF-LIVES OF GREATER THAN I DAYS - ORGAN D0RE RATE 5 i i 1.3 RADI0 ACTIVE GAREQUS EFFilIENT MDRIT011RG 1RSTRtRWITATION 6 1.3.1 REQUIREMENT 6 1.3.2 MLMPE SAMPLING 7 1.3.3 1RSTRtBIENT SETPOINTS 3 1.3.3.1 Emmacted Monitor maanonna 3 1.3.3.2 Calculated Maximum Satooint s 1.3.3.3 Bernal Default Satooint 9 t 1.3.3.4 Actual Nonitor Satooints 10 1.4 DOSE - EDELE GASES 11 1.4.1 REQUIREMENTS 11 i 70C-1 00101 + 4 +, ,e w,- v.- ee-- ,--e.---3-- -a

EEDUOYAH EUCLEAR PLANT oft $1TE D0AE CALCULATION MANUAL TOLE OF CONTENT $ Revision 23 Pa6e 1.4.2 CUMULATIVE Dost PAf.CUllTIONE - R0kt

• CARER 12 1.4.2.1 "--- dans t o air 12 1.4.2.2 Rata dona to air g3 1.4.2.3 C==>1stiva haes - Bahia can 13 1.4.2.4 Cannarison to Limita 13 1.5 etmart2TrYa notn - 1 111. 1 112. TarTrun Ann mAnf0NUctfntt IB PARTICULATE FORM 14 1.5.1 RROUIREMENTS g4 1.$.2 DDRR nUR TO I-111. 1 111. TRffft3 Ann Af_f. RAnIONUCLIDES IR PARTretit ATE PORN WITH MAf.*-LIVER OF CDR ATER TRAW 3 DA}g gg 1.5.2.1 Or=== dama calculatian 16 1.5.2.2 Cumulativa Domas 17 1.5.2.3 e===riaan to Limita 17 1.6 GAREQUS RADWASIX TREATHERT gg 1.6.1 REQUIREMENTS gg 1.6.2 DORE PROJECTIONS

.g9 1.6.3 CABROUR RADWARTE TREATHERT SYSTEM DEsCRIPT10m g, 1.7 OUARTERLT DOSE CALCULATIONS 20 1.7.1 MORLR CAA - GABBRA AIR DORE 20 1.7.2 30RfW CAE - RETA AIR nott 20 1.7.3 *AnIOroninR. PAmTIcutaTe Ann Tattrun - mArfutas Oncin nost 21 TOC-2 00101 1 1

~. _ i SEQUDYAN NUCLEAR PLANT prrsin DOSE cALCuuTION MANUAL TABLE OF CONTErrS Revision 23 pa8e 1.7.4 POPULATION DOSES 22 1.7.5 REPORTING OF DOSES 23 1.8 GARIOUS RELEASES - Dona Factora 24 1.8.1 PASTURE GRABS-COW /G0AT-MILE INGESTION D0RE FACTORS - Rept 24 1.8.2 STORED FEED-COW / GOAT-MILE INGESTION DOSE FACTORS - 71CSi 24 1.8.3 PASTURE GRASA-REEF...INGEAT10R D012. TACT 018.- Rupi 25 i 1.8.4 STORED FERD-REEF INGESTION DOSE FACTORS - Rngi 26 l 1.8.5 FRESN LEAFY YEGETABLE INGESTION DORE FACTORS - Ryyi 26 j 1.8.6 STORED YEGETABLE INGESTION DORE FACTORS - Rygg 27 l L 1.8.7 TRITIUM-PARTURI GRASS-COW /C0AT-MILE DORE FACTOR - RCTF 28 1.8.8 TRITI E STORED FEED-COW /G0AT-MILE DORE FACTOR - RCTS 28 i,[ 1.8.9 TRITI h PASTURE GRASS-R H F D0RE FACTOR - RNT 29 f 1.8.10 TRITI E STORED FEED-RH F DOSE FACTOR - RMTS 29 l 1.8.11 TRITI N FREEN LEAFT VEGETABLES DOSE FACTOR - Ryyy 30 1.8.12 TRITIUM-STORED VEGETABLES DORE FACTOR - Rygg ~30 1.8.13 INEALATION DOSE FACTORS-Rgg 31 t 1.8.14 GROUND PMME DOSE FACTORS - Rgg 31 ( 1.9 DISPERSION METHODOLOGY 32 l 1.9.1 AIR CONCINTRATION - Y (pC1/s8) 32 l !- l 1.9.2 RELATIVE CONCERTRATION - 1/0 (esc /a8) 33 1-TOC-3 00101 1 ~. .... _..... _. ~.., -

+;. ". nv p p eg. I gi l SEOUOYAH MUCLEAR PLANT { OFFRITE DORE t'A1.CtfLAff 05 MANUA1. I TABLE QF CONTENTS Revision 23 page L 1.9.3 ELATIVE DEPOSITION D/0 (a-a) 34 1 2.0 LIQUID RFFLUERTS 35 4 2.1 RELEA$$ P01ETS 3$ 2.2 CONCENTRATIOR 37 2.2.1 RROUIRElEENTS I g' + f 37 33 l 2.2.2 MPC-SUN OF THE RATIOS 2.3 #Anf0 ACTIVE LfollID EFFt.tres? MONITORING fBBfttBEtuTATION 39 3 2.3.1 REQUIREMEETS ' N= '"'* 5 39 j 2.3.2 RELEASE SAMPLING 40 l 2.3.3 IRSTRtalEET SETPOINTS i .p,6 41 2.3.3.1 Exnacted Monitor Reananaa f, 41 2.3.3.2 Calculated Mart=== Monitor Satnaint 41 ... v 2.3.3.3 Ramal Darault setnaint 43 2.3.3.4 Aglyal Manitor Satooints 43 2.3.4 Peat-talamaa Analvala -,g m.... 4 4. # - 2.4 00H

• PWM*'

45 i . c,, i. 2.4.1 REQUIREMENTS q. .r 45 ...,-v.- 2.4.2 CIERHATIVE L10UID EFFLUERT DOSE CALCULATIOMS 47 i .. # 4.. 2.4.2.2 Monthly Dona Calculations +--******"*4 43 - M e.en>M$ P l - ~ i 2.4.2.3 Cumulative Donaa 43 i . -...a. V-TOC-4 u ' t i'* 5 + NdW * .,f.agJed W ine ..s,. ,s. & ts e - ...r.o u felp.6...- .M';ee, 00101 .s s e,. - - - _. ,,,,...c..- v -w. - - - -. -,.. - -..,, -.. - ~.. -. - -. - ~

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RE000YAR EUCLEAR PLANT OPPSITE DOSE CALCULATIOE MANUAk TABLE OP courEurs i Revision 23 page 2.4.2.4 Cannarison to Limita 43 2.5 LIDUID WARTE TREATMENT 49 i 2.5.1 REQUIREERT 49 2.5.2 LIQUID RADWARTE TERATMENT SYSTEM 50 2.5.3 DDSI PRO.IECTIORS 50 2.6 00ARTERLT D012 CALCU1ATIDEA 51-I 2.6.1 WATER IEGESTIOR 51 2.6.2 F185.IEGESTION 52 I 2.6.3 BHORELIEE RECREATIDs 52 2.6.4 TOTAL MAIDRBI IEDIVIDUAL D0RE 53 2.6.5 POPULATION DDRES 53 1 2.7 LIQUID DORE PACTOR EDUATIORS 56 l 2.7.1 WATER INGERTION - Awig (ares /hr per pC1/al) 56 2.7.2 FIAR IBGERTION - Argt (area /hr per PC1/al) 56 2.7.3 SBORELINE RECREATION - Atit (aren/hr per pCi/al). '56 3.0 Radiolomical Pavironmental Manitorina 58 ( 3.1 MINIMUM REQUIRED E NITORIEG PROGRAM 58 l 3.1.1 v .o 58 3.1.2 M EITORING PROGRAM 59 3.1.3 DETECTION CAPARILITIts 60 700-5 1 ) h' s 00101 1 s t iH'. l l l -ce je..<

i EE000YAN NUCf. RAD Pt.AwT QffjITE DOSE CALCULATION MANUAL j TAmt.e OF CONTENTS Revision 23 l Pa6e 3.2 LAND USE C2HSUS 61 3.2.1 REOUltEMENT 61 3.2.2 LAND USE CENSUS 61 3.3 INTERL&ADRATORY COMPARISOE PROGRAM 63 3.3.1 REQUIREMENT 63 3.3.2 1NT**t AkaR1 TORY C^*ARIRON PROCRAM 63 4.0 TOTAL DQ2E 64 4.1 REQUIREMEET 64 4.2 A= tat. mArrent runivinttAv. nostR - TOTAL mmpoaiin noBE 65 $.0 REP 0kTIEQ REQUIREMENTS 66 5.1 A'nntar. manrotocif*Av. ENVIEG__srAL OPenAff ac LaMRT 66 5.2 neur. AmeriAv. minr0 Active Errurent met =Aer La-6t? 66 TOC-6 00101

-s l SEQD0YAN NUCLEAR PLANT Orr81TE DO8E cALcuLAT10m nANUAL 1 LIAT OF TAktM l Revision 23 PaSe 1.1 RADI0 ACTIVE GA8EOUS WA8TE MONITORING SAMPLING AND ANALT815 PROGRAM 64 i 1.2 JOINT FERCERTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES 72 1.3 SQN - 0FFSITE RECEPT 0R LOCATION DATA 79 l 1.4 D0tt FACTORS FOR SUBMER810N IN N0BLE CASES 80 l y 1.5 RADI0 ACTIVE GA8EOUS EFFLUENT MORITORING INSTRUMENTATION 81 r 1.6 RADI0 ACTIVE CA8ROUS EFFLUENT MONITORIM INSTRUMENTATION l SURVEILLANCE REQUIREMENTS 83 I.7 SECTOR ELEMENTS CONSIDERED FCR POPULATION DOSES 45 t 1.8 POPULATIOW WITHIN EACE SECTOR ELEMENT 86 1.9 INGESTION DOSE FACTORS 88 1.10 RADIONUCI.IDE DECAY AND STARLE ELEMEFT TRANSFER DATA 95 i 1.11 DOSE CALCULATION FACTORS 98 1.12 INNALATION DOSE FACTORS 100 1.13 EXTERNAL DOSE FACTORS FOR STANDIM ON C0FtAMINATED GROUND 108 2.1 RADI0 ACTIVE LIQUID WA8TE 8AMPLIM' AND ANALTSIS PROGRAM 110 2.2 kAD10 ACTIVE LIQUID EFFLUENT MONITORIM INSTRUMENTATION 114 2.3 RADI0 ACTIVE LIQUID EFFLUENT MONITORIM INSTRUMElf!ATION SURVEILLANCE REQUIRRMENT8 117 2.4 RECEPTORS FOR LIQUID DOSE CALCULATIONS 119 2.5 RIDACCUltiLATION FACTOR 8 FOR FRE8HWATER FISM 120 l TOC-7 00101 a

. ~. _ SE000YAH NUCIPA9 PtAwT OFFSITE DORE cafCULATION MANUAL LIST OF TARtat Revision 23 page r 3.1 RADIOLOGICAL ENVIROINENTAL MONITORING FROGRAM 121 3.2 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION 124 3.3 REPORTING LEVEL 8 FOR RADIDACTIVITT CONCENTRATIONS IN ENV!k0lWEENTAL SAMPLES RADIO W ICAL ENy,30NERNTAL MONITORING pgog,Ag NNE " E"NGNIE3' **87a 8ADIOL0cIce MONIT0nING 2'2 ""*'" =a ru r - = 0ap,=,C N, ,0,,,,,,,,,,,,,, 4 L l l l e 70C-8 00101 ---.a.

13000YAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL LIST OF FIGURES Revision 23 page 1.1 GASEOUS EFFLUENT RELEASE POINTS 135 j i 1.2 AUKILIART AND SHIELD BUILDING VENTS (DETAIL) 136 1.3 SQR LAND SITS BOUNDARY 137 I 1.4 GASE0US RADWA8TE TREATMENT SYSTEM 138 i 1.5 PLtME DEPLETION EFFECT FOR GROUND LEVEL RELEASES 139 1.6 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 140 1.7 RELATIVE DEPOSITION FOR GROUND LEVEL RELIA 8ES 141 i 2.1 LIQUID EFFLUENT RELEACE POINTS 142 2.2 LIQUID RADWASTE SYSTEM 143 3.1 RADIOLOGICAL INVIR0lttENTAL SAMPLIM LOCATION 8 - WITHIN 1 MILE OF PLANT 144 3.2' RADIOLOGICAL ENVIROIStENTAL SAMPLI M LOCATIONS - WITHIN 1 TO 5 MILES OF PLANT 145 l 3.3 RADIOLOGICAL ENVIROIDERNTAL SAMPLI N LOCATIONS - GREATER TRAN 5 MILES OF PLANT 146 l l 4 TOC-9 00101

i SQN ODCM l Revision 23 l Page 1 of 146 l 1.0 GASEQUS EFF12ENTS 4 1.1-RELEASE POINTS DESCRIPTION l l. There are six exhausts at Sequoyah Nuclear Plant that are monitored for i . airborne effluents.~ These ares a Condenser Vacuum Exhaust for each unit, a Service Building Exhaust, an Auxiliary Building Exhaust and a Shield Building Exhaust for each unit. Figure 1.1 provides an outline of the airborne effluent release and discharge points with associated radiation monitor identifications, t l Condenaar Vacuum Exhaust I The Condenser Vacuum Exhausts (CVEs) are located in the turbine building. They exhaust at a maximum design flow rate of 45 cubic feet per minute. They are monitored by radiation monitors (1)- and (2)- 5 90-99 -119. Earvica Buildina Vant The Titration Room, Chemistry Lab, Not Shop, and Health Physics Lab all exhaust to the Service Building Vent. This exhausts at approximately l 14,950 cfm and is monitored by radiation monitor 0- 5 90-132. 'I l. j Auxiliary Buildina Exhaust (see Figure 1.2 for detail) The annulus vacuum prising systes exhausts through the containment vent to the Auxiliary Building. The Auxiliary Building ashaust aimes with the General Exhaust System and they cumulatively exhaust at a maximum design flow of 228,000 cfa. The exhaust is monitored by radiation monitor 0- W 90-101. shield Ruildina Vent (see Figure 1.2 for detail) i The Auxiliary Building Gas Treatment System (ABGTS) draws from the Auxiliary Building and exhausts to the waste gas header. There are nine Wasta Gas Decay Tanks (WGDTs) that also empty into this header. Either ABGT8 or the Emergency Gas Treatment System (EGT8) is run to release a WCDT. Each WGDT has a design capacity of 600 cubic feet and a design release rate of 12.5 cis. Both the Containment Purge and the Incore Instroent Room Purge from each unit tie into the waste gas header. The e Containment Purge exhausts at a maximum of 28,000 cfm and is monitored by radiation monitors (1)- (2)- 5 90-130,'-131. If the Incore Instrument Room Purge-is operating exclusively, it exhausts at 800 cfa. thuler emergency conditions, and sometimes during normal operation, the 3GTS is used to draw a vacuum in the annulus and exhaust to the Shield Building Vent. Auxiliary Building Isolation starts both the ABGTS and ECTS. The common header exhausts to the Shield Building Exhaust. There is one exhaust for each unit. This exhausts at a maximum design flow of 26,000 cfm and is monitored by radiation monitors (1)- (2)-RM-90-100. l 00631 e w -e --e.-es

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u a SQN ODCM 2evision 23 L Page 2 of 146 1.2 DOSE RATR 1.2.1 v - 4 " l The dose rate due to radioactive asterials released la gasseus affluents to ' areas at er beread the site boundary (unrestricted area) (see Figure 1.3) shall be limited to the following

a. For noble gases: Less than er equal to 500 aren/yr to the total body ami less than er equal to 3000 ares /Fr to the skia, and

b. For lediao-131. Iodine-133, Tritius, and for all radicans 11 des la partiestate form with half-lives greater than 8 daret Less than er equal to 1500 aram/yr to any organ, his requirement is applicable at all tiasa.

This requirensat is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units en the site will be within the annual dose limits of 10 CFs Part 20. The annual dose limits are the desea l associated with the consentrattens of 10 CFs Part 30, Appendia B, Table !!, Columa 1. These limite provide reasonable assurasse that radiomative matettal discharged La gaseous affluents will met result la the esposure of a member of the public, either withis or outside the ette bondary, to amenal svarage concentrations azeeeding the limits specified la Appendia S. Table II of le l CFR Part 20 (10 CFR Part 20.106(b)). For membere of the publis uhe may at l times be within the site boundary, the occupaaer of the ladividual will be suffittently low to ceaponsete for any increase is the atmospheria diffustoa [ facter above that for the site boundary. The specified release rate limits restrict, at all times, the eerresponding samma and beta dose rates above background to an individual at er beyond the site boundary to less than er equal to 500 aren/yr to the total body or to less than er equal to 3000 area /yr to the skin. These release rate liatte aise restrist, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-tafant pathway to less than er equal to 1500 ares /yr for the nearest l cow to the plant. This requirement applies to the release of gaseous L effluents trea all reacters at the site. For units with shared redweste treatment systems, the gaseous effluents from the shared systems are l-proportieaed amens the units sharing that system. If this requirement le met met, the folleving setten will be performed: With dose rate (s) esseeding the above limits, without delay restgre the release rate to within the above limit (s). i-L To ensure that this requirement is met The dose rate due to asble gases in gaseous offissats shall be determined l i to be within the above limits la accordance with the methodology and i parameters la secties 1.2.3, and 00631

)Y) SQN ODCM { Revision 23 Page 3 of 146 The dose rate due to I-131, I-133, Tritium, and for all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents aball be determined to be within the above limits.in accordance with the methodology and parameters in Section 1,2.4 and by obtaining representative samples and performing analyses in accordance with the l sampling and analysis program specified in Table 1.2.. 1.2.2 rep 0RTING,(lHlIl i 10 CFR 50.73 requires that any airborne radioactivity release that exceeda 2 times the applicable concentrations of the limits specified in Appendix B, Table II of 10 CPR 20 in unrestricted areas when averaged over a period of one hour be reported to the NRC within 30 days. For the purposes of meeting this requirement, it is assumed that the dose rate limits stated above are the result of offsite concentrations equal to those listed in Appendia B, Table II of 10 CFR 20. 1.2.3 B0BLE ras DOSE RATES i Dose rates are calculated for total body and skin due to submersion within a cloud of noble gases using a semi-infinite cloud model. t' 1.2.3.1 Total nody nome mate The dose rate to the total body, DRTB in ares / year, is calculated using the following equations DRTB.(X/Q)FICgDFBt (1.1) l t 1 where i X/g . relative concentration, s/m8 Relative air concentrations are calculsted for the land-site boundary in each of the sixteen sectors as described in Section 1.9.2 using the historical meteorological data for the period 1972-1975 given in Table 1.2. For dose rate calculations, the highest value from the sixteen land-site boundary locations is used. i = 5.125-06 s/m8 (from Table 1.3). L F = flevrate of effluent stream, ec/s. l Cg = concentration of noble gas nuclide i in effluent stream, l pC1/cc. i Dr81 = total body dose factor due to samma radiation for noble gas nuclide 1, aram/y per pCi/m8 (Table 1.4). 00631 y# ~ ~,. - r ,_.._1-

b SQN ODCM Revision 23 Page 4 of 146 1.2.3.2 Skin Dean Rate The dose rate to the skin, DRs in ares / year, is calculated using the following equation: s.(X/Q)FICg(Drst+1.11Drg) DR y (1.2) 1 where X/Q = relative concentration, s/a, gelative air s concentrations are calculated for the-land-site boundary in each of the sixteen sectors as described in Section 1.9.2 using the historical meteorological data for the period i 1972-1975 siven in Table 1.2. For dose rate calculations, the highest value from the sixteen land-site boundary locations is used. l = 5.123-06 s/as (from Table 1.3). I F = flowrate of effluent stream, ec/s. Cg = concentration of noble gas nuclide i in effluent stream, pC1/ce. DP8g = skin dose factor due to beta radiation for noble gas nuclide 1, ares /y per pC1/as (Table 1.4). 1.11 = the average ratio of tissue to air energy absorption I i l coefficients, ares /arad. DF g e does conversion factor for external samma for noble gas y ( nuclide i, arad/ year per pC1/m8 (Table 1.4). l I e. G 00631 O i n

son oDen 8evisien 23 Page 5 of 146 1.3.4 1 111 1-11n. vertitas aun A? t mAmrnener vnna IB DARTrern ATR F1 m m mite.t.i.a at anniven Team a niva. ama*= maen mATm Organ does rates due to 1-131, I-133. Tritium and all radieneelidea la partleulate fers with half-lives of greater than 8 days Da. La er aren/ year, are calculated for all age groups (adult, teen, abild, and infant) and all ergana (bene, liver, total body, thyroid, kidney, lums, j and St Tract) estas the folleving egnatient ta,,ge F[ Oy(2/Q)(8tT+ECTP]e!C[(X/g)3gg,(Dg)[gCPi+301)) (1.3) / L .orei F = fleyrate of effluent stream, se/s. Cg e sessentratten of tritius La effluent stream, pC1/se. 14 / a relative esseestraties, s/a8 Salative air sessentrations are calculated for the land-aite boundary in saak of the ) sisteen aestors as described la Sectica 1.9.3 ustas the histerteal esteetelestaal data for the period 1973-1975 given la table 1.3. For dose rate calculattens, the highest value from the sixteen land-atte boundary lesattens is used. 5.135-04 s/as (frea table 1.3). ) 317 e inhalaties dose faster for tritium, area / year per pC1/m8 Dese faster is salentated as desaribed la Sestles 1.8.13. RCTP = trans-cow-silk dose faster for tritium, area / year per s i pC1/a. Dese faster is calestated as described in Section 1.8.7. Cg = esmaestraties of muslide i in effluent stream, pC1/se. Sgg e tahalation does factor for each identified auslide 1 ares / year ^ s per pC1/a. Dese factors are calenlated as described in geetten 1.8.13. D/Q = relative depeetties, 1/a, gelative depeettien is s 4 salculated for the land-site boundary la each of the sisteen sectors as described la Seetles 1.9.3 matas the historical i meteorelegical data for the period 1973-1975 sites la Table 1.3. For dose rate calculations, the highest value from the sixteen land-site boundary lesattens is used. 4 = 1.393-08 1/as (free Table 1.3). Egyg a trase-sow-ellk dose faster for each identified nuclide 1, a8 eres/ year per pC1/s. Dese factors are calculated as described ta Secties 1.8.1. Egg a ground plane dose factor for each identified nuclide 1, s a wares / year per pC1/s. Dese factors are calculated as described la Secties 1.8.14. k The maalaus organ dose rate is selected from emens the dose rates calculated for all the organs and all age groups. 00631 4 -,wm-u.-..--w,-,. n.m-.wcuwm..-,-- ,,.m..,--,,.--n,----n_,,,, .~ -v--

SQM ODCM Revision 23 Page 6 of 146 1.3 RAnfoAbTfva citrous trrtimmt noNIToniNC fNATRUidwrAvfoN 1.3.1 RE0111 RELENT The radioactive gaseous effisant monitoring instr oentation chamaels eheva in Table 1.5 shall be operable with their alarm / trip setpoints set-to ensure that the limits of goetion 1.2 are not exceeded. The alarm / trip setpotats of these chamaels shall be determined la accorfance with the methodelegy and parameters la Secties 1.3.3. This regoiressat is applicable as aheva la Table 1.5. The radioactive gaseous effisent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous i effluents. The alarm / trip setpoints for these instruments shall be l calculated in accordance with the procedures in section 1.3.3 to ensure i that the alarm / trip will occur prior to exceeding the limits of l 10 CFR Part 10. i The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and I i 64 of Appendix A to 10 CFR Part $0. If this requirement is not met, the appropriate following action (s) will be performed: l With a radioactive gasoons effluent moniterlag lastrumentation s. L chamael alarm / trip setpoint less cesservative than required above, without delay suspend the release of radioactive gaseous effluenta i monitored by the affected chamael, declare the channel inoperable, or change the setpoint se it is acceptably senservative. b. With less than the miatam amber of radiosetive gaseous effluent asaltering instruneataties channels operable take the acties sheva in Table 1.5. Ezert best efforts to return the lastruments to operable l status within 30 days and, it unsuccessful, explaim in the next semi-Annual Effluent Report why the Laoperability could not be corrected within 30 days. To ensure that this requirement is, met: Bach radioactive gaseous effluent nomitortag instroentaties shamael shall be demonstrated operable by performance of the channel cheek, source check, chamael calibraties, and chamael functional test operations at the fregnancies aheva la Table 1.6. 00631 1 i

SQN ODCM Revision 23 Page 7 of 146. 1.3.2 RELEASE SAMPLING Prior to each release (excluding an Incore Instrument Room Purse), a grab sample is taken and analyzed to determine the concentration, pCi/cc, of each noble gas nuclide. On at least a weekly basis, filters are analysed to determine the amount of iodines and particulates released. Composite samples are maintained (as required by Table 1.1) to determine the concentration of certain nuclides (8r-89, 8r-90, and alpha emitters). For those nuclides whose activities are determined from composite samples the concentrations for the previous composite period will be assumed as the concentration for the next period to perform the calculations in Sections 1.2, 1.4, 1.5 and 1.6. The actual measured concentrations will be used for the dose calculations described in Section 1.7. ) 4 00631 i

I l SQN ODCM Revision 23 Page 8 of 146 1 1.3.3 INSTttBIF.NT SETPOINTS 1.3.3.1 n==aeted monitor mannamme For each release, the expected monitor response, R in cpa, is calculated using I i the following equations R= 3 + E offt Cg (1.4) i where s = monitor background, cym. - efft = efficioney factor for the monitor for nuclide 1, cpm per pCi/ce. Cg = esasured concentration of nuclide 1, pC1/ce. t For the noble gas response, the summation in the above equation will be i b performed over all sensured noble asses. Similarly, the responses for '~ todines and particulates would sua over all seasurud iodine and particulate nuclides respectively. 1.3.3.2 caleninted aant-- tecnotat For each release from a release point, a calculated maximum setpoint is detarained for the appropriate monitor which corresponds to the most restrictive dose rate limit. This maximum setpoint is calculated as l follows: 1. The ratio, r, of the dose rate limit to the calculated dose rate for the release is obtained using the following equations s DR11a r= (1.5) where i DR11a = the dose rate limit, area / year. = 500 ares / year to the total body for noble gases. = 3000 area / year to the skin for noble gases, and = 1500 area / year to the maximum organ for lodines and particulates. DR = the calculated dose rate for the release, area / year. e DRyg for total body (as described in Section 1.2.3.1),, = DRs for skin (as described in Section 1.2.3.2), and i. = Dtors for maxis,% orten (as described in Section 1.2.4). L 00631 l l v r-,---,. v w .~,-e-,- -w-- ---.--,-.*--.-,-r er-,--- -r

SQN ODCM { Revision 23 j Page 9 of 146 2. The calculated maximum monitor response R11a in epa, corresponding to the dose rate limit is determined using the following equation: R11a = (r(R - B)) + B (1.6) where 1 = ratio of dose rate. limit to calculated dose rate for the i r release, as calculated above. For noble gases, the amaller c,f l i the.two ratios for total body or skin is used. R = expected monitor response (as calculated in Section 1.3.3.1), cya. b = monitor background, cpa. 3. The calculated maximum setpoint, Saan in epa, corresponding to the dose rate limit is calculated using the following equations Saan = ((Ae8F)(211a - 3)) + B (1.7) ') where A = dose rate allocation factor for the release point, dimensionless. The dose. rate allocation factors for release points are defined in approved plant procedures. SF = safety factor for the monitor, dimensionless. Safety factors for each monitor are defined in approved plant precedures. R g. = the calculated monitor response, as calculated above, cya. i B = the monitor background, cya. 1.3.3.3 Normal Default setnaint i A normal default setpoint is determined for each monitor. The default setpoints for each monitor are defined and documented in approved plant + procedures. The default setpoints should be set high enough such that In most cases,-the value will not need to be changed for each release. default setpointe should be low enough, however, to ensure that the limits The given in Section 1.2.1 are not violated, and to ensure that unexpected releases are identified. b 00631 i i,

i l t: SQN ODCM Revision 23 Page 10 of 146 l-1.3.3.4 Actual Monitor Betoointa l The setpoint chosen for a monitor for each release is determined as follows:

1. IF the calculated maximum setpoint is less than the normal default, THEN the setpoint shall be set equal to the calculated nazimum setpoint.

2. IF the calculated maximum setpoint is greater than the normal default, AND XI times the expected monitor response is less than the normal default setpoint, THEN the setpoint shall be set equal to the normal default setpoint.

3. IF the calculated maximum setpoint is greater than the normal default,

) AND XI times the expected monitor response is greater than the i normal default setpoint, THEN the setpoint shall be set equal to 1 X ' times the expected response. i t i l L n I 1 X is an administrative factor designed to account for expected variations in monitor response. It will be defined in approved 1 plant instructions. 00631 j n4-v m-me--.+ a-. -,nmm-w

_ ~.. 1 SQN ODCM y Revision 23 i Page 11 of 146 1.4 DOSE - ROBLE GASES 1 1.4.1 REQUIRDIENTS j The air dose due to noble gases released in gaseous effluents from each reactor unit to areas at or beyond the site boundary (see Figure 1.3) shall be limited to the followingt

a. During any calendar quarter 1.eas than er equal to 5 arad for gassa radiation and less than or equal to 10 ared for beta j

radiation and

b. During any calendar yeart Less than or equal to 10 mrad for gamma radiatica and less than or equal to 20 mrad for beta radiation.

This requirement is applicable at all times. L This requirement is provided to implement the requirements of Sections II.B,III.A and IV.A of Appendix I, 10 CFR Part 50. The requirement i implements the guides set forth in Section II.B of Appendix I. The action to be taken provide the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low a reasonably achievable." The surveillance implements the requirements in Section III.A of Appendix I that conformaner, with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a l-member of the public through appropriately modeled pathways is unlikely + to be substantially underestimated. The dose calculations established in Section 1.4.2 for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109. " Calculation of Annual-Doses to Man from Routine Releases of Reactor Effluents for the Purposes a of Evaluating Compliance with 10 CFR Part 50, Appendia I," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in toutine Releases from Light-Water Cooled Reactors," Revision le July 1977. The ODCM equations provided for determining the air doses at the site boundary are based upon the historical average atmospheric conditions. If this regsfransat is not met, the following acties will be performed: With the calculated air dose from radioactive noble gases in gaseous efflesats escoeding any of the above limits, prepare and submit to the Ceamission within 30 days, pursuant to Technical Specification ) 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. 00631 n. __,-.._,,___,,,,.,._m..,.,_,._.,_,.c,.,r.,y_._.,

_ ~. _. _ _.... _ _ _ _ _. _ i SQN ODCM Reviaton 23 Page 12 of 146 To ensure that this requirement is met Cumulative dose contributions for the current calendar guarter and i current calendar year for noble gases shall be determined in accordance with the methodology and parameters in Section 1.4.2 at l 1 east esce per 31 days. 1.4.2 CUMLfLATIVE DORE cAf CtfLATIONS - NORYD cAREE t Doses to be calculated are gaana and beta air doses due t exposure to an j infinite cloud of noble gases, these doses will be calculated at the land-site boundary location with the highest annual-average X/Q based on 1972-1975 meteorological data (Table 1.2). This location is chosen from the site boundary locations listed in Table 1.3. Dispersion factors are calculated using the methodology described in Section 1.9.2. i No credit is taken for radioactive decay. l 1.4.2.1 c--- done to air I i The gamma air dose, Dy in arad, is calculated for each release using the following equation: Dy = 1.93-06 (X/q) g Qg DF g T (1.3) y i where: 1.9E-06 = conversion factor, years per minute. X/Q = highest land-site boundary annual-average relative concentration, 5.12x10-s s/as (from Table 1.3). Qg = release rate for nuclide 1, pCi/s. DF g a dose conversion factor for external gasmia for nuclide i y (Table 1.4), arad/ year per pC1/m8 T = duration of release, minutes. The gamma-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 1.4.2.3. 1 1 00631

SQN ODCM Revision 23 Page 13 of 146 1.4.2.2 Rata done to air The beta air dose, D3 in arad, is calculated for each release using the following equation: Dg = 1.9E-06 (X/Q) g gg prgg y (1,9) where: 1.9E-06 = conversion factor, years per minute. [ X/Q = highest land-site boundary annual-average relative concentration, 5.12:10-s e/a8 (from Table 1.3). Qi = release rate for nuclide 1, pC1/s. l Drgt = dose conversion factor for external beta for nuclide 1, l g arad/ year per pC1/as (from Table 1.4). 1 T = duration of release, minutes. The beta-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 1.4.2.3. 1.4.2.3 c - lative nome - nobin c== l Quarterly and annual suas of all doses are calculated for each release as described below to compare to the limits listed in Section 1.4.1. 1 ( For noble gases, cumulative doses are calculated for samma and beta air doses. Doses due to each release are summed with the doses for all previous release in the quarter or year to obtain cumulative quarterly and annual doses. 1.4.2.4 c = =riaan to Limita l i The cumulative calendar quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance. -i i k 00631 \\ ~ -- - - ~--. - - - -- -- - - - - - ~ ~ ~ - ' - ~

SQN ODCM Revision 23 Page 14 of 146 i 1.5 ctBRfLAvivE Dost - I-131.1-133. TRITIUM Ann ninIONUctfDrs tw PARTICUIATE FORM 1.5.1 REQUIRENERTS i The dose to a member of the public from I-131, I-133. Tritium and all radiemuelides in particulate form with half-lives greater than a days in ) gaseous effluents released to areas at or beyond the site boundary (see Figure 1.3) ahall be limited to the following free each reactor unitt

a. During any calendar guarter Less than or equal to 7.5 mram to any organ end, b.

r any calendar yeart Less than or equal to 15 mram to any s This requirement is appitcable at all times. This requirement is provided to implement the requirements of Sections !!.C,III.A and IV.A of Appendix I, 10 CFR Part 50. The requirement implements the guides set forth in Section II.C of Appendix 1. The action to be taken provides the required operating flexibility and at the-same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable." section 1.5.2 calculational methods implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix ! be shown by calculational procedures based on models and data such that the actual i I esposure of a member of the public through appropriately modeled pathways is unlikely to be substantially underestimated. Section 1.5.2 calculational methods for calculating the doses due to the actual release rates of.the subject materials are consistent with the methodologies provided in NUREG/CR-1004, "A 8tatistical Analysis of Selected Parameters for Predicting Pood Chain Transport and Internal Dose of Radionuclides," October 1979 and Regulatory Guide 1.109,_" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Rvaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1 October 1977 and Regulatory Guide 1.111, "Rethods for Ratis,ating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1 July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for I-131, I-133 tritium and all radionnelidea in particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man, beyond the site boundary. \\ The pathways which were examined in the development of these calculations ,)

1) individual inhalation of airborne radionuclides, 2) depo 31 tion were:

of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and

4) deposition on the ground with subsequent esposure of man.

00631 l

i 8QM ODCM Revision 23 Page 15 of 146 p If this requirassat is not met, perform the following action With the calculated dose from the release of I-131, 1-133 trittua and all radienselides la particulate form with half-lives escoeding 4 days, is gaseous effluents escoeding any of the above limits, prepare and submit to the Ceanission within 30 daye,. pursuant to Techsteal Specification 6.9.2, a Special Report which identifies the cause(s) for eseeeding the limit (s) and defines the corrective actions that have been tak e to reduce the releases and the proposed corrective actions to be takaa to assure that subsequent releases will be la templiance with the above limits. To emeure that this requirement is met Cuss 1stive dose contributions for the current calendar guarter and carrant salendar year for I-131, 1-133 tritius and all radiennelides in partioniste form with half-lives aseseding 4 days shall be deternised in accordanes with the methodology and parameters in Secties 1.5.1 at least emee per 31 days. 1 t t 9 i i l j 1 00631 l

Q j k t-SQN ODCM Revision 23 Page 16 of 146 1.5.2-- DORE DUE TO I-131. 1-133. TRITID4 MD ALL RADIONUCLIDES IN PARTICULATE FQRM WITE HALF-LIVES OF GREATER.THAN a DAYS ~ 1.5.2.1 Ornan done Calculation Organ doses due to I-131, 1-133, tritium and all radionuclides in particulats form with half-lives of greater than 8 days are calculated for each release for the critical receptor. The critical receptor is defined as the land-site boundary in the sector w!th the highest annual average X/Q. The annual average X/Q and D/Q are calculated using the methodology in Sections 1 9.2 and 1.9.3 using the historical 1972-1975 meteorological data '(Table 1.2).- Pathways considered to exist at this location are inhalation, ground plane exposure, grass-cow-milk ingestion, grass-cow-beef ingestion and fresh leafy and stored vegetable ingestion. All age groups are considered (adult, teen, child'and infant). Dose factors for-these age groups and . pathways are calculated as described in Section 1.8. For the ground exposure pathway, whica has no age or organ specific dose factors, the total body dose will be added to'the internal organ doses for all age groups. No credit is taken for radioactive decay. The general equation for the calculation of organ dose ist Dors = 3.178-06 TIIRpi(WpQi) (1.10) iP where 3.173-03 = conversion factor, year /second T = dtration of release, seconds. Rpi- = dose factor for pathway P for each identified nuclide 1, n o -area / year per pC1/s for ground plane, grase-cow-milk, grass-cow-meat, and vegetation pathways, and area / year per s pCi/m for inhalation and tritium ingestion pathways, . Equations for calculating these dose factors are given in Section 1.8. Wp = dispersion factor for the location and. pathway, = X/Q for the inhalation and tritium ingestion pathways, = 5.128-06 s/a8 .D/Q for the food and ground plane pathways, = 1.295-08 m-a Qi- = release rate for radionuclide i, pCi/s From the four age groups considered, the maximum is determined by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the critical age group. The organ doses for the critical age group will be used in the cumulative doses discussed in section 1.5.2.2. 00631

p i SQN ODCM Revision 23' Page 17 of 146 1.5.2.2 Cuanlative Doses Quarterly and annual suas of all doses are calculated for each release as described below to compare to the limits listed in Section 1.5.1. For maximum organ dose, cumulative quarterly and annual doses are maintained for. each of the eight organs considered. The cumulative dose is obtained by summing the doses for each organ of the critical age group (as calculated in Section 1.5.2.1) as determined for each release with the organ doses for all previous releases in the quarter or year to obtain the cumulative quarterly and annual doses. Thus, the cumulative organ doses will be conservative values, consisting of doses belonging to various age groups depending on the six of radionuclides. The highest of. these cumulative organ doses is used for the comparison to the limits described in Section 1.5.1. 1.5.2.3 ca-aarison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance. l I l j l J = l-i i !~ n 00631 ? ~

i-t SQN ODCM Revision 23 Page 18 of 146 1.6 GASEOUS RADWASTE TREATfENT 1.6.1 REQUIREMENTS The Gaseous Radweste Treatment Systen and the Ventilation Exhaust Treatment system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent doses due to gaseous affluent releases to areas at or beyond the site bo n dary (see Figure 1.3), when averaged over 31 days, would exceed 0.2 arad per unit for. gassna radiatios, and 0.4 mrad per mit for beta radiation. The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive asterials in gaseous waste prior to their ] discharge when the projected doses due to gaseous affluents to areas at 4 i or beyond the site botundary (see Figure 1.3) when averaged over'31 days would exceed 0.3 ares per mit to any organ. Li This requirement is applicable at all times. s L This requirement that the appropriate portions of these systems be used, when epecified, provides reasonable assurance that the releases of-radioactive materials in gaseous affluents will be kept "as low as L reasonably achievable." This requirement implements the requirements of 10 CFR Part 50.36a, General Design Criteria 60 of Appendix A to 10 CFR i" Part 50, and the dealan objectives given in Section II.D of Appendix I to L 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specithd as a suitable fraction of the dose-t design objectives set forth in Section II.8 and II.C of Appendix I,10 CFR Part 50, for gaseous effluents. If this requirement is not met, perform the following action: With the gaseous waste being discharged without treatment for more than 31 days and in excess of the above limits, prepare and submit to the Ceemission within 30 days, pursuant to Technical specification 6.9.2, a Special Report which includes the following information

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

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

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

To ensure that this requirement is met: Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and t parameters in Section 1.6.2. l 00631

- ~. -. ~... - - i SQN ODCM-Revision 2) Page 19 of 146. 1.6.2 DOSE PROJECTIONS In accordance with Section 1.6.1, dose projections will be performed. This will be done by maintaining running 31-day totals for the samma- 'done, the beta' dose and the maximum organ dose. Once per 31 days, these 31-day running totals will be compared to the limits given in Section 1.6.1 to determine compliance. If the projected doses exceed any of these lialts, the gaseous radwaste treatment system and the ventilation ashaust treatment system shall be used to reduce radioactive materials in gaseous effluents to areas at or beyond the site boundary. s 1.6.3 nAREOUR DA WARTE TDMATNENT SYSTEM DERCRIPTION The gaseous radweste treatment system (GRTS) described below shall be-maintained and operated to keep releases ALARA. -i A flow diagram for the CRTS is given in Figure 1.4. The systes consists of two waste-gas compressor packages, nine gas decay tanks, and the associated piping, valves, and instrumentation. Gaseous wastes are received from the following:.desassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown, displacing l' of cover gases caused by liquid accumulation in the tanks connected to the vent header, and boron recycle process operation. p p L L L l' 00631 i

_ _. ~ _ __ SQN ODCM i Revision 23-Page 20 of 146 l 1.7 DUARTEELY DQSE CALCULATIONS s A complete dose analysis utilising the total estimated gaseous releases for each calendar quarter will be performed and reported as required in j Section 5.2. Methodology for this analysis is that which is described in this i section using the quarterly release values reported by the plant personnel. All real pathways and receptor. locations identified by the most recent land use survey are considered. In addition, actual meteorological data representative of a ground level release for each corresponding calendar quarter will be used. For iodine releases, it is assumed that half the iodine . released is in organic form. Organic iodine causes a dose only by inhalation. For cow-milk and beef ingestion doses, the fraction of the time the animals are on stored feed (identified in the survey) is used in the calculation. The highest organ dose for a real receptor is determined by summing the dose contribution from all identified pathways for each receptor including ground i 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 receptora). I 1.7.1 iDBLE GA4 - GAltlA AIR DOSE Gamma air doses due to exposure to noble gases, D in area, are calculated y using the following equation: Dy = Xia DF g (1.11) y where: concentration of nuclide i at location a, pCi/a. Air Xia s = concentrations are calculated as described by Equation 1.16 DF g y dose conversion factor for external samma for nuclide 1, = arad/ year per pC1/a8 (Table 1.4). 1.7.2 EORLE GAA - RETA AIR DOSE L Beta air doses due to exposure to noble gases, Da in area, are ). calculated using the following equation: 1 Da = Xia DFgg (1.12) where Xia concentration of nuclide i at location a, pCi/m8 Air = concentrations are calculated as described by Equation 1.16. DFat dose conversion factor for external beta for nuclide i, = arad/ year per pC1/a8 (Table 1.4). 00631 l _m-, ~. ,,,r

i SQN ODCM-Revision 23 Page 21 of 146 1.7.3 RADIDIODINE. PARTICULATE AND TRITIUM - MAXIMUM ORGAN DOSE ' Organ doses due to radiciodine, particulate and tritium releases, Dors in area,.are calculated using the-following equation Dors =3.17E-08((X/Q)]RprQ7+][(X/Q)]Rpg+(D/Q)3cg+(X/Q)Rgg]Qg) .(1.13) P i P where: 3.17E-08 = conversion factor, year /second. X/Q = Relative concentration for location under consideration, s/a8 Relative concentrations are calculated as described by Equation 1.17. RPT " ingestion dose factor for pathway P for tritium, a m -area / year per pCi/s. Ingestion pathways available for consideration are the same as those listed above for Ryg. Equations for calculating ingestion dose factors for tritium are-given in Sections 1.8.7 through 1.g.12. QT = adjusted release rate for tritium for location under consideration, pCi/s. Calculated in the same manner _as Qg i above. Ryg = ingestion dose factor for pathway P for each identified .nuclide 1 (except tritium), a -area / year per pCi/s. s Ingestion pathways available for consideration includes pasture grass-cow-milk ingestion stored feed-cow-milk' ingestion pasture grass-goat-milk ingestion stored feed-goat-milk ingestion l pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetable ingestion Equations for calculating-these ingestion dose factors are given in Sections 1.8.1 through 1.8.6. D/Q = Relative deposition for location under consideration, a-a. Relative deposition is calculated as described in Equation 1.18. Rgg = Dose factor for standing on contaminated ground, a m -mram/ year per pC1/s. The equation for calculating the ground plane dose factor is given in Section 1.8.14. Ryg = Inhalation dose factor, arem/ year per pC1/m8 The equation for calculating the inhalation dose factor is given in Section 1.8.13. Qi = adjusted release rate for nuclide i for location under consideration, pCi/s. The initial release rate is adjusted to account for decay between ths release point and the -g location, depending on the frequency of wind speeds applicable to that sector. Hence, the adjusted release rate is equal to the actual release rate decayed for an average travel time 00631

L SQN ODCM Revision 23 O Page 22 of 146 during the period.. 9 Qio I fj exp(-At x/uj) (1.14) ' i j=1 1 where-Qgo = initial average release rate'for nuclide i over the' s period, pC1/s. g" ' fj - = joint relative frequency of occurrence of winds in windepeed class j blowing.toward this exposure point, expressed as a fraction. Ag = radiological decay constant for nuclide 1, s-1 x = downwind distance, meters. uj = midpoint value of wind speed class interval j, m/s. 1.7.4 POPULATION DOSES l 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-1.7. Frsr each of these sector elements, an average l 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 1.7). For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is' grown locally. q The general equation used for calculating the population dose in a given sector element ist Dosepop=]RATI0p*P0PN* AGE *0.001*D08Ep (1.15) i. P where RATIOp = ratio of average to maximum dose for pathway P. (Average ingestion rates are obtained from Regulatory Guide 1.109, Table E-4.) = 0.5 for submersion and ground exposure pathways, a shielding / occupancy factor. = 1.0 for the inhalation pathway. = 0.515, 0.515, 0.5, and 0.355 for milk, for infant, child, teen (_ and adult, respectively. (It is assumed that the ratio of /_ L 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. 00631

--~-__-- --- SQN ODCM Revision 23 Page 23 of 146- = 1.0, 0.38, 0.38, 0.37 for vegetable ' ingestion, for infant,, 'childe. teen and adult, respectively. (It-is assumed that the average individual eats no fresh leafy vegetables, only stored 1 vegetables.) POPN = the population of the sector element, persons (Table 1.8). AGE = fraction of the population belonging to each age group. -1 = 0.015, 03168, 0.153, 0.665 for infant, child, teen and adult,- respectively (fractions taken from NUREG/CR-1004, Table 3.39). 0.001 = conversion from area to ren. 1 DOSEp = the dose for. pathway P to the a nimum individual at the location'under consideration, area. For ingestion pathways, this dose is multiplied by'an average decay correction to account for decay as the food is moved through the food distribution cycle. This average decay correction, ADC, is. defined as follows: For milk and vegetables, ADC = up(-l t) i where I K' = decay constant for nuclide 1, seconds. 1 t = distribution time for food product under consideration (values from Regulatory Guide 1.109, Table D-1).. = 1.21E+06 seconds (14 days) for vegetables. = 3.46E+05 seconds (4 days) for milk. l up(-A t) A tt eb t For seat, ADC = 1 - up(-1 t1 eb) where 11 = decay constant for nuclide i, seconds. .t = additional distribution time for seat, over and above the time for slaughter to consumption described in Section 1.3.3, 7 days. tch = time to-consume a whole-beef, as described in Section 1.8.3. For beef ingestion, the additional factors in the calculation of ADC negate the integration of the dose term over the period during which a whole beef is consumed, for.the calculation of population dose. In other words, this assumes that the muinus individual freeses and eats a-whole beef, while the average individual buys smaller portions at a time. l Population doses are summed over all sector elements to obtain a total i population dose for the 50-mile population. 1.7.5 REPORTING 0F DOSES l The calculated quarterly doses and calculated population doses described in this section are reported in the Semi-Annual Effluent Release Report submitted to the NRC for the period ending December 31 of each year. 00631

r .I SQN ODCM Revision 23 Page 24 of 146

.L 1.8 cane 0uS Rettants - Done Factorm 1.8.1 PASTURE CRAES-COW /C0AT-MILE INCESTION DOSE FACTORS - R cpi a

(m -area / year per microcuries/second) ap a19f*EP(-A tl fa)f (~ ~(1-exp(-1 tep ~)) Bgy(1-exp(-Xgtb)) r E RCPi = 108DFL ,U F t p ~f A ~TI - p E i where: .i los = conversion factor, picocurie / microcurie.

DFLge,

= ingestion dose conversion factor for_nuclide 1, age group a, organ o, area / picocurie (Table 1.9). U = milk ingestion rate for age group a, liters / year. ap Fag = transfer factor for nuclide i from animal's feed to allk, days / liter (Table 1.10). Qg = animal's consumption rate, kg/ day. Ag = decay constant for nuclide.1, seconds-1 (Table 1.10). tg. = transport time from milking to receptor, seconds, f = fraction of time animal spends on pasture, dimensionless.. p = fraction of activity retained on pasture grass, dimensionless. r KE = the effective decay constant, due to radioactive decay and weathering,- . seconds-1, equal to 1g + Aw. = weathering-decay constant for leaf and plant surfaces, seconds-1 t,p = time pasture is exposed to deposition, seconds, p Y = agricultural productivity by unit area of pasture grass, kg/m, p a L - Bgy = transfer factor for nuclide i from soil to vegetation, picoeuries/kg (wat weight of vegetation).per picocuries/kg (dry soil), tb = time period over which accumulation on the ground is evaluated, seconds. P = effective surface density of soil, kg/m, a Il0TE: Factors defined above which do not reference a table for their numerical values, are listed in Table.1.11. ~1.8.2 STORrD Fern-COW /C0AT-MILE INCRETION DOSE FACTORS - R a CSi (m -area / year per microcuries/second) (1-exp(-Agte g)) l' RCSi = 108 DFL ao C i ap Fai Qf fa exp(-Agt a) - tcaf'It f s { ESI. Eg$- gafN- + EiYilj!jE1:hilhM_} .where sf 1 108 = conversion factor, picocurie / microcurie. DFLiao = ingestion dose conversion factor for nuclide 1, age group a, organ o, ares /picoeurie (Table 1.9). Unp = milk ingestion rate for age group a, liters / year. 00631 6

y SQN.0DCM-Revision 23 Page 25 of'146 3 F g- = transfer factor for nuclide i from animal's feed to milk, days / liter (Table 1.10). Qg = antaal'p consumption rate, kg/ day. .f. = fraction of time animal spends on stored feed, dimension 1eas. .I Ag = decay constant for nuclide 1, seconds-1 (Table 1.10). tfa

• transport time from silking to receptor, seconds.

L tcaf a time between harvest of stored feed and consumption by animal, seconds. = fraction of activity retained on pasture grass, dimensionless. r AB = the effective decay constant, due to radioactive decay and weathering, -t seconds-1, equal to Ag'+ %,. 1,- = weathering decay conetant for leaf and plant surfaces, seconds-1 t.g. = time stored feed.is exposed to deposition, seconds. e Yog = agricultural productivity by unit. area of stored feed, kg/m, a Bgy = transfer factor for nuclide i from soil to vegetation, picoeuries/kg q (wet weight of vegetation) per picoeuries/kg (dry soil). tb = ties period over which accumulation on the ground is evaluated, seconds. P = effective surface density of soil, kg/m, a J 1.g.3 PARTuna cms amer Iw=eTION DOBn FACT 0n2 - Rgpg (a8-area / year-per microcuries/second) (1-exp(-K teb)) i EMPi = los pyg,, g,, ygg gf g Attcb 1 f,{ IM"'. 1a30. + _B,,1gg,, (-l t )) } ih 10' = conversion factor, picoeurie/ microcurie. DFL ao = ingestion dose conversion factor for nuclide i, age group a, otsan o, i area / picocurie (Table 1.9). U 't = neat ingestion rate for age group a, kg/ year. an Fgg = transfer factor for nuclide i from cow's feed to seat, days /kg (Table 1.10). Qg = cow's consumption rate, kg/ day, y Ag = decay constant for nuclide 1, seconds-1 (Table 1.10). L l teb = time for receptor to consume a whole beef, seconds, t. = transport time from slaughter to consumer, seconds, p f = fraction of time cow spends on pasture, dimensionless, p i r = fraction of activity. retained on pasture grass, dimensionless. ~ AE. = the effective decay constant, due to radioactive decay and weathering, seconds *1, equal to Ag + Av. Av = weathering decay constant for leaf and plant surfaces, see'onds-1 t,p = time pasture is exposed to deposition, seconds. I- . Y =.asricultural productivity by unit area of pasture grass, kg/m, p a Bgy = transfer factor for nuclide i from soil-to vegetation, picoeuries/kg (wat weight of vegetation) per picocuries/kg (dry soil). tb = time over which accumulation on the ground is evaluated, seconds. P = effective surface ' density of soil, kg/a, s NOTE: Factors defined above which do not reference a table for their numeric values, are listed in Table 1.11. 00631 U ~. -. --

e-SQN ODCM-l Revision 23 Page 26 of 146 ~ 1.8.4 STORrn Fern.ntrr INCESTION DOSE FACTORS - Rggg a (m -area / year per microcuries/second) (1-exp(-A tt eb))- . Rust = 108 { DFL ao Uas Fri Qt ---~ %g tcb i a d -{ N -]_ an d +,B1y {31t.b12} fa 108' - = conversion factor, picoeurie/sicrocurie. DFL ao = ingestion dose conversion factor for nuclide 1, age group a, organ o, i -area /picoeurie (Table 1.9). U = neat ingestion rate for age group a, kg/ year. am. Fgg' = transfer factor for nuclide i from cow's feed to meat, days /kg (Table 1.10). Qg = cow's consumption rate, kg/ day. li = decay constant for nuclide i, seconds-1 (Table 1.10). ,1 teb - = time for receptor to consume a whole beef, seconds. t. = transport time from slaughter to consuser, seconds. fs = fraction of time cow spends on stored feed, dimensionless, test = time between harvest of stored feed and consumption by cow, seconds. = fraction of activity retained on pasture grass,.dimensionless. r i tg = time stored feed is exposed to deposition, seconds. Yg = agricultural productivity by unit area of stored feed, kg/m, g ,a 13 = the effective decay constant, due to radioactive decay and weathering, seconds-1, equal to Ag + Av. = weathering decay constant.for leaf and plant'aurfaces, seconds-1 Bgy - = transfer factor for nuclide i from soil-to vegetation, picoeuries/kg L -(wat weight of vegetation) per picoeuries/kg (dry soil). tb = time wier which accumulation on the ground is evaluated, seconds. L P = effective surface density of soil, kg/m, 't a NOTE: Factors defined above which do not reference a table for their. numerical (> values, are listed in Table 1.11. 1.8.5 FDRRH f.RAFY VECETART.R INCESTION DOSE FACTORS - R a VFi (m -area / year per microcuries/second)- Ryyg =-108 DFLiao e(-Agthe) UFLaf {r(1-e(-1 te)) + iy(1-e(-K t ))) E B ib L g pg h where: los = conversion facte/, picoeurie/ microcurie. DFL ao = ingestion dose c.onversion factor for nuclide i, age group a, organ o, i area /picoeurie (Table 1.9). i. - Ag = decay constant for nuclide 1, seconds-1 (Table 1.10). the- = average time between harvest of vegetables and their consumption and/or storage, seconds. 1 00631 i

]

n 9'

SQN ODCM Revision 23 Page 27 of-146-l UFLa = consumption rate of fresh leafy vegetables by the receptor in age group f a, kg/ year. 1 L~ fL = fraction of fresh leafy vegetables grown locally, dimensionless.. r = fraction of deposited activity retained on vegetables, dimensionless. AE = the effective decay constant, due to radioactive decay and weathering, seconds-1 =li + Av l = decay constant for removal of activity on leaf and plant surfaces by y weathering, seconds-1 t, = exposure time in garden for fresh leafy and/or stored. vegetables, seconds. a Yg- = agricultural yield for fresh leafy vegetables, kg/m, Bg = transfer factor for nuclide i fros soil to vegetables, picocuries/kg1 i (wet weight of vegetation) per picoeuries/kg (dry soil). tb ". time period over which accumulation on the ground is evaluated, seconds. a P = effective surface density of soil kg/m, 1.8.6' STORED VECETABLE INCESTION DOSE FACTORS - Rygg a m -area / year per microcuries/second) 1 (1-e(-l tsv)) i Rygi = 108 DFL ao'azp(-l t e) U$afs y g, i ih {IO 12+IiE(1-'(-ltl}} ih 10s = conversion factor, picocurie / microcurie. ,DFL ao =. ingestion dose conversion factor for nuclide i,. age group a, organ o, i I. -area /picoeurie (Table.1.9). [ Ag -= decay constant for nuclide i, seconds-1 (Table 1.10).. s l the- = average time between harvest of vegetables and their consumption and/or storage, seconds. Us, = consumption rate of stored vegetables by the receptor in age group a, ~ kg/ year. f = fraction of stored vegetables grown locally,-dimensionless. g i E toy time between storage of vegetables and their consumption,. seconds. a fraction of deposited activity retained on vegetables, dimensionless, r = b 15 = the effective decay constant, due to radioactive decay and weathering, L seconds-1 =li + 1, Av = decay constant for removal of activity on leaf and plant surfaces by weathering, seconds-1 t, = exposure time in garden for fresh leafy and/or stored vegetables, seconds. Y,y = agricultural yield for stored vegetables, kg/m, a Biy = transfer factor for nuclide i from soil to vegetables, picoeuries/kg l. (wat weight of vegetation) per picoeuries/kg (dry soil). I p tb = time period over which accumulation on the ground is evaluated, seconds. P = effectiva surface density of soil, kg/m, a NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.11. 00631 i 1

i "t -i SQN ODCM Revision 23.. Page 28 of 146 1.8.7 TRITIUM-PASTURE CDARS-COW /C0AT-MILK DOSE FACTOR - RCTP (area / year per microcuries/a ) 8 RCTP = 10s,los pyL ao fat Qf U p [0.75(0.5/H)] fp exp(-Artfa). T where: i 10s- = conversion factor,' grams /kg.' 108 = conversion factor, picoeuries/microcuries. DFL ao = ingestion dose conversion factor for tritium for age group a, organ o, T aren/picoeurie (Table 1.9).. FmT- = transfer factor for tritium from animal's feed' to milk, days / liter (Table.l.10). Qg =' animal's consumption rate, kg/ day. U., = milk ingestion rate for age group a, liters / year. 0.75 = the fraction of total feed that is water. ~ 0.5 = the ratio of the specific activity'of the; feed grass water to the atmospheric water. H = absolute humidity of the atmosphere, g/a, s f = fraction of time animal-spends on pasture, dimensionless. p AT = decay constant for trittua, seconds-1 (Table 1.10), tm = transport time from milking to receptor, seconds. f 1.8.3 TaiTInn-stonen Fern-Cow /c0AT-Mitr DOSE FACTOR - RCTS- .(area / year per microcurias/a8)- ap [0.75(0.5/H)] fs (1-exp(-A tesf)) T -RCTS = los los DFL ao FmT Qf U T AT Esf exp(-1 t7 fa) where: 10.8 = conversion factor, grams /kg. 108 = conversion factor, picoeuries/sierocuries. DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, l area /picoeurie_(Table 1.9).. Fa7 = transfer factor for tritium from animal's' feed to milk, days / liter l .(Table 1.10). Qg = animal's consumption rate, kg/ day. U = milk ingestion rate for age group a, liters / year. ap 0.75 = the fraction of total feed that-is water, ji 0.5 = the ratio'of the specific activity of the feed grass water to the j t-atmospheric water. H = absolute humidity of the atmosphere, g/a, s f, = fraction of time animal spends on stored feed, dimensionless. ly = decay constant for tritium, seconds-1-(Table 1.10). tegy = time between harvest of stored feed and consumption by animal, seconds. tra = transport titae from milking to receptor, seconds. i NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.11. 00631 1-l

SQN ODCM Revision 23 Page 29 of 146 1.8.9 TRITIUM-PASTURE GRARS-BEEF DOSE FACTOR - RMT 8 (area / year per microcuries/m ) - RMTP = 108 108 DFLy o FfT Qf Uam (0.75(0.5/H)) fp exp(-Ayt ) .II:f}IhIlapl1._11:ex25hIlchll-T tep. Xy tch where l: 10s = conversion factor, grams /kg. 108 = conversion factor, picoeuries/microcuries. DFL ao = ingestion dose conversion factor for H-3 for age group a, organ o, T area / picocurie (Table 1.9). L FfT. = transfer factor for H-3 from cow's feed to seat, days /kg (Table 1.10). Qg = cow's consumption rate, kg/ day. Uan = neat 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 '? E atmospheric water. s H = absolute humidity of the atmosphere, s/a, f = fraction of time cow spends on pasture, dimensionless. p 17 --decay constant for tritium, seconds-2 (Table 1.10). t, = transport time from slaughter to consumer, seconds, t,p = time pasture is exposed to deposition, seconds, tch = time for receptor to. consume a whole beef, seconds, y 1.8.10-TRITIUM-STORED FEED-BEEF DOSE FACTOR - Rggs u (area / year per microcuries/a8) l - Egyg = los los pIL ao Fry Qg Uam (0.75(0.5/H)] fs exp(-Arts) T _Il.!*I :topEIhIlan))(1-**El-lIch))_ t ET teb T wheret los = conversion factor, grams /kg. 108 = conversion factor,.picoeuries/microcuries. DFL eo = ingestion dose conversion factor for H-3 for age group a, organ o, T area /picoeurie (Table-1.9). Fry = transfer factor for H-3 from cow's feed to meat, days /kg (Table 1.10). Qg = cow's consumption rate, kg/ day. Uam = seat 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. s H = absolute humidity of the atmosphere, s/a, f, = fraction of time cow spends on-stored feed, dimensionless. A. = decay constant for tritium, seconds-1 (Table 1.10). H T p ts = transport time from slaughter to consumer, seconds, tep = time pasture is exposed to deposition, seconds, p teb = time for receptor to consume a whole beef, seconds. NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.11. 00631 4 j' j e I

e w. l SQN ODCM Revision 23 Page 30 of 146-1.s.11 TRITI E FRESH LEAFY YEGETABLES DOSE FACTOR - Ryyy (ares / year per alcrocuries/a8) 8 8 DFL ao [0.75(0.5/H)) UFLa fL exp(-A thc) RVTF = 10 10 T f where: los ' = conversion factor, grams /kg. 108 = conversion factor, picoeuries/microcuries.- DFLy.. = ingestion dose conversion factor for tritium for age group a, organ o, ( area /picoeurie (Table 1.9). 0.75 m.the fraction of total vegetation that is water. 0,5 = the ratio of the specific activity of the vegetables water to the ' atmospheric water. E = absolute heldity of the atmosphere, s/a8 UFLa = consumption rate of fresh leafy vegetables by the receptor in' age group a, kg/ year. 1 fL = fraction of-fresh leafy vegetables grown locally, dimensionless. AT = decay constant for tritium, seconds-1 (Table 1.10). the = time between harvest of vegetables and their consumption and/or storage, seconds. 1.8.12 TRITI E STORED VEGITABLES DOSE FACTOR - Rygg (area / year per microcuries/a8) (1-exp(-A t y)) T IVTg = 108 los DFL ao (0.75(0.5/H)) Ugaf5 M tav T exp(-A t e) Th where:- los = conversion factor, grams /kg. l-108 = convereton factor, picoeuries/microcuries. DFLTao = ingestion dose. conversion' factor for tritium for age group a', organ o,- area /picoeurie (Table 1.9). 0.75 = the fraction of total vegetation that is water. 0.5- = the ratio.of-the specific activity of the vegetation water to the atmospheric water. B -= absolute humidity of the' atmosphere, s/m8 i Ug. = consumption rate of stored vegetables by the receptor in age group a, i: kg/ year. 1; f = fraction of stored vegetables grown locally, dimensionless. g AT = decay constant for tritium, seconds-1 (Table 1.10). t, = time between harvest of stored vegetables and their consumption and/or 4 .E storage, seconds. i.;. the = time between harvest'of vegetables and their storage, seconds. NOTE: Factors defined above which do not reference a table for their numerical 14 values, are listed in Table 1.11. h i-00631 l' r i

g SQN ODCM Revision 33 Page 31 of.146 1.8.13 INHAtiTION DOSE FACTORS--Rg1 (area / year per microcuries/m ) 8 RIi = DFA ao bra 108 i l -wheres DFA ao = inhalation dose conversion factor for nuclide i, age group a and i organ o, arem/picoeurie (Table 1.12). ~BR = breathing rate for age group a, a / year (Table 1.11). s 10 = conversion factor, picoeurie/ microcurie. I'.8.14'CROUND PLAWE DOSE' FACTORS - Rgt a (m -area / year per microcuries/second) Rgi = DFGio 1/11 10' 8760 [1 - exp(-1 t )3 1b wheret ) DFgio = doseJconversion factor for standing on contaminated ground'for nuclide i and organ o.(total body and skin), aram/hr per-picoeurie/m3 (Table 1.13). 11 = decay constant of nuclide 1, seconds-1 (Table 1.10). los = conversion factor, picoeurie/ microcurie. 8760 = conversion factor, hours / year. tb- = time period over which the ground accumulation is evaluated, seconds (Table 1.11). u e 4 k 1 \\ ~ ? 00631

k [ SQN ODCM- -Revision 23 Page 32 of 146 (1.9 DISPERSIDE 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 9a 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' t effects on dispersion are not considered. Hourly average meteorological data are expressed as a joint-frequency distribution of wind speed, wind direction, and atmospheric stability. The joint-frequency distribution which represents the historical meteorological data for the period January 1972 to December -1975 is given in Table 1.2. ~ The wind speed classes that are used are as follows: Number Ranne (m/s) Midnoint (m/mi 1 <0.3 0.13 2 0.3-0.6 0.45 3 0.7-1.5 1.10 4 1.6-2.4 1.99 5 2.5-3.3 2.88 6 3.4-5.5 4.45 7 5.6-8.2 6.91 8 8.3-10.9 9.59 9 >10.9 10.95. The stability classes that will be used.are the standard A through G classifications. The stability classes 1-7 will correspond to A=1, B-2,.... G=7. 1.9.1 AIR CONCENTRA* ION - y (pCi/m3) Air concentrations of nuclides at downwind locations are calculated using the following equation: 9 7 Xi = } } (2/w)1/2 fjk Qi p exp(-li x/uj) (1.16) j=l k=1 Ezk uj (2rx/n) - where $h 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 radionuclide 1, pCi/s. 00631 l 1

f f SQN ODCM Revision 23 p, Page 33 of 146 .p = fraction of radionuclide remaining in plume (Figure 1.5). Isk = vertical dispersion coefficient for stability class k which includes a building wake adjustment, =(ejk+cA/v)1/3, or .= /3 e k, whichever is smaller. s where ogg-is the vertical dispersion coefficient for stability class k (a) (Figure 1.6), e is a building shape factor (c=0.5), a A is the minimum building cross-sectional area (1800 m ), uj = sidpoint value of wind speed class interval j, s/s. i x = downwind distance, n. 'i n = number of sectors, 16. 11 = radioactive decay coefficient of radionuclide i, s-1 2vz/n = sector width at point of interest, n. 1.9.2-RELATIVE CONCENTRATION - it/0 (sec/a8) Relative concentrations of nuclides at downwind locations are calculated using the following equation l 9 7 9k L X/Q

}1k}l(2/v)1/a (3,37) j

Izk uj (2vz/n) a where l-fjk = joint relative frequency of occurrence of winds in windepeed class j, stability class k, blowing toward this exposure point, expressed as a fraction. Isk = vertical dispersion coefficient for stability class k which includes s' building wake adjustment,. =(ej,g+cA/v)1/a, j. or = /3 ogg, whichever is smaller.. where l ogg is the vertical dispersion coefficient for l stability class k (a) (Figure 1.6), e is a building shape factor (c=0.5), A is the minimum building cross-sectional area (1800 a m ), uj = nidpoint 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, s. L i l 00631 ?

l: SQN ODCM U-Revision 23' Page 34 of 146 1.9.3 REIATIVE DEPOSITION-D/0 (m-2) Relative deposition of nuclides at downwind locations is calculated using the following equation: fjk DR-II'18) "j1 1 (2rx/n)

• e,e

- fg = joint relative frequency of occurrence of winds in windepeed class'j sad stability class k, blowing toward this exposure ~ point, expressed as a fraction. DR = relative deposition rate, a-1 (from Figure 1.7). m = downwind distance, a.. 4 - n- = number of sectors, 16. ,[f 2rz/n = sector width at point of interest, m. i I r t l 00631 1 i

SQN ODCM j Revision 23 Page 35 of 146 2.0 LIQUID EFFLUENTS 2.1 RELEABR POINTS There are four systems from which liquid effluents are released to the 'g environment. -These are the Liquid Radwaste System, the Condensate Domineraliser System, the Turbthe Building Sump,.and the Units 1 and 2 Steam Generator. Blowdown. Figure 2.1 provides an outline of the liquid release paths and discharge pointe with associated flow rates and radiation monitors. All liquid effluents are ultimately discharged to the Diffuser Pond which- - releases to the Tennessee River. The Essential Raw Cooling Water (ERCW) provides dilution for liquid effluents at a minimum flow rate of 15,000 spa. ERCW flow is monitored by radiation monitors 0-RM-133, -134, -140, -141. The inlet of the Diffuser Pond is monitored by radiation monitor 0-BM-90-211. Linuid Radwasta Svqten The Liquid Radwaste System processes liquid from the Reactor Building'and ' Auxiliary Building Floor Drains and the laundry / hot shower and chemical drain tanks. Figure 2.2 provides a schematic of the Liquid Radwaste-System, showing the liquid pathways, flow rate and radiation monitors. - The normal release points for liquid radwaste are the Monitor Tank and the Cask Decontamination Collector Tank (CDCT). The Monitor Tank has a capacity of 22,000 gal and is released routinely at a flow rate.of 125 spa.. The CDCT has a espacity of 15,000 gal and is also released routinely.at a flow rate of.125 spa. -The Monitor Tank and CDCT discharge to the Cooling Tower Blowdown (CTBD) line-as a batch release and are monitored by radiation monitor 0-RM-90-122. Condannate Domineralimer Svatem The Condensate Domineraliser System processes liquid wastes coming from the High Crud Tanks (HCT-1 and -2), the Reutralisation Tank, and the Non-Reclaimable Waste Tank-(RRWI). The RCTs have a capacity of 20,000 gal and a naxia m discharge flow rate of.245 gym. The Beutralisation Tank has a capacity of 19,000 gal and a maximum discharge flow rate of 245 spa. The NRWT has a capacity of 11,000 gal and a anximum discharge flow rate of 245 spa. The Condensate Desinaraliser System is routinely released to the CTBD line and is monitored by i radiation monitor 0-BM-90-225. Turbine Buildina S== j The Turbine Building Sump (TBS) normally releases to the Low Volume Waste Treatment Pond (LVWIP) but can be released to the Yard Pond. The TBS has a capacity of 30,000 gal and a design discharge release rate of 1,750 sps per pump. TBS releases are monitored by radiation monitor 0-RM-90-212. 00631

a ^ th. l r 4 "l p;;. SQN ODCM Revision 23 -Page 36 of 146. Staan Canarator Blowdown I

is

~ The Steam Generator Blowdown'(SGBD) is processed in the Steam Generator! Draindown' Flash Tanks or SGBD Heat Exchangers.. The SGBD discharge has a-maximum flow rate of 80 spa per steam senerator. SGBD discharges to the > CTBD line are continuous and are monitored by radiation monitors-(1) (2)-BM-90-120, -121. 1 h,( ? t i i o l -l s ~. u

l' l-l I

h I'. 00631

.~... l: 7 I -SQN ODCM' ) Revision 23 Page 37 of 146 2.2 CONCENTRATION -2.2.1 REQUIREMENTS The concentration of radioactive material released to unrestricted areas i(see Figure-1.3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other 4 then dissolved or entrained noble gases. For dissolved or entrained noble gases,'the concentration shall be limited to 2 x 10-8 microcuries/a1 total activity. This requirement is applicable at all times. This requirement is provided to ensure that the concentration of- .i radioactive materials released in liquid waste effluents to unrestricted areas-will be less than.the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. _This limitation provides additional assurance that the levels of radioactive materials in bodies of water in unrestricted areas will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to-a member of the public and (2) the limits of 10 CFR 20.106(e) to-the population. The concentration limit for dissolved or entrained noble gases is based upon the. assumption that Xe-135 is the controlling radioisotope and its MPC in air.(submersion) was converted to an equivalent concentration in water using the methods described in International Commission of Radiological Protection (ICRP) Publication 2. s If this requirement is not met, the following action will be performed: With the concentration of radioactive' material released to arestricted areas exceeding the above limits, without delay, restore the concentration to within the above limits. To ensure that this requirement is mett Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 2.1 and The resulte of the radioactivity analysis shall be used in accordance with the methods in Section 2.2.2 to assure that'the concentration at the point'of release is maintained within the limits stated above. l. 1 00631 l l 1

1 SQN ODCM 1 oe Revision 23-Page 38 of 146

j 2.2.2 MPC-SUM OF THE RATIOS The sum of the ratios (Rj) for each release point will be calculated by the following relationship.

si: Cg Rj=} (2.1) i MPCg wheret-R3 = the sum of the ratios for release point J. 1 MCg = the MPC of.radionuclide 1, as specified in Section 2.2.1, l pCi/mL'. Cg = concentration of radionuclide 1, pCi/mL. The sum of the NPC ratios must be i 1 due to the releases from any or all y of the release points described above. E ] The following relationship is used to ensure that this criterion is met: fR11+fR22+fR33+fR44 (2.2) RTBS + 1 1.0 F where .L RTBS = sum of the ratios of the turbine building sump as determined by equation 2.1. f,fsf,f4.-= effluent flow rate for radweste, condensate t 2 3 domineralizer system and each of the steam generators, respectively, spa. RR,R,R,R '= sum of ratios for radwaste, condensate 1 2 3 4 domineralizer system and each of the steam generators, respectively, as determined by equation 2.1. L = F- = minimum dilution flow rate for CTBD, 15,000 spa. Ll l l 0 1 4 00631 I k

l, SQN ODCM Revision 23-Page 39 of 146 2.3 nAnI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION 2.3.1 REQUIREMENTS The' radioactive liquid' effluent monitoring instrumentation channels shown~in Table 2.2 shall be operable with their alara/ trip setpoints set 4 to ensure that the limits of Section 2.2.1 are not exceeded. The E . alarm / trip setpoints of these channels shall be determined in accordance 7 .with the methodology and parameters in Section 2.3.3. This requirement is applicable during all releases via these pathways. The radioactive liquid effluent' instrumentation is provided to monitor. F and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in Section 2.3.3 to ensure that the alara/ trip will occur prior to exceeding the limits of i 10 CFR Part 20. The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. If this requirement is not met, the appropriate following action (s) will be performed; l a. With a radioactive liquid effluent monitoring instrumentation channel alara/ trip setpoint less conservative than required above, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint'so that it is acceptably conservative. b. With less than the minimum amber of radioactive liquid effluent - monitoring instrumentation channels operable, take the action shown in Table 2.2. Exert best effort to return the instriacats to operable status within 30 days and, if unsuccessful, explain in the next Semi-Annual Effluent Release Report why the inoperability could 1 not be corrected within 30 days. ] To ensure that this requirement is met: Each radioactive liquid effluent monitoring channel shall be demonstrated operable by performance of the channel check, channel calibration, and channel function test operations at the frequen.cies shown la Table 2.3. h' 00631

I 4 SQN ODCM Revision 23 l-Page 40 of 146 2.3.2 RELEASE SAMPLING Radwaste tanks will be recirculated through two volume changes prior to sampling to ensure that a representative sample is obtained. The l condensate domineralizer waste evaporator blowdown tanks cannot be recirculated. However, the contents will be transferred to the waste distillate tanks prior to release. Condensate domineraliser tanks are routinely continuously releaseda and utilise a composite sampler to obtain a representative sample while being discharged. In the event of an inoperable affluent radiation monitor or composite sampler, a two volume recirculation and two independent samples and analyses will be performed. Releases from the steam generator blowdown and turbine building sump

• are considered continuous and grab sampled daily.

1 Prior to a batch release,'a grab sample will be taken and analyzed to determine the concentration, pCi/al, of each gamma-emitting nuclide. For continuous releases, daily grab or composite samples will be taken i and analyzed to determine the concentration, pCi/al, of each i samma-emitting nuclide nuclide. Composite samples are maintained (as required by Table 2.1) to determine the concentration of certain nuclides l (R-3, Fe-55, Sr-89, Sr-90, and alpha emitters). For those nuclides whose activities are determined from composite samples (i.e. Sr-89, Sr-90, Fe-55 and H-3) the concentrations for the previous _ l composite period will be assumed as the concentration for the next period l to perform the calculations in Sections 2.2, 2.3, 2.4 and 2.5. The actual measured concentrations will be used for the dose calculations described in Section 2.6. i ~ l i i a Sampling requirements for these release points are applicable only ( during periods of primary to secondary leakage or the release of / _ radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of 1 1E-06 pCi/a1 and allowing for background radiation during periods when primary to secondary leakage is occurring. 00631

s i SQN ODCM Revision 23 l Page 41 of'146 2.3.3 INSTRIBEENT SETPOINTS Liquid effluent monitor setpoints are determined to ensure that the i concentration of radioactive material released at any time from the site to unrestricted areas does not exceed the MPC limits referenced in Section 2.2.1. 2.3.3.1 Runected' Monitor mannonne For each release, the expected monitor response, R in cym, is calculated j using the following equation: R = B + E EffteCi (2.3) i where B = monitor background, cpm. Effi = monitor efficiency for nuclide i, cpm per pCi/ce. Cg = tank concentration of nuclide i, pCi/cc. 2.3.3.2 calculated Marimum Monitor setnoint 1' For each release from a release point, a setpoint is calculated for the i appropriate monitor which corresponds.to the MPC limit for that release. The calculated maximum monitor setpoint, Smax in eps, is given by the following equation: S ax = (SAF*(R - B)) + B (2.4) m where SAF = setpoint adjustment factor as calculated below. R = arpected monitor response, cym, as. calculated by equation 2.3 in Section 2.3.3.1.' B = background, cym. Setnoint Adinatment Facto _r - SAF The SAF is determined by calculating the required dilution factor for the waste stream which will ensure that the NPC limits are met at the L unrestricted area boundary. If no dilution is required, then there is no ) need for a SAF. If. dilution is required to meet the MPC limits, the SAF l adjusts the monitor-to account for any additional dilution over the required amount.- The methodology for determining the SAF is given below. h 00631

.L SQN ODCM 1 Revision 23 j Page 42 of 146. 1. A' required dilution-factor,'DFr, is calculated using the following equation: DFr= '(2.5) where Rj. = sum of the MPC ratios for release point j as calculated in Section 2.2.2. SF = safety factor for the monitor. ( 2. The following criteria will be applied to the required dilution

j factor to determine the SAF t

A. If the required dilution factor, DF is lesn'than or equal to r 1, then the SAF u 0. B. If the required dilution factor, DFr, is greater than 1, SAF is calculated using the following equation. This accounts for the downstream dilution of the vaste flow over and above the required dilution. DFs SAF = DF - r where DF = the required dilution factor as calculated above. r DF = the actual dilution factor, calculated using the l a following equations ' FLOW,+ ( A

• FLOWdil')

DFa = (2.6) where FLOW = flow of waste stream, spa. y FLOWdil = flow of the dilution stream, spa.- A = fraction of dilution flow allocated to this-release l-point. For the TBS, this fraction is zero. The fractions for the remaining 4 release points are defined as the ratio of the allocated minimum CTBD flow for that release point to the total minimum CTBD flow. The minimum CTBD flow allocation for these-release points is as follows; Radwaste 9000 spa. Condensate demineralizer .3000 gpm Steam generator blow down (U1) 1500 gpm Steam generator blow down (U2) 1500 spm l 00631

- - ~ -.. . ~. SQN ODCM' l Revision 23 1 Page 43 of 146 2.3.3.3 normal Default setnoint A normal default setpoint may be determined for each monitor. A default setpoint'for a monitor will be defined and documented in approved plant procedures.' A default _setpoint should be low enough to ensure that-concentration limits defined in Section 2.2.1 are not violated and to ensure that unaxpected releases are identified. 2.3.3.4 Actual Monitor Satoointa ^l The maximum calculated monitor setpoint is determined fot each monitor-using the methodology in' Section 2.3.3.2. The default setpoint is defined in Section 2.3.3.3. The monitor setpoint for the release is determined as described below. The setpoint chosen for a monitor for each release is determined as follows:

1. IF:the calculated anximum setpoint is less than the normal default, THEN the setpoint shall be set equal to the calculated maximum setpoint.

2. IF the calculated maximum setpoint is greater than the normal default, AND X1 times the expected monitor response is less than the normal default setpoint, THEN the setpoint shall be set equal to the normal default setpoint.

-3. IF the calculated maximum setpoint is greater than the normal default, &N" X1 times the azpected monitor response is greater than the ti default setpoint..THEN the setpoint shall be set equal to 'ines the expected response. i i w k 1 X is an administrative factor designed to account for expected variations-in monitor response. It will be defined in approved plant instructions. t I 00631

I r SQN ODCK ).evision 23 Page 4a of 146 2.3.4 Pont-talaman Analvais A post-release analysis will be done using actual release data to ensure that the limits specified in Section 2.2.1 were not exceeded. A composite list of concentrations (Cg), by isotope, will be used with the actual vaste (f) and dilution (T) flow rates (or volumes) during the release. The data vill be substituted into Equation 2.2 to demonstrate compliance with the limits in Section 2.2.1. This data and setpoints will be recorded in auditable records by plant personnel. b f I i f i 9 7 ( l t t' 00631 =

9QN ODCM Revision 23 l Page 45 of 146 i 2.4 D915 1 2.4.1 REQUIRDirJITS 1 The dose er dose commitment to a member of the public from radioactive j asterials la liquid effluents released to unrestricted areas shall be limited free each reactor units

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

b. Dorias any talendar year to less than er equal to 2 stem to the total body and to less than or equal to 10 mram to any organ.

This requirement is applicable at all times. 1 This requirement is provided to implement the requirements of Sections II.A. f III.A, and IV.A of Appendix I, 10 CFR Part 50. The requirement implements the guide set forth in Section II.A of Appendix I. The action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in liquid effluents will be kept "as low as reasonable s achievable." Also, for fresh water sites with drinking water supplies which i can be potentially affected by plant operations, there is reasonable assurance i i i. that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in this Section implement the requirements in Section III.A of Appendix ! that conformance with the guides of Append 1F I be shown by Calculational procedures based on models and l data, such that t!J 4 ctual suposure of a member of the public through appropriately modeic;. pathways is unlikely to substantially underestimated. The equations specified in this section for calculating the doses due to the l actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation af Annual Doses to Man from Routine Releases of Reactor Effluents t for the Purposes of Avaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113. "Estinating Aquatic Dispersion of Rffluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. This requirement applies to the release of liquid effluents from each reactor t at the site. For units with shared radwaste treatment systems, the liquid effluents from the chared systems are proportioned among the units sharing that system. i 00631 3

SQN ODCM Revision 23 Pase 46 of 146 If this requirement is met met, the following acties will be performed: With the calculated dose from the release of radioactive materials in liquid effluents aseeeding any of the above limits, prepare and submit to the Ceanission withia 30 days, pursuant to Technical Specification 6.9.1, a Special Report which identifies the cause(s) for escoeding the limit (s) and defines the corrective settens that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This special Report shall aloe imelude (1) the results of radiological t analyses of the drinking water source and (2) the radiological impact on -fintahad drinking water supplies with regard to the requirements of 40 CFR 141 (applicable saly if drinking water supply is taken from the receiving water body within three miles devastream of the plant discharge). To ensure that this requirement is met: Cumulative dose eestributions fres liquid affluents for the curreAt calendar guarter and current calendar year shall be detenstaed in accordance with the methodelegy and parameters in Section 2.4.2 at least ence per 31 days. l l-i 4 s P P l t 1 L 00631 I 1 ---n.-,--,-e-v e,e-a-.+,---.-----,,,,, -.,,, - - m-,v,- s w -- ~ - -,,~, -,. - -., -v+-

,-se,w,r g

,a rw-e -n-

SQN ODCM i Revision 23 Page 47 of 146 l 2.4.2 CUttrLATIVE LIQUID EFTLUENT DOSE CALCULATIONS i Doses due to liquid effluents are calculated for each release for all age i groups (adult, teen, child and infant) and organs (bone, liver, total body, j thyroid, skin, kidney, lung and GI tract). Pathways c.onsidered are ingestion i of drinking water, fish consumption and recreation-shergline. The maximum individual dose from drinking water is assumed to be that caleviated at the location immediately downstream from the diffuser (sea Table 1.1). The anximum individual dose from fish ingestion is aestmed to be that calculated for the consumption of fish caught anywhere between the p140t and the first downstream das (Chickamauga Dass). The maxiava pot otin.1 regreatica dose is calculated for a location immediately downstream cf the p1kut outta11. Dose factors for these age groups and pathways are calc 41sted ks dnucribed in Section 2.7. For pathways with no age or organ specift e deso fotors.(1.e. shoreline recreation), the total body dose will be addet to d e.1hterntl organ i doses for all age groups. l The general equation for the dose calculations ist Dose =IAggTCgD (2.7) 1 wheret Agg = the total dose factor to the total body or any org,sta t for nuclide 1, area /hr per pC1/al. The to ni dcas ft.ctor is the sua of the dose factors for water ingention, fish incastion, and shoreline recreation, as defined in Sectier,3.7, T = the length of time period over which the conc 4ntrations and the flows are averaged for the liquid release, houva. Ci = the average concentration of radionuclide s, in undiluted liquid effluent during the time period T from say.tiquid release, pCi/al. D = the near field average dilution factor for Cg during any effluent release. D is calculated by the following equationt FLOWy i 0.60 RF wheret l

FLOW, a maximum undiluted liquid waste flow during the release, cfs.

For TBS releases, this ters is the diluted waste flow into the pond. 0.60 = mixing factor of effluent in river, defined as the percentage of the riverflow which is available for dilution of the i release. l-RF = default riverflow, cfs. For each release, this value is set to 7900 cfs (the lowest average quarterly riverflow recorded l from the period 1978-1988). 00631

b SQN ODCN Revision 23 Page 48 of 146 From the four age groups considered, the maximum is determined by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the critical age group. The total body and maximum organ doses for the critical age group are used in the calculation of the monthly dose described in Section 2.4.2.2. 2.4.2.2 Monthiv Dona Calculations i At the end of each month, the actual average riverflow for the month is i used to recalculate the liquid doses. The monthly cumulative dose is defined as the sum of the doses for the critical age group for each i rolesse during the month. Thus, the monthly cumulative dose will be a conservative value, consisting of doses belonging to various age groups i depending on the mix of radionuclides. These doses are multiplied by the ratio of the default riverflow (7900 cfs) to the actual monthly average riverflow to obtain the monthly dose. The total body and maximum organ doses determined in this manner are then used to determine the cumulative l quarterly and annual doses described in Section 2.4.2.3, and for the dose l projections described in Section 2.5.3. ? 2.4.2.3 Cumulativa Donna 4 Quarterly and annual sums of all doses are determined at the and of each month to compare to the limits given in Section 2.4.1. These quarterly-and annual suas will be the sum of the monthly cumulativa doses described in section 2.4.2.2 for the appropriate months in the guarter or year. These doses will be used in the comparison to the limits. 2.4.2.4 Cammariaan to Lim,*;g The cumulative calendar quarter and calendar year doses are compared to the limits in Section 2.4.1 once per 31 days to determine compliance. )' 00531

SQN ODCM Revision 23 Page 49 of 146 j 2.5 LIQUID WAITE ftF,ATMENT 2.5.1 REQUIRIMENT the Itquid radvaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent to meestricted areas (see Figure 1.3) would exceed 0.06 mres per reactor mit to the total body or 0.2 mram per reactor unit to any organ la a 31-day period. This requiremsat is applicable at all times. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid offluents will be kept "as low as reasonable achievable." This requirement implements the requirements of 10 Crt Part 50.36a, General ) Design Criteria 60 of Appendix A to 10 Crt Part 50 and the design objective given in Section II.D of Appendix I to 10 Crt Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents. If this requirement is not met, the following acties will be performed: With radioactive liquid waste being discharged without treatment and la escess of the above limits, prepare and submit to the Commission i within 30 days pursuant to Technical Specification 6.9.2, a Special Report which includes the following information: 1. Identification of the inoperable equipment or subsystems and the reason for inoperability, t 2. Actiea(s) taken to restore the inoperable equipment to operable g l status, and 3. Summary description of action (s) taken to prevent a recurrence. s To ensure that this requirement is mett i Doses due to liquid releases shall be projected at least once per 31 l days, la accordance with the methodology and parameters la secties 2.5.3. L l I t 00631 s j

l SQN ODCM Revision 23 Page 50 of 146 2.5.2 LIQUID kiDWASTE TREATMENT SYSTEM The liquid radwaste treatment system described below shall be maintained and operated to keep releases ALARA. A flow diagram for the LRTS is given in Figure 2.2, The system consists of one reactor coolant drain tank with two pumps and a floor and equipment drain sump inside the containment of each unit and the following shared equipment inside the auxiliary buildings one sump tank and pumps, one tritiated drain collector tank with two pumps and one filter, one floor drain collector tank with two pumps and one filter, a vaste condensate tank filter, three vaste condensate tanks and two pumps, a chemical drain tank and pump, two laundry and hot shower tanks and pump, a spent resin storage tank, a cask decontamination tank with two pumps and two filters, Auxiliary Building floor and equipment drain sump and pumps, and evaporator with two distillate tanks, a Mobile Waste Desineraliser System (if needed) and the associated piping, valves and instrumentation. 2.5.3 DOSE PROJECTIONS In accordance with Section 2.5.1, dose projections will be performed by averaging the two previous month's doses as determined in Section 2.4.2.2. To determine compliance with the limits, these averages are assigned as the dose projections for the upcoming month. The projected doses are compared to the limits of Section 2.5.1. If the projected doses exceed either of these limits, the liquid radweste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge to unrestricted areas. i l 1 00631 i y -=--1m. -r+v,---w-t-r- ---y-r neg m-- .v.

) h. I SQN ODCM Revision 23 page 51 of 146 2.6 011ARTERLY DOSE CALCULATI01ts A complete dose analysis utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as required in Section 5.2. Methodology for this analysis is that which is described in j this section using the quarterly release values reported by the plant 1 personnel. The releases are assumed, for this calculation, to be continuous over the 90 day period. L The average dilution factor, D, used for the quarterly calculations is 1 D= (for receptors upstream (2.7) RF

• 0.60 of Chickamauga Dan) and 3

D= (for receptors downstream (2.8) RF of Chickamauga Daa) i where RF = the average actual riverflow for the location at which the dose is being determined, cfs. 1 0.60 = the fraction of the riverflow available for dilution in the-near field, dimensionless. 2.6.1 WATRE IBGESTION Water ingestion doses are calculated for each water supply identified within a 50 mile radius downstream of SQN (Table 2.4). Water ingestion doses are calculated for the total body and each internal organ as described below Dors = los 9.80E-09 Awig Qg D exp(-8.64E+04 11t) (2.9) d where l l 108 = conversion factor, pC1/C1. t 9.80E-09 = conversion factor, cfs per al/ hour. Awig = Dose factor for water ingestion for nuclide i, age group t, l area / hour per pC1/al, as calculated in Section 2.7.1. Og = Quantity of nuclide i released during the quarter,. Curies. D = dilution factor, as described above, cfs-1 l 11 = radiological decay constant of nuclide 1, seconds-1 (Table 1.10). td = decay time for water ingestion, equal to the travel time from the plant to the water supply plus one day to account for the time of processing at the water supply (per Regulatory Guide 1.109), days. 8.64E+04 = conversion factor, seconds per day. L 00631 k

SQN ODCM' Revision 23 Page 52 of 146 2.6.2 TISH IBGESTION Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstreas of SQN (Table 2.4). Individual fish ingestion ) doses are calculated for the total body and each internal organ as described below l 1 Dors = los 9,goE-09 0.25 Arit Qi D axp(-8.64E+04 Xtt) (2.10) d

• ere 108

= conversion factor, pCi/C1. 9.80E-09 = conversion factor, cfs per al/ hour. 0.25 = fraction of the yearly fish consumption eaten in one quarter, dimensionless. 8 Argt = Dose factor for fish ingestion for nuclide 1, age group t, + area / hour per pC1/al, as calculated in Section 2.7.2. t-Qg = Quantity of nuclide i released during the quarter, Curies. D = dilution factor, as described above, cis-1 1g = radiological decay constant of nuclide i, seconds-1 (Table 1.10). td = decay time for fish ingestion, equal to the travel time from the plant to the center of the reach plus one day to account for transit through the food chain and food preparation time (per Regulatory Guide 1.109), days. 8.64E+04 = conversion factor, seconda per day. 2.6.3 EHORELINE RECREATION { tecreation doses are calculated for each identified reach within a 50 mile radius downstream of SQN (Table 2.4). It is assumed that the i. maximum exposed individual spends 500 hours per year on the shoreline at l a location immediately downstream from the diffusers. Individual [ recreation shoreline doses are calculated for the total body and skin as described below Dors = 108 9.40E-09 rf ARit Q1 D exp(-8.64E+04 Kg t ) (2.11) d where L 108 = conversion factor, pC1/C1. l 9.80E-09 = conversion factor, cfs per al/ hour. l rf a 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. e 00631 1

~. - - - - SQN ODCM Revision 23 Page 53 of 146 Aggg = Dose factor for shoreline recreation for nuclide i, age group t, area / hour per pCi/al, as calculated in Section 2.7.3. Qt = quantity of nuclide i released during the quarter, Curias. D = dilution factor, as described above, cis-1 l Ag = radiological decay constant of nuclide 1, seconds-1 (Table 1.10). ] td = decay time for recreation, equal to the travel time from the j plant to the center of the reach, days. 8.64E+04 = conversion factor, seconds per day. ) 1.6.4 TOTAL llL1193Rt INDIVIDUAL DORE The total maximum individual total body dose is obtained by summing the r following for each age groups the highest total body water ingestion dose i from among all the.public water supplies; the highest total body fish insestion 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 groups that organ's highest water ingestion dose from among all the public water supplies; that organ's highest fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual skin dose is that skin dose calculated for the maximum shoreline dose. 2.6.5 POPULATION DOSES For determining population doses to the 50-mile population around the plant, an average dose is calculated for each age group and each pathway and,then multiplied by the population. For water ingestion, the general equation used for calculating the population doses, P0PWTR, in man-res for a given PWS ist 5 4 POPWTRt = 10-8 IPOPa }POPa ATNW TWDOS at (2.12) a a n=1 a=1 wherst , POPWTRg = water ingestion population dose to organ t, man-rea. POPa = fraction of population in each age group a (from NUREG CR-1004, table 3.39). k Adult = 0.665 Child 0.168 = Infant = 0.015 Teen = 0.153 00631

SQN ODCM Revision 23 Page 54 of 146 POPa = Population at PWS a. The 4 PWSs and their populations are listed in Table 2.4. ATMW = ratio of average to maximum water ingestion rates for each a age group a. Maximan water ingestion rates are given in Table 1.11. Average water ingestion rctes, in L/ year, (from R.G. 1.109 Table E-4) ares Adult = 370 Child 260 = Infant = 260 260 Teen = TWD08ast = total individual water ingestion dose to organ t at PWS m, to the age group a, as described in Section 2.6.1, area. 10-s = conversion factor for res/ area. For population doses resulting from fish ingestion the calculation-assumes that all fish caught within a 50-mile radius downstream of SQR are consumed by local population. An additional 7-day decay ters is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in man-rom from fish ingestion of all fish caught within a 50-mile radius downstrema is: 453.6 NVST APR TFD08 art POPa POPPg = I I (2.13) 108 108 r=1 a=1 FISHa POPa i wheres ? POPFt " total fish ingestion population dose to organ t, man-rea. i NV8T = fish harvest for the Tennessee River, 3.04 lbs/ acre / year. l-APR = size of reach, acres (Table 2.4). TFDOSart. = total fish ingestion dose to organ t for reach r, for the (. age group s, as described in Section 2.6.2, area. POP. = 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 = 5.2 Teen = 453.6 = conversion factor, s/lb. los = conversion factor, area /res. 108 = conversion factor, s/kg. l l h 00631 . _. _. ~ _ _. _ _ _ _

1 a I i SQN ODCM Revision 23 Page 55 of 146 i For recreation shoreline, the general equation used for calculating the i population doses, POPR, in man-rea is: 4 REQPRA POPRg = I TSHDOSrt 3KVI3r NRSVISr (2.14) 108 4760 r=1 wheres i P0PRt = total recreation population dose for all reaches to organ t, man-rea. REQFRA = fraction of yearly recreation which occurs in that quarter, i as given in Section 2.6.3. I TSKDOSrt = total shoreline dose rate for organ t, in reach r, ares /h. SHVIS' RRSVIk = shoreline visits per year at each reach r, (Table 2.4). r = length of shoreline recreation visit at reach r, 5 hours. 108 = conversion factor, ares /res. 8760 = conversion factor, hours / year. ? h l l l ) 00631

[ t. SQN ODCM Revision 23 Page 56 of 146 2.7 LIOUID DORE FACTOR EDUATIONS 2.7.1 WATIR_1HGE1Tl0E - Awig (aram/hr per pCi/al) \\ DFList Uwa 106 108 i AWit " s760 wheres DFList = ingestion dose conversion factor for nuclide i, age group a, r organ t, area /pci, (Table 1.9). U, = water consumption rate for age group a, L/ year, (Table 1.11). 10 = conversion factor, pCi/pci. 10e = conversion factor, al/L. 8760 = conversion factor, hours per year. l 2.7.2 FISH INGESTION - Aygg (area /hr per pCi/al) l UaBt 106 108 DFList f AFit "' 37en where: DFList = ingestion dose conversion factor for nuclide 1, age group a, i organ t, area /pci, (Table 1.9). Ua = fish consumption rate for age group a, kg/ year, (Table 1.11). f Sg = bioaccumulation factor for nuclide 1, pCi/kg per PC1/L, (Table 2.5). 10' = conversion factor, pCi/pci. 108 .= conversion factor, al/L. 4760 = conversion factor, hours per year. 2.7.3 SEQR5 LIER _RECREAT105 - ARit (area /hr per pC1/al). DFgit Ke M W 108 10' U Il-tap (-A tb)3 ARit " 3760 a 3600 At l where Drggg = dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), area /hr per a pCi/m, (Table 1.13). K = transfer coefficient from water to shoreline sediment, e .L/ks-hr, (Table 1.11). a M = mass density of sediment, kg/m, (Table 1.11). W = shoreline width factor, dimensionless, (Table 1.11). 10s = conversion factor, al/L. 106 = conversion factor, pCi/pci. 00631

SQN ODCM Revision 23 Page 57 of 146 3600 = conversion factor, seconds / hour. it = decay constant for nuclide.1, seconds-1, (Table 1.10). tb

• time shoreline is exposed to the concentration on the water, seconds, (Table 1.11).

U = usage factor, 500 hours / year. 4760 = conversion factor, hours / year. k* 00631

b i SQN ODCM l Revision 23 l Page 58 of 146 l i 3.0 Radiolomical Environmental Monitorina i I 3.1 MINIMUM REQUIRED MOMITORING PROGRAM 3.1.1 REQUIREMENT I The radiological environnantal monitoring program shall be conducted as specified la Table 3.1. This requirement is applicable at all times, I The radiological environmental monitoring program required by this section provides measurements of radiation and radioactive esterials in those exposure + I pathways and for those radioraclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentration of radioactive materials and levels of radiation are not higher than expected on the basis of the affluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, e program changes may be initiated based on operational experience. L l-The LLDs required by Table 3.2 are considered optimum for routine I environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a atisti (before the fact) limit representing the capability of a messerement system and not as a contariori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unschievable. In such cases, the contributing circumstances will be identified and described in the Annual Radiological Environmental Operating Report. If this requirement is not met, the appropriate following action (s) will be performed 1 a. With the radiological environmental monitoring program not being conducted as specified la Table 3.1, prepara and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. b. With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.3 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from l the and of the affected quarter, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a member of the 00631

l I sQu oDcx Revision 23 page 59 of 146 l public is less than h calendar year lialts of Sections 1.4.1, 1.5.1 and 2.4.1, When one or more of the radionuclides in Table 3.3 is detected in I h sampling medium, this report shall be submitted it concentration (1) + concentration (2) +... t 1.0 limit level (1) limit level (2) i 1 When radionuclides other than h oe in Table 3.3 are detbeted and are the result of plant effluents, this report shall be submittet if the potential-annual dose to a member of the public is equal to or greater than the calendar year limits of Sections 1.4.1, 1.5.1 and 2.4.1. This report is not required if the measured level of radioactivity was not the result of plant effluentet however, in such an event, the conditisn shall be f reported and described in W &nnual Radiological Envitonnental Operating l Report. c. With milk er fresh leafy vegetable sangles unavailable from one or more of the sample locations required by Table 3.1, identify locations for obtaining replacement samples and add them to W radiological environmental monitoring program within 30 days. h speelfied locations from which samples were unavailable may them be deleted from the monitoring program, pursuant to section 5.1, identify W new locations -for obtaining replacement samples in W Annual Radiological. Environmental operating Report. A revised figure (s) and table (s) for the occu reflecting the new location (s) shall be included in W next seal-Annual Effluent Release Report pursuant to section 5.2. To ensure that this requirement is met: l The radiological environmental monitoring samples shall be collected pursuant to Table 3.1 from W locations given in W tables and figures I listed below and shall be analysed pursuant to W requirements of i Table 3.1 and the detection capabilities required by Table 3.2. i t 3.1.2 MOBITORING PROGRAM An environmental radiological monitoring program shall be conducted in accordance with the above requirement. The monitoring program described in Tables 3.4, 3.5, and 3.6, and in Figures 3.1, 3.2 and 3.3 shall be conducted. Results of this program shall be reported in accordance with section 5.1. - The atmospheric environmental radiological monitoring program shall consist of monitoring stations from which samples of air particulates and atmospheric radiolodine shall be collected. 7s The terrestrial monitoring program shall consist of the collection of milk, soil, around water, drinking water, and food crops. In addition, direct sanna radiation levels will be measured in the vicinity of the plant. 00631

4 i SQN ODCM Revision 23 Page 60 of 146 The reservoir sampling program shall consist of the collection of samples of surface water, sediment, clams, and fish. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavailability, or to malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling peri'od. 3.1.3 DRTECTIOR CAPARILITIES Analytical techniques shall be such that the detection capabilities listed in Table 3.2 are achieved. 00631

I a SQN 09CM Revision 23 Page 61 of 146 3.2 LAND USE CERSUS 3.2.1 REQUIREMENT A Land Use Census shall be conducted and shall identify within a distance of a km (5 miles) the location in each of the 16 meteorological sectors of the, ~ nearest alik animal, the nearest residence, and the nearest garden

• of greater then 50 ma (500 sta) producing fresh leafy vegetables.

This requirement is applicable at all times. This requirement is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of that census. The best survey information from the door-to-door, aerial, or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix ! to 10 CFR Part 50. Restricting the census to gardens of greater than 500 fta provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minism required to provide the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minima garden size, the following assumptions were used, 1) that 20% of the gar 6en was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/a8 The results obtained in the Land Use Census will be evaluated in accordance with the following appropriate actions: a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitaant 205 greater than the values currently being calculated in goetions 1.4 and 1.5, identify the new location (s) in the next Semi-Annual Effluent Release Report pursuant to Section 5.2. b. With a Land Use Census identifying a location (s) that yields a calculated dose or dose comattaent (via the same pathway) 205 greater than at a location from which samples are currently being obtainad in accordance with the requirements of Section 3.1.1, add the new location (s) within 30 days to the radiological environneatal nomitoring program given in Sectica 3.1.2, if samples are available. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose comattaant(s), via the same exposure pathway, may be deleted from this acattoring program after October 31 of the year in whteh this Land Use Ceases was conducted. pursuant to Technical Specification 6.14, subait in the mest Semi-Annual Effluent Release Report documentation for a change in the ODG8 including a revised figure (s) and table (s) for the ODQt g refleeting the new location (s) with the information supporting the change in sampling locations. 00631

_ _ _ ~ _ i SQN ODCM Revision 23 i Page 62 of 146 l To ensure that this requirement is met: The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, mail survey, telephone survey, i serial survey, or by consulting local agricultural authorities. The results of the Land Use Census shall be included in the Annual i Radiological Environmental Operating Report pursuant to Section 5.1. 3.2.2 LAND USE CENSUS f A land use survey shall be conducted in accordance with the requirements ? i above. The results of the survey shall be reported in the Annual Radiological Environmental Operating Report. l. i t I l. l. t e Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden L census. Specifications for broac leaf-vegetation sampling in Table 3.1.4c shall be followed, including analysis of control samples. 00631 ( l .r -e-.v--.mi--- w -e 'm.w ew,- r -.*nr t-- ---*+g-v g

i k SQN ODCM Revision 23 r Page 63 of 146 i 3.3 INTEDf_Aa0RAv0RY COMPARISON PROCRAM i 3.3.1 REQUIRDIENT I Analyses shall be performed on radioactive materials supplied as part of an [ Interlaboratory Comparison program which has been approved by the Conanission. This requirement is applicable at all times. The requirement for participation in an Interlsboratory Comparison Program is l provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid. i If this requirement is not met, the following action will be performed With analyses not being performed as required above, report the corrective actions being taken to prevent a recurrence to the Commission in the Annual Radiological Enviroasustal Operating Report. To ensure that this requirement is mets e A summary of the results obtained as a part of the above required l Interlaboratory Comparison program and in accordance with the guidance below shall be included in the Annual Radiological Environmental Operating Report. L 3.3.2 INvtDf.Ah0RAv0RY 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 result 6 obtained in the intercomparison shall be included in the Annual Radiological Environmental Operating Report (or the EPA program code designation may be provided). t 5 If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report. 1' 00631 . ~. ~... ,.-...,.._,.-n....,_..~,,

SQN ODCM Revision 23 Page 64 of 146 4.0 TOTAL DOSE l 4.1 REQUIRDENT The samual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity from uranimi fuel cycle sources, shall be limited to less than or equal to 25 area to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 area). J This requirement is applicable at all times. j This requirement is provided to meet the dose limitations of 40 CFR 190. The action requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the seaber of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If this requirement is not met, the following action will be performed: With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceedias twice the limits of section 1.4.1, i 1.5.1, or 2.4.1, calculations abould be made to determine if the above limits have been violated. If such is the case, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Regulatory Camaission, Washington D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits above. This Special Report, as defined in 19 CFR Part 20.405c, shall imelude an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (tacluding all effluent pathways and direct radiation) for a calendar year that includes the release (s) covered by this report. If the estimated does(s) exceeds the above limits, and it. the release condition resulting in violation of 40 Crt 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 ) and including the specified information of Section 190.11(b). Submittal of the report is considcred a timely request, and a variance is granted until the staff action on the request in completed. 00631 1

1 a SQN ODCM Revision 23 l Page 65 of 146 To ensure that this requirement is met Coulative dose contributions from liquid and gaseous effluents shall be determined la accordance with the methodology and parameters in Sections 1.4.2, 1.5.2, and 2.4.2. 4.2 ANNUAL MAXIMUM INDIVIDUAL DOSES - TOTAL REPORTED DOSE j To determine compliance with 40 CFR 190 as required in Section 5.2, the annual dose contributions to the maximum individual from SQN radioactive effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by first, summing the quarterly total body air submersion dose, the quarterly critical organ dose from gaseous effluents, the quarterly total body dose from liquid effluents, the quarterly critical organ dose from liquid effluents, and the direct radiation monitoring program, and then taking the sua for each qua'tter - and summing over the four quarters. l t l l o e 4 1 00631 I

l [ / SQN ODCM Revision 23 Page 66 of 146 5.0 REPORTING REQUIREMENTS 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ) The annual radiological environmental operating reports shall include l summaries, interpretations, and an analysis of trends. of the results of the radiological environmental surveillance activities for the report ] period, including a comparison with preoperational studies, operational s controls (se appropriate), and previous environmental surveillance _ reports and an assessment of the observed impacts of the plant operation l on the environment. The reports shall also include the results of land use censuses required by Section 3.2 and a listing of the new locations for dose calculations And/or environmental monitoring identified by the I land use census. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action to alleviate the probles. i l The annual radiological environmental operating reports shall include l summarized and tabulated results in the format of Regulatory Guide 4.8, l December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall l be submitted as soon as possible in a supplementary report. The reports shall also include the following a summary description of the radiological environmental sonitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program required by Section 3.3. 5.2 S Mi-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 8ealannual radioactive release reports shall include a summary of the quantit!.es of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents froa l' Light-Water-Cooled Nuclear Power Flants," Revision 1, June 1974, with data summarised on a quarterly basis following the format of Appendix B thereof. The semiannual radioactive release report shall include unplanned releases from the site to unrestricted areas on a quarterly basis and shall also include any changes made to the ODCM pursuant to Technical l Specification 6.14 00631 i

U SQN ODCM Revision 23 Page 67 of 146 The semianaval radioactive release report shall include information for solid waste as outlined in the Process Control Program, and shall also include any changes made to the PCP during the reporting period, l' The annual radioactive effluent release report (Radiological Impact) to L be submitted 60 days af ter January 1 of each year shall include an annual summary of hourly noteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind. direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the annual radioactive effluent release report, this summary of required meteorological data may be retained in site in a file that shall be provided to NRC upon request). This same report shall include an assessment of the radiation doses due to radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and 5 saseous effluents to members of the public due to their activities inside the site boundary (Figure 1.1) during the trport period. All assumptions used in making these asseessents (i.e., specific activity, exposure time, and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and l' measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with i Sections 1.7 and 2.6. The annual radioactive effluent release report to be submitted after January 1 of each year shall also include an assessment of radiation ( doses to the likely most exposed members of the public from reactor I releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190. Environmental Radiation Protection Standards for Nuclear Power Operation, in accordance with Section 4.2. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1. t l lI t L 00631 1

SQN ODCM Revision 23 Page 68 of 146 Table 1.1 (Page 1 of 4) RADICACTIVE GASEOUS WASTE MONITORING 8AMPLING AND ANALYSIS PROGRAM Gaseous Minimus Type of Lower Limit of telease Sampling Analysis Activity Detection (LLD) Type Frequency Frequency Analysis (pC1/al)a A. Waste Gas P P Storage Each Tank Each Tank Principal 1x10-8 Tank Grab Gamma taitters8

5. Containment

1. Purge Pi Di Principal 1x10-8 Each Purge Each Purge Gamma Grab Raitters8 Sample H-3 1x10-8 D3 DJ Principal 1x10-8

2. Vent Each Day Each Day Gamma Grab Raitters8 Sample H-3 1x10-8 C. Noble Gases and M

M Principal 1x10-8 Tritius Grab Gamma 8 ample Emitters 4

1. Condenser Vacuus H-3 1x10-8 Exhausth

2. Auxiliary l

Building Exhaust s8e

3. Service Blds.

Exhaust 4 Shield 81ds. b Exhaust,c.h \\ i l 00591 i t

l l [ i s0N ODCN Revision 23 1 Page 69 of 146 l Table 1.1 (Page 2 of 4) RADI0 ACTIVE GAsSOUs WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM Gaseous 1 INinimum ITyPe of ILower Limit of Release Isampling lAnalysis lActivity IDetection -LLD Type IPrequency IPrequency lAnalysis l(yci/ml)a i l I i D. Iodine and l l We l I-131 1 1x10-as Particulates Icentinuousf I Charcoal l l Isampler i Sample I i i i i i

1. Auxiliary i I

W8 IPrincipal 1 1x10-** Duilding icontinuousf IParticulate IGamma l Rxhaust Isampler Isample lemitterst I t-l 1 l(I-131 I

2. shield I

l 10thers) I Duilding i I i 1 Exhaust l l N l Gross Alpha 1 1x10-*A lContinuousf IComposite l l i Isampler IParticulate 1 l t Isample l l I I I I l I Q lse-09, I tulo-** lContinuousf IComposite Isr-90 l Isampler IParticulate l l I lsample l l l l l l l i l l E. Noble Cases lContinuousf l Noble Gas l Noble Gases . 1 1x10-* all Pelease IMonitor INonitor IGross Data 1 types as i I for Gamma i listed in C I I I I y e 00591 l l 1 -..,-.---,.,,,.----,----r-- ,,,. +. ,e.... n ,.a

SQN ODCM Revision 23 Page 70 of 146 i Table 1.1 (Page 3 of 4) i RADI0 ACTIVE GASEOUS WASTE MONITORING 8AMPLING l TABLE NOTATION i P = Completed prior to each release. D = At least once per 24 hours M = At least once per 31 days V = At least once per 7 days Q = At least once per 92 days a The LLD is defined, for the purpose of these specifications, as the smallest concentration of radioactive material in a sample that will yield j a not count above systen hackground that will be detected with 95E 2 probability with only a 55 probability of falsely concluding that a blank observation represents a "real" signal. i \\ For a particular measura system (which may include radiochealcal separation): 4.66sb l E V 2.22x10' Y Where esp (-A At) i LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume, is the standard deviation of the background counting rate or of the ob E is the counting efficiency as counts per disintegration, c V is the sample size in units of mass or volume, Y is the fractional radiochemical yield (when applicable) j A is the radioactive decay constant for the particular radionuclide, and l At is the elapsed time between aidpcint of sample collection and time of ~ counting (midpoint). It should be noted that the LLD is defined as ut a'eriori (before the t i fact) limit representing the capability of a ksasurement system and not an a neateriori (after the fact) limit for a particular measurement. b Sampling and analysis shall also be performed following shutdown, startup or a thermal power change exceeding 15% of rated thermal power within l 1 hour unless (1) analysis shows that the' dose equivalent I-131 of 3 and (2) the containment noble gas activity monitor (RE i 35-90-112) factor of 3.shows that the radioactivity has not increased by more than a I 00591 l l l i .. -, ~. - -.

l SQN ODCM i Revision 23 l Page 71 of 146 1 Table 1.1 (Page 4 of 4) RADI0 ACTIVE CASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION { c Tritius grab samples shall be taken at least once per 24 hours when the refueling canal is flooded. d samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours for at least 2 days following each shutdown from 1155 RATED THERMAL POWER, startup of (< 1155 RATED THERMAL POWER or THERMAL POWER change anceeding 15% of RATED THERMAL POWER in one hour and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours ars analysed, the corresponding LLD's may be increased by a factor of 10. e Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool, f The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation ) made in accordan:e with sections 1.2, 1.4, and 1.5. 1 g The principal samma esitters for which the LLD specification applies exclusively are the following radionuclidest Kr-37, Kr-88, Xe-133, Xe-133a, Xe-135, and Xe-138 for noble gases and h-54, Fe-59, I-131, i Co-58, Co-60, En-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate principal samma esitters. Thia list does not mean that only these nuclides are to be detected and reported. Other gamma peaks which are seasurable and identifiable, together with the above nuclides, shall also be analysed and reported in the Semi-annual Radioactive Effluent Release Report pursuant to Section 5.2. h During releases via this exhaust system. I Purging - Applicable in MODES 1, 2, 3 and 4, the upper and lower compartments of the containment shall be sampled prior to PURGING. Prior to breaking containment integrity in MODE 5 or 6, the upper and lower compartments of the containment shall be sampled. The incore instrument room purge sample shall be obtained at the shield building exhaust between 20 and 25 minutes following initiation of the incore instrument room purse. 3 Venting - Applicable in MODES 1, 2, 3, and 4; the containment wil'1 be vented to the containment annulus and then to the auxiliary building via g containment annulus fans. The lower containment compartment shall be F sampled daily when venting is to occur to account for the radioactivity being discharged from the venting process. 00591

6. ' ? v ?h ? SQN ODCM ' Revision 23- ~-' Page 72 of 146 Table 1.2 (1 of 7) JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED a FOR DIFFERENT STABILITY CLASSES

• SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY
• JAN.1, 72 - DEC. 31, 75

} i STABILIT1 OLASS A DELTA T1-1.9 DEG. C/100M-WIND SPEED (NPH) l - 0.6-1.5-3.5-5.5-7.5-112.5-18.5-CALtL L4-Li. -.idL 2.d ILi. IL.L Lbi_ j24.5 TOTAL .N 0.01 0.01-0.01 0.03 0.04 0.04 0.0 0.0 0.0 0.13 NNE-0.0 0.0 0.04 0.19 0.20 0.16 0.01 0.0 0.0 0.60 NE 0.0 0.0 0.08 0.20 0.15 0.13 0.0-0.0 0.0 0.56 ENE-0.0 0.0 0.03 0.03 0.01 0.0 0.0 0.0 0.0 0.07 E 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0-0.0 0.01 ESE-0.0 .0.0-0.01 0.01 0.0 0.0 0.01 0.0 0.0 0.03 SE> - 0.0 0.0 0.01 0.02 0.0 0.0 0.0 0.0 0.0 0.03 SSEL ~0.0 0.0 0.01 0.03 0.02 0.02 0.01 0.0 0.0 0.09 i S. 0.0 0.0 0.01 0.04 0.06. 0.05 0.01 0.0 0.0 0.17 I SS'd 0.0 0.0 0.01 0.09 0.18 0.16 0.01 0.0 0.0 0.45 L SW 0.0 0.0 0.04 0.12. a0.10 0.09 0.02 0.0 0.0 0.37 TNIW 0.0 0.0 0.02 0.03 0.03 0.02 0.02-0.0 0.0 0.12 L W '0.0 0.0 0.01 0.0 0.01 0.02. 0.0 0.0' O.0-0.04 H WNW= 0.0 0.0 ' O.0 0.0 0.0 0.01 0.01 0.0 0.0 0.02 l' NW 0.0 0.0-0.01 0.01 0.01 0.05 0.01 0.0 0.0 0.09 PNW 0.0 0.0 0.01 0.0 0.02 0.08 0.01 0.0' O.0 0.12 SUB-TOTAL '0.01 0.01 0.31 0.80 0.83 0.83 0.12 0.0 0.0 2.90 m 958 STABILITY CLASS A OCCURRENCES OUT OF TOTAL 32723 VALID TEMPERATURE DIFFERENCE READINGS 934 VI. LID WIND DIRECTION ' WIND SPEED READINGS OUT OF TOTAL 958 STABILITY CLASS A OCCURRENCES i. ALL COLtRNES~AND CALM TOTAL 100 PERCENT OF RET VALID READINGS +

• METEOR 0 LOGICAL' FACILITY LOCATED 0.74 MILES SW OF SEQUOYAH NUCLEAR PLANT R

TEMPERATURE IMSTRUMENTS 33 and 150 FEET ABOVE GROUND WIND INSTRUMENTS 33 FEET AB0VE GROUND 00591

4 ,Ji ? ? 1 3 ~ SQN ODCM.. Revision 23 ? Page 73 of 146 Table 1.2 (2 of 7) ~ JOINT PERCENTAGE FREQUENCIES'0F WIND DIRECTI FOR DIFFERENT STABILITY CLASSES

• SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY
• JAN. 1, 72 - DEC. 31, 75 STABILITY CLASS B i

4 f -1.9 < DELTA T1-1.7 DEG. C/100M i WIND SPEED (MPH)- P 0.6-1.5-3.5-5.5-7.5-12.5-18.5-GAIE. LA 11 .Li_ ld. 12.d_ 1L1 21d_ >24.5 TOT 4L V N 0.0 0.0 0.01 0.01 0.02 0.03-0.0 0.0 0.0 0.07 NNE 0.0' O.0 0.05 0.23 0.20 0.18 0.01 0.0 0.0 0.67 NE 0.01 0.0 0.08 0.29 0.09 0.06 0.0 0.0 0.0 0.52 ENE 0.0 0.0 0.03 0.03 0.01 0.0 0.0 0.0 0.0 0.07 i 3 .R 0.0 0.0 0.02 0.01 0.0. 0.C 0.0 0.0 0.0 0.03 ESE 0.0 0.0 ~ 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.01 SE 0.0 0.0 0.01 0.02-0.0 0.01 0.0 0.0 0.0 0.04 SSE 0.0 0.0 0.01 0.03. 0.0 0.02 0.0 0.0 0.0 0.06-S 0.0 - 0. 0 0.03 0.03 0.07 0.04 0.01 0.0 0.0 0.18-SSW 0.0 0.0 0.04 '0.09 0.20 0.20 0.03 0.0 0.0 0.56 SW 0.0 0.0. 0.03 0.11 0.14 0.10 0.02 0.0 0.0 0.40 WSW-0.0 0.0 0.01 0.01 0.03 0.02 0.01 0.01 0.0 0.09 W - '0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 WNW 0.0 .0.0 0.0 0.01-0.01 0.03 0.0 0.0 0.0 'O.05 NW .0.0 0.0 0.0 0.0 0.01 0.05 0.0 0.0 0.0 0.06 NNW 0.0 0.0 0.01 0.02 0.02 0.06 0.01 0.0' O.0 0.12 SUB-TOTAL -0.01 0.0 0.33 0.90 0.81 0.81 0.09 0.01 0.0 2.95 - 969 STABILITY CLASS B OCCURRENCES OUT OF TOTAL DIFFERENCE READINGS 953 VALID WIND DIRECTION - WIND SPEED READINGS r CLASS B OCCURRENCES l' ALL COLUMNS AND CAIJt TOTAL 100 PERCENT OF NET VALID R i

• METEOR 0 LOGICAL FACILITY LOCATED 0.74 MILES SW TEMPERATURE INSTRUMENTS 33 and 150 FEET AB0VE GROUND WIND INSTRUMENTS 33 FEET AB0VE GROUND 00591 i

i d!1 SQN ODCM Revision 23 Page 74 of 146 ~ Table 1.2 (3 of 7) L JOINT PERCENTAGE FREQUENCIES'0F WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

• j.

SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY

• JAN. 1, 72 - DEC. 31, 75

[ STABILITY CLASS C -1.7-< DELTA TA-1.5 DEG. C/100M ~, WIND SPEED (MPH) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-CAIJL _LA. L.s.- L1_ _LA. 12.d_ 18.d_ Zid 224.5 TOTAL l R 0.0 0.0 0.01 0.02 0.02 0.02 0.0 0.0 0.0 0.07 NNE 0.0 0.0 0.05 0.12 0.11 0.11 0.0 0.0 0.0 0.39 NE ~ 0.0 0.0 0.05 0.14 0.05 0.03 0.0 0.0 0.0 0.27 ENE 0.0-0.0 0.03 0.02 0.0 0.0 0.0 0.0-0.0 0.05 d E 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 ESE 0.0 0.0 0.01 0.01 0.0 0.0' O.0-0.0 0.0 0.02 ~ SE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 SSE 0.0 0.0 0.01 0.02 0.0 0.02 0.0 0.0 0.0 0.05 8 0.0 0.0 0.03 0.04 0.06. 0.05 0.0 0.0 ~0.0 0.18 SSW 0.0 0.0 0.01 0.11 0.14 0.13 0.02 0.0 0.0 ' 0.41 - l SW 0.0 0.0 0.03 0.08 0.12 0.07 0.01 0.0 0.0 0.31 WSW' O.0 0.0 0.01-0.02 0.03 0.02 0.0-0.01 0.0 0.08 W 0.0 0.0 0.0 0.01 0.0 0.01 0.01 0.0-0.0

0. 0,5 WNW 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 NW 0.0' O.0 0.0 0.0 0.02 0.03 0.01 0.0 0.0 0.06 NNW 0.0 0.0 0.0-0.02 0.02 0.05 0.0 0.0 0.0 0.09 SUB-TOTAL- 0.0 0.0 -

0.26 0.64 0.58' O.55 0.05 0.0 0.0 2.08 684 STAP!LITY CLASS C OCCURRENCES OUT OF TOTAL 32723 VALID TEMPERATURE DIFFERE! ICE READINGS V 672 VALID WIND DIRECTION - WIND SPEED READINGS OUT OF TOTAL 684 STABILITY 1 CLASS C OCCURRENCES ALL COLUlGIS AND CALM TOTAL 100 PERCENT OF NET VALID READINGS

• METEOR 0LCGICAL' FACILITY LOCATED 0.74 MILES SW 0F SEQUOYAH NUCLEAR PLANT TEMPERATURE INSTRUMENTS 33 and 150 FEET AB0VE GROUND WIND INSTRUMENTS 33 FEET AB0VE GROUND i-00591

SQN ODCM. i Revision 23 Pa8e 75 of 146 j Table 1.2 (4 of 7)- JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

• SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY
• JAN. 1, 72 - DEC. 31, 75

) STABILITY CLASS D i -1.5 < DELTA TA-0.5 DEG. C/100M WIND SPEED (MPH) - 1 0.6-1.5-3.5-5.5-7.5-12.5-18.5- -l GALil _l d. 1.4 id. LA 12d_ 18 4 2Ad_ >24.5 TOTAL -{ N 0.003 0.011 'O.24 0.22 0.16 0.17. 0.0 0.0 0.0 0.80 NNE' O.017-0.06 0.73 1.03 0.84 0.78- -0.07 0.0-0.0 3.51 NE 0.006 0.02 0.76 0.88 0.42 0.42 0.05 0.0 0.0 2.55 I ENE 0.003 0.01 0.21 0.11 0.03 0.0 0.0 0.0 0.0 0.36 .I E 0.003 0.01 0.12-0.03 0.02 0.01 0.0 0.0 0.0 0.19 l ESE 0.003 0.01 0.06 0.02 0.0 0.0 0.0 0.0 0.0 0.09 SE 0.0 0.0 0.12 0.08 0.0 0.0 0.0 0.0 0.0 0.20 SSE 0.0 0.0 0.15 0.15 0.05 0.06 0.01 0.01 0.0 0.43 8 0.003-0.01 0.31 0.53 0.38 0.25 0.02 0.0 0.0 1.50 s SSW 0.003 0.01 0.44 1.25 0.95 0.70 0.07 0.0 0.0 3.42 SW 0.003 0.01-0.47 1.17 1.03' O.52 0.03 0.01 0.0 3.24 WSW 0.0 0.0-0.22 0.34 0.18 0.21 0.07. 0.01 0.0 1.03 W 0.003-0.01 0.06 0.08 0.10 0.19 0.02 0.01 0.0 0.47-WNW 0.003 0.01 0.06 0.05 0.11 0.18 0.01 0.0 0.0 - 0.42 NW. 0.0 0.0 0.08 0.08 0.22 0.31 0.03 0.0 0.0 0.72 NNW 0.003 0.01 0.15 0.14 0.25 0.36 0.02 0.0 0.0 ' O.93 SUB-TOTAL 0.05' O.18 4.18 6.16 4.74 4.16 0.40 0.04 0.0 19.86 )) 4 6567 STABILITY CLASS D OCCURRENCES OUT OF TOTAL 32723 VALID TEMPERATUR DIFFERENCE READINGS. -i 6345 VALID WIND-DIRECTION - WIND SPEED READINGS OUT OF TOTAL 6567 STAB -CLASS D OCCURRENCES ALL COLUMKS AND CALM TOTAL 100 PERCENT OF NET VALID READINGS

• METEOROLOGICAL FACILITY LOCATED 0.74 MILES SW OF SEQUOYAH NUCLEAR P TEMPERATURE INSTRUMENTS 33 and 150 FEET ABOVE GROUND WIND INSTRUMENTS 33 FEET AB0VE GROUND 00591 i

SQN ODCM l Revision 23-l Page 76 of 146-Table 1.2 (5 ~ of 7) l JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SP FOR DIFFERENT STABILITY CLASSES

• j i

SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY

• JAN. 1, 72 - DEC. 31, 75-i STABILITY CLASS E

-0.5 < DELTA TA 1.5 DEG. C/100M VIND SPEED (MPH) O.6-1.5-3.5-5.5-7.5-12.5-18.5-GALIL _ L A-2.d_ - 5. 4-LA_ ILi_ ILL 21.A_ >24.5 ID.IAL N 0.017 0.23 1.26 0.83 0.39 0.27 0.0 0.0 0.0 2.98 t NNE 0.023 0.31 2.83 2.46 1.07 0.92 0.03 0,0 0.0 7.62 NE 0.011 0.15 1.03 0.71 0.31 0.18 0.01 0.0: 0.0 2.39 ENE 0.009 0.12 0.48 0.16 0.04 0.0 0.0 0.0-0.0 0.80 i L-E. 0.010 0.14 0.24 0.05 0.01 0.01 0.0 0.0 0.0 0.45 [' ESE 'O.007 0.09 0.11 -0.01 0.01 0.01 0.01 0.0 0.0 0.24 SE .0.007 0.10 0.37 0.06 0.01 0.01 0.0 0.0 0.0 0.55 SSE 0.008 0.11 0.58 0.24 0.13 0.23 0.04 0.02-0.0 1.35 S 0.013 0.17 1.33 1.49 0.91 1.05 0.04 ~0.0 0.0 u5.03 SSW .0.007 0.10 1.67 2.32 1.67-1.45 0.11 0.0 0.0 7.32

SW 0.013 0.17 1.59 2.07 1.30 0.99-0.10 0.0 0.0 6.22 WSW 0.010 0.13 0.47 0.55 0.35 0.40 0.06 0.0 0.0 2.36 W

0.007 0.10 0.42 0.28 0.21 0.22 0.03 0.0-0.0 1.26 WNW 0.010 0.14 0.37 0.22 0.19 0.27 0.02 0.0 0.0 1.21 NW 0.007 0.10 0.50 0.37 0.43 0.38 0.02 ' 0. 0 0.0 1.80 NNW 0.011 .0.15 0.80 0.68 0.57 0.40 0.01 0.0 0.0 2.61 SUB-TOTAL 0.17 2.31 14.45 12.50. 7.60 6.79 0.52 0.02 0.0 44.19 14624 STABILITY CLASS E OCCURRENCES OUT OF TOTAL 32723 VALID -i DIFFERENCE READINGS-b 14146 VALID WIND DIRECTION - WIND SPEED READINGS OUT OF T l-CLASS E OCCURRENCES ALL COLUMNS AND CAIM TOTAL 100 PERCENT OF NET VALID READINGS

• METEOROLOGICAL FACILITY LOCATED 0.74 MILES SW OF SEQUOYAH L

TEMPERATURE INSTRUMENTS 33 and 150 FEET ABOVE GROUND WIND INSTRUMENTS 33 FEET ABOVE GROUND e h 00591 H h

i i i SQN'0DCM Revision 23 Page 77 of 146 Table 1.2 (6 of 7) JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES *- SEQUOYAH NUCLEAR-PLANT METEOROLOGICAL FACILITY

• J AN. 1, 72 - DEC, 31, 75 STABILITY CLASS F 1.5 < DELTA TA 4.0 DEG. C/100M WIND SPEED (MPH) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-GALIL LA_

Li_ LA_ _2.d_ 12.d. 18.d _ 2LA_ >24.5 TOTAL M 0.011. 0.21 1.37 0.44 '0.04 0.0 0.0 0.0 0.0 2.06 NNE 0.018 0.35 3.61 0.84 0.05 0.0 0.0 0.0 0.0 4.85 NE 0.011 0.21 1.15 0.28 0.01 0.0 0.0 0.0 0.0 1.65 L ENE 0.008 0.16 0.39 0.03 0.0 0.0 0.0 0.0 -0.0 0.58 E 0.010 ~ 0.20 0.22 0,0 0.0 0.0 0.0 0.0 0.0. 0.42 ESE 0.007 0.13 0.18 0.02 0.0 0.0 0.0 0.0 0.0 0.33 J SI 0.007 0.14 0.23 0.02 -0.0 0.0 0.0 0.0 0.0 0.39 SSE 0.008 0.15 0.37 0.07 0.03 0.01 0.0 0.0 0.0 0.63 S 0.009 0.17. 0.77 0.30 0.10 0.06' O.0 0.0 0.0 1.40 SSW 0.006 0.12 1.13 0.71 0.26 0.11' O.0 0.0 0.0-2.33 SW 0.005 0.10 0.99 0.86 0.27 0.13 0.0 0.0 0.0 2.35 WSW 0.005 0.09 0.46 0.19 0.04 0.01 0.0 0.0 0.0-0.79-W 0.004 . 0.07 0.20 0.07 0.01 0.0 0.0 0.0 0.0 0.35 l -WNW 0.005' - 0.10 0.24 0.07 0.01 0.0 0.0 0.0 0.0 0.42 NW 0.003 - 0.05 0.29 0.15 0.05 0.01 0.0 0.0 0.0 0.55 NNW 0.005 0.09 0.52 0.34 0.05 0.01 0.0 0.0 0.0 1.01 SUB-TOTAL 0.12 2.34 12.12 4.39 0.92 0.34 0.0 0.0 0.0 20.11. 6542 STABILITY CLASS F OCCURRENCES OUT OF TOTAL 32723 VALID TEMPERATURE DIFFERENCE READINGS 6461 VALID WIND DIRECTION - WIND SPEED READINGS OUT OF TOTAL 6542 STABILITY CLASS F OCCURRENCES i ALL COLUMNS AND CALM TOTAL 100 PERCENT OF NET VALID READINGS

• METEOROLOGICAL FACILITY LOCATED 0.74 MILES SW 0F SEQUOYAH NUCLEAR PL' ANT TEMPERATURE INSTRUMENIS 33 and 150 FEET AB0VE GROUND WIND. INSTRUMENTS 33 FEET ABOVE GK0UND

.u 00591 m.

? i 3' f. a ' SQN ODCM Revision 23 PaSe 78 of 146 Table 1.2 (7 of 7) a JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

• l SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY
• l JAN. 1, 72 - DEC. 31, 75 4

STABILITY CLASS G DELTA T > 4.0 DEG. C/100M t WIND SPEED (MPM) 0.6-1.5-3.5-5.5-7.5-. 12.5-18.5-g&ML ,L.4_ _1d_ _id_ _2.d_ ILA. ILA. 2id. >24.5 IQ2&L N 0.003 0.06. 0.33 0.09 0.0 0.0 -0.0 0.0 0.0 0.48 IOtB 0.005 0.10-1.03 0.20 0.0 0.0 0.0 0.0 0.0 1.33 NE 0.005 0.09 0.74 0.12 0.0 0.0 0.0 0.0 0.0 0.95 i ENE 0.007 0.13 0.42 0.02 0.0 0.0 0.0 0.0 0.0 0.57 E 0.007 0.14 0.18 0.01. 0.0 0.0 0.0 0.0-0.0 0.33 ESE 0.006 0.11 0.08 0.01 0.0 0.0 0.0 0.0 0.0 0.20 - SE 0.005 0.09 - 0.08 0.0 0.0 0.0 0.0 0.0 0.0 0.17 SSE 0.008 0.16 0.21 0.0 0.01 0.0 0.0 0.0 0.0 0.37 8 0.006 0.11 0.39 0.04 0.02 0.0 0.0 0.0 0.0 0.55-SSW: 0.003 0.06 0.48 0.32 0.06 0.01 ' O.0 0.0 - 0.0 0.89 l SW 0.002 0.03 0.44 0.42 0.0 0.0 0.0 0.0 0.0 0.95 WSW 0.001 0.01 '0.11 0.07 0.0 0.0 0.0 0.0 0.0 0.19 W 0.002 0.03 0.08 0.02 0.0 0.0 0.0 0.0 0.0 0.13 WNW 0.001 0.01 0.03 0.01 0.0 0.01 0.0 0.0 0.0 0.06 l NW 0.001 0.02 -0.06 0.03 0.0 0.0 0.0 0.0 0.0 0.11 1 NNW 0.001 0.02 ~0.08-0.03 0.0 0.0 0.0 0.0 0.0 0.13 SUB-TOTAL 0.06 1.17 4.74 1.39 0.09 0.2 0.0 0.0 0.0 7.41 2379 STABILITY CLASS G OCCURRENCES OUT OF TOTAL 32723 VALID TEMPERATURE ^ DIFFERENCE READINGS 2378 VALID WIND DIRECTION - WIND SPEED READINGS OUT OF TOTAL 2379 STABILITY CLASS G OCCURRENCES ALL COLUBEIS AND CALM TOTAL 100 PERCENT OF NET VALID READINGS

• METEOROLOGICAL FACILITY LOCATED 0.74 MILES SW 0F SEQUOYAH NUCLEAR PLANT

S TEMPERATURE INSTRUMENTS 33 and 150 FEET ABOVE GROUND -WIND INSTRUMENTS 33 FEET ABOVE GROUND 00591 2 . m E m ---*---m - - - - =.

O v D r SQN ODCM l Revision 23 Page 79 of 146 j Table 1.3 SQN - 0FFSITE RECEPT 0E LOCATION DATA-DISTANCE x/Q D/Q= l POINT from plant (s/m') (1/m') (m) Site Boundary N 950 5.12E-06 1.29E-08 Site Soundkry NNE 2260 1.93E-06 5.28E-09 Site Boundary. NE 1910 2.32E-06 6.33E-09 Site Boundary ENE 1680 1.12E-06 2.64E-09

Site Soundary E

1570 7.10E-07 1.46E-09 Mite Boundary. Est-1400 7.91E-07 1.58E-09 ~ Site Boundary SE 1460-9.145-07 2.415-09 Site Boundary. SSE 1550 1.345-06 3.23E-09 site Boundary; 8 1570 2.378-06 4.18E-09 'Si Site Boundary SSW 1840 4.51E-06 9.26E-09 Site Boundary SW 2470 1.38E-06 2.63E, Site Boundary WSW 910 2.93E-06 3.86E-09 Site-Boundary W 670 3.63E 3.745 Site Boundary WWW 660 2.49E-06 2.44E-09' Site Boundary NW 660 2.85E-06 3.67E-09 Site Boundary NNW 730 3.95E-06 6.59E-09 1 Liquid Discharte S 870 N/A N/A BOTE: For quarterly airborne dose calculations, doses will also be calculated-for all locations identified in the most recent land use census, and for any additional points deemed necessary. h i l 00591 i

I t SQN ODCM Revision 23 Y Pa8e 80 of 146 -l Table 1.4. DOSE FACTORS FOR SUBMERSION IN NOBLE GASES Submersion dose Air dose-area /yr per pCi/a8-erad/yr per pCi/a8 Dr g-DFgi DFBg-DFSg y 1.93E+01 2.88E+02 Kr-83a 7.56E-02 Kr-85a-1.175+03 -1.46E+03 1.23E+03 1.97E+03 i Kr-85 1.61E+01' 1.34E+03 1.72E+01 1.95E+03 ? Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 -j Kr-89 1.668+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01-4.76E+02 1.56E+02 1.11E+03 l - 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 1.278+04 Ka-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 i Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

Reference:

L Regulatory Guide 1.109, Table B-1. l I 1 00591 l

~. j h ': 1'- SQN ODCM Revision 23 Page 81 of 146 5 Table 1.5 (Page' 1 of-2) RADI0 ACTIVE GASECUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLIC-INSTRUMENT OPERABLE ABILITY ACTION 1. WASTE GAS DISPOSAL SYSTEM a. Noble Gas Activity Monitor 1 40 b. Effluent System Flow Rate MeasurinS Device 1 41 2. CONDENSER VACUUM EXHAUST SYSTEM 4 a. Noble Gas Activity Monitor 1 42 b. Flow Rate Monitor 1 41 3. SHIELD BUILDING EXHAUST SYSTEM s. Noble Gas Activity Monitor 1 42 9. b. Iodine Sampler 1 44 c. Particulate Sampler 1 - 44 d. Flow Rate Monitor 1 41 e. Sampler Flow Rate Monitor 1 41 4. AUXILIARY' BUILDING VENTILATION SYSTEM l. [ a. Noble Gaa Activity Monitor 1 42 b. Iodine Sampler 1-44'

c. -, Particulate Sampler 1

44 1 41 d. Flow Rate Moniter~ 1 41 e. Sampler Flow Rate Monitor 6. SERVICE BUILDING VENTILATION SYSTEM l a. Noble Gas Activity Monitor 1 42 .b. Flow Rate Monitor 1 41 ~ 6 00591

E SQN ODCM Revision 23 Page 82 of 146 O Table 1.5 (Page 2 of 2) ) RAD 10 ACTIVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION TABEL NOTATION At all times. b During waste gas disposal system operation. During shield building-exhaust system operation. ACTION 40 - With the number of channels OPERABLE less than required by the Minimus Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided-that prior to initiating the releases

a. At least two independent samples of the tank's contents are analyzed,-and

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

-ACTION 41 - With the number of channels OPERABLE less than required by the Minimus Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. ACTION 42 -'With the number of channels OPERABLE less than required by the Minimum' Channels OPERABLE requirement, effluent releases via this-pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for noble gas gross activity within 24 hours.- ACTION 44 - With the number of channels.0PERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided that within 4 hours after the channel has been declared; inoperable samples are continuously collected with auxiliary sampling equipment as required in Table 1.1. s e 00591 a

I e 'SQN ODCM E5 Revision 23 Page 83 of 146 Table 1.6 (Page 1 of 2) J RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS MODES CHANNEL IN WHICH CHANNEL FUNC-SURVEIL - CHANNEL SOURCE CALIBRA-TIONAL LANCE-INSTRUMENT CHECK CHECK Il2H ' TEST REQUIRED

1. WASTE GAS DISPOSAL SYSTEM

a. Noble Gas Activity Monitor P

P R(3) Q(1)

b. Flow Rate Monitor D

N.A. R Q

2. CONDENSER VACUUM EXHAUST SYSTEM

)'

a. Noble Gas Activity Monitor D

M R(3) Q(2)

b. Flow Rate Monitor D

N.A. R Q '3. SHIELD BUILDING EXHAUST SYSTEM

a. Noble Gas Activity Monitor D

M R(3) Q(2)

b. Iodine Sampler-W N.A.

N.A. N.A.

c. Particulate Sampler W

N. A.. N.A. N.A. i

d. Flow Rate Monitor D

N.A. R Q j e.-Sampler Flow Rate Monitor D N.A. R Q J -4. AUXILIARY BUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor D

M R(3)- Q(2) -b.~ Iodine Sampler W N.A.. N.A. N.A. i 'c. Particulate Sampler ~W N.A. N.A. N.A.

d. Flow Rate Monitor D

N.A. R Q

e. Sampler Flow Rate Monitor D

N.A. R. Q 1

5. SERVICE BUILDING VENTILATION SYSTEM

.] q 'l

a. Noble Gas Activity Monitor D

M-R(3) Q(2)

b. Flow Rate Monitor D

N.A. 'R Q 00591

j .I I .l SQN ODCM-j Revision 23 1 i Page 84-of 146 Table 1.6 (Page 2 of 2) RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS u TABLE NOTATION' P = Completed prior to each release R = At'least once'per 18 months Q = At lease once per 92 days D = At least once.per 24 hours J N.A._= Not Applicable M = At least_once per 31 days At all times. During waste gas disposal system operation. During shield building exhaust system operation.

• • • • ' During waste gas releases.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control' room alara annunciation occurs if. _l L any of the following conditions exists:

1. Instrument indicates measured levels above the alara/ trip setpot.at.

2. Circuit failure.

3. Downscale failure.

(2) The CHANNEL FUNCTION TES't shall also demonstrate that control room alara annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alara setpoint.

2. Circuit failure.

3. Downscale failure.

For the auxiliary building ventilation system, at least once every 18 4 months, the CHANNEL FUNCTIONAL TEST shall also demonstrate automatic isolation of this pathwayJ1f the following condition exists: -Instrument indicates measured levels above the alara/ trip setpoint. (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall i permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that t have been related to the initial calibration shall be used. (4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent hydrogen, balance nitrogen and.

2. Four volume percent hydrogen, balance nitrogen.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent oxygen, balance nitrogen, and l

2. Four volume percent oxygen, balance nitrogen.

00591 L l l-

SQN.0DCM Re'tision 23 Page 85 of 146 l Table 1.7 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES Range of-Midpoint of Sector Element Sector Element Site' boundary mile 0.8 mile 1.- 2 miles 1.5 miles 2'- 3 miles 2.5 miles 3-4 miles 3.5 miles 4-5 miles 4.5 miles 5 - 10 miles 7.5 miles 10 - 20 miles' 15 miles 20 - 30 miles 25 miles 30 - 40 miles. 35 miles 40 - 50 miles 45 miles f,!: l a kiI e. '~-j. ) 00591

n-j r-SQN ODCM Revision 23' Page 86 of-146 -l Table 1.8 j POPULATION WITHIN EACH SECTOR ELEMENT i Sector Midpoint (miles) -0.8: 1.5. 2.5 3.5 4.5 7.5 15 25 35 45 l-N 20 41 213 129 66 1784 5453 3470 2610. 11145 .. NNE O-30-123 182 62 600 10628 4910 8250 10625 NE 0 0 67 ~67 94 581 2884 6998 7047 18080 ENE 0 11 24 222 300 773 4707 5747 29477 18679 E O 70 11 191 137 918 17440 6808 5072 4129 3 ESE 0 118 113 194 137 1849 46521 5044' 1896_ 13624 SE 0 179 322 168

205 1507 6005 5461

-15641 -3417 SSE 0 125' 370 750 601 2347 13242 8596 34279 11648 8 0 67 143 229 811 3930 28008 26690~ 19642' 11622 SSW 0 82 140 400 170 8927 96966 55597 21349 11978 SW 0 10 306 634 194 9787 94225 23455 11641 11109 WSW 20 190 642 1124 1669 19089 28405 4106 -15081 9548 W 10 -~ 20 233 657 657 5225 '1580 6350 5699 7707 WNW 10 30 365 598 598 2622 6540 4920 6699 2450 NW 50 80 292 569 -336 2696 1410 1750 1217 15896 ' NMW 10 263 80 75 213 1610 471 3130 2835 5719 l-00591 l~ L 1 l' ~~

F4 s o, q SQN ODCM i s Revision 23 ^ Page 87 of 146 Table 1.9 (1 of 8) INGESTION DOSE FACTORS (ares /pCi ingested) ADULT L bone liver t body' thyroid kidney lung 31-111 u H-3 1.05E-07 1.05E-07 1.0$E-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 1.708-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06' P-32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 ~2.17E-05 Cr-51 0.00E+00 0.00E+00 2.66E-09 1.59E-09 5.86E-10 -3.53E-09 6.69E-07 Mn-54 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00E+CO 1.40E-05 Mn-56 0.00E+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06_ + Fe-59 4.34E-06 1.02E-05 3.91E-06 0.00E+00 0.00E+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 d.44E-06 J ? Co-58 0.00E+00 7.45E-07. 1.67E-06 0.00E+00 0.00E+00 0.00E+00

7. 51E-05 j

l 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' O.00E+00 0.00E+00 1.74E-06 Cu-64 0.00E+00. 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 z9.70E i Zn ^1.03E-08 1.97E-08 1.37E-09 0.00E+00 1.28E-08 _0.00E+00 2.96E-09 E -69m 1.70E-07 4.08E-07 3.73E-0C 0.00E+00 2.47E-07 0.00E+00 ~2.49E-05 Br-84 0.00E+00 0.00E+00 2.26E-Cs 0.00E+00 0.00E+00 0.00E+00' 2.59E-06 Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 Br-84= 1.00E+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00- 4.09E-13 Br-85 0.90E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rt-86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 Rb-88 0.00E400 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' O.00E+00 0.00E+00 -0.00E+00 2.33E-21' Sr-89 3.08E-04 0.00E+00 8.84E-06 -0.00E+00 0.00E+00 0.00E+00 4.94E-05 Sr-90 7.58E-03 0.00E+00- 1.86E-03 0.00E+00 0.00E+00- 0.00E+00.2.19E-04 Sr-91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 '0.00E+00- 0.00E+00 '2.70E-05 Sr-92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00Et00 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-91a 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y-91 1.41E-07 0.00E+00 3.77E-09 0.00E+00 0.00E+00 0.00E+00 7.76E-05

,Y-92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y-93 2.68E-09 0.00E+00 '7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E Nb-95 6.228-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E+00 "2.10E-05 Nb-97 5.22E-11 1.32E-11 4.82E-12 0.00E+00 1.54E-11 0.00E+00 4.87E-08 Mo-99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 l Tc-99a 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07 F Tc-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05 Ru-105 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-07 0.00E+00 9.42E-06 h Ru-106 2.75E-06 0.00E+00 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 Sb-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0.00E-00 2.18E-06 7.95E-05 00591 l.

SQN ODCM Revision 23 Page 88 of 146 i Table 1.9 (2 of 8)- INGESTION DOSE FACTORS (arem/pci ingested) ADULT bone liver t body thyroid kidney lung 31-111 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.00E-00 1.33E-06 1.97E-05 Te-125m 2.68E-06 9.71E-07 '3.59E-07 8.06E-07' 1.09E-05 0.00E+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.735-06 2.75E 0.00E+00 2.27E Te-127 1.10E-07 ~3.95E-08 2.38E-08 8.15E-08 4.488-07 0.00E+00 8.68E-06 Te-129m 1.155-05 4.29E-06 1.82E-06 3.95E-06 4.80E 0.00E+00 5.79E-05 Te-129 3.145-08 1.18E-08 7.65E-09 2.415-08 1.32E-07 0.00E+00 -2.37E-08 Te-131m-1.73E-06 8.465-07 7.05E-07 1.34E-06 8.57E-06 0.00E+00J 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 3.485-06 0.00E+00 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06 I-132 2.038-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00 1.028-07 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 1.063-07 2.88E-07 1.03E-07 4.99E-06.4.58E-07 0.00E+00 2.518-10 I-135 4.438-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.318-06 Cs-134' 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E 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 7.978-05 1.09E-04 7.14E-05 0.00E+00 3.705-05 1.235-05 2.11E Cw-138 5.525-08 '1.09E-07 5.40E-08 0.00E+00 8.01E-08 7.91E-09 4.655-13 Ba-139-9,70E-08 6.91E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 0.00E+00 3.313-11 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 Co-141 9.368-09 6.33E-09 7.18E-10 0.00E+00 2.94E-09 0.00E+00 2.42E-05 Co-143 1.65E-09 1.22E-06 1.35E-10 0.00E400 5.37E-10 0.00E+00 4.56E-05 Co-144 4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.215-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.135-09 0.00E+00 4.03E-05 Pr-144 3.018-11 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 4.255-09 0.00B+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 Mp-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 0.00E+00 2.40E-05 Referencest Regulatory Guide 1.109, Table E-11. Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Ane Snecific Radiation Done Commitment Factors for a One Year Chronic Intake, November, 1977, Table 4. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 00591

SQN ODCM ?F Revision 23 Pa8e 89 of 146 Yable 1.9 (3 of 8) INGESTION DOSE FACTORS _(arem/pCi ingested) TEEN bone liver t body thyroid kidney lung gi-111 H-3 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Ma-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P 2.76E-04' 1.71E 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 Cr-51 0.00Et00 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 0.00E400 1.58E-07 2.81E-08 0.00E+00 2.00E-07 0.00E+00 1.04E-05 Fe 3.78E-06 2.68E-06 6.25E-07 0.00E+00 0.00E+00 1.70E-06' 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 Co-57 0.00E+00 2.38E-07 3.99E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co-58 0.00E+00 9.72E-07 2.24E 0.00E+00 0.00E+00 0.00E+00

1. 3'4E-05 Co-60 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00' O.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 Ni-65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 Cu-64 0.00E+00 1.158-07 5.41E-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 1.478-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 Zn-69s 2.40E-07 5.66E-07 5.19E-08 0.00E+00 3.44E-07 0.00E+00 3.11E-05 Br-82 0.00E+00 0.00E+00 3.04E-06 0.00E+00 0.00E+00 -0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 '0.00E+00' Br-84 0.00E+00 0.00E+00 7.22E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00-Br-85 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41E-06

'Rb-88 0.00E+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00 -7.30E-15 Rb-89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43E-17 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' O.00E+00' 3.66E-05 St-92 3.058-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E-05' Y-90 1.378-08 0.00E+00 3.69E-10 0.00E+00' O.00E+00 0.00E+00. 1.13E-04 Y-91a 1.29E-10 '0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09 Y-91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 Y-92 1.215-09 0.00E+00 3.50E-11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y-93 3.83E-09 0.00E+00 1.05E-10 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 0.00E+00 7.11E-10 0.00E+00 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 Nb-97 7.37E-11 1.83E-11 6.68E-12 0.00E+00 2.14E-11 0.00E+00 4.37E-07 Mo-99 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.08E-05 Tc-99a 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 0.00E+00 1.09E-07 0.00E+00 8.99E-07 0.00E+00 2.13E-05 Ru-105 2.18E-08 0.00E+00 8.46E-09 0.00E+00 2.75E-07 0.00E+00 1.76E-05 Ru-106 3.92E-06 0.00E+00 4.94E-07 0.00E+00 7.56E-06 0.00E+00 1.88E-04 As-110m 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 Sb-124 3.87E-06 7.13E-08 1.51E-06 8.78E-09 0.00E-00 3.38E-06 7.80E-05 00591 6 I

a j t 3: SQN ODCM Revision 23 Page 90.of_146 Table 1.9 (4.of 8) INGESTION DOSE FACTORS U (arem/pci ingested) TEEN bone liver t body thyroid ' kidney lung 31-111 $b-125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0.00E+00 2.18E-06. 1.93E-05 Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06. 0.00E+00 0.00E+00 1.13E-05 ~ Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.095-07 -6.40E-07 0.00E+00 1.22E-05, Te-129s 1.635-05 6.058-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E 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-131-2.798-08 -1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0.00E+00 7.00E-05 I-130 1.038-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.00E+00 2.29E-06' I-131 5.85E-06 8.19E-06 4.40E-06 2.393-03 1.41E-05 0.00E+00 1.62E-06 I-132 2.795-07 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 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E 0.00E+00 5.10E-09 I-135 6.105-07 1.575-06 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 2.455-06 Ca-136 8.59E-06 3.38E-05 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E 5.19E-05 0.00E+00 5.075-05 1.97E-05 2.128-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 i Ba-139 1.39E-07 9.78E-11 4.05E-09 0.00E+00 - 9.22E-11 6.74E 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 g 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 1.995-11 9.18E-20 La-140 .3.48E-09 1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 0.00E+00 0.00E+00 0.00E+00 2.42E Co-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 Co-144 6.96E-07 2.888-07 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 0.00E+00' 3.04E-09 0.00E+00 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 0.00E+00 1.01E-11 -0.00E+00- 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 0.00E+00 5.99E-09 0.00E+00 3.68E-05 l W-187 1.462-07 1.19E-07 4.17E-08 0.00E+00 0.00E+00 0.00E+00 3.22E-05 i ~ NP-239 1.76E-09 1.66E-10 9.22E-11 0.00E+00 5.21E-10 0.00E+00 2.67E-05 L

References:

L Regulatory Guide 1.109, Table E-12. ) Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from l NUREG-0172 Ana Snacific Radiation Dose Commitment Factors for a One Year Chronic Intake, November, 1977, Table 4. -) NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 00591

-1 1 SQN ODCM I i Revision 23 Page 91 of 146 I t Table 1.9 (5 of 8) L INGESTION DOSE FACTORS l< (arem/pci ingested)- l' CHILD L' bone liver t body thyroid kidney lung 31-111 Y I H-3 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03C-07 1

C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06' 2.42E-06 2.42E-06

'Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 0.00E+00 0.00E+00 0.00E+00 2.28E-05' i Cr-51 0.00E+00 0.00E+00 8.90E-09 4.94E-09 1.35E-09 '9.02E-09 4.72E-07 Mn-54 0.00E+00 1.07E-05 2.85E-06 0.00E+00 3.00E-06 0.00E+00 8.98E, Mn-56 0.00E+00 3.34E-07 7.54E-08 0.00E+00 4.04E-07 0.00E+00' 4.84E-05 i Fe-55 1.15E-05 -6.10E-06 1.89E-06 0.00E+00 0.00E+00 3.45E-06 1.13E-06 I Fe-59 l'.65E-05 2.67E-05 1.33E-05 0.00E+00 0.00E+00. 7.74E-06--2.78E-05 Co-57 0.00E+00 4.93E-07 9.98E-07 0.00E+00 0.00E+00 0.00E+00 4.04E-06 Co-58 0.00E+00 1.80E-06 5.51E-06 0.00E+00 0.00E+00 0.00E+00' 1.05E-05 -i L Co-60 0.00E+00 5.29E-06 '1.56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05 L 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 6.415-06' Zn-69 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00, 3.99E-06 l. Zn-69m 7.10E-07 1.21E-06 1.43E-07 0.00E+00 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 Br-83 0.00E+00 0.00E+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00' O.00E+00 1.98E-07 0.00E+00 0.00E+00 -0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 9.12E 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00' O.00E+00 4.31E-06 Rb-88 .0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 0.00E+00 9.32E-09 Rb 0.00E+00.1.17E-07 1.04E-07 0.00E+00 0.00E+00 '0.00E+00 1.02E-09' Sr-89 1.32E-03 0.00E+00 3.77E-05 0.00E+00 0.00E+00 -0.00E+00 5.11E-05 -Sr-90 1.70E-02 0.00E+00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 : 2.29E-04

f Sr-91 2.40E-05 0.00E+00 9.06E-07 0.00E+00 0.00E+00 -0.00E+00 5.30E-05 Sr-92 9.03E-06 0.00E+00 3.62E-07 0.00E+00 0.00E+00 0.00E+00. 1.71E-04 Y-90 4.11E-08 0.00E+00 1.10E-09 0.00E+00 0.00E+00 ~0.00E+00 1.17E-04 Y-91m 3.82E-10 0.00E+00- 1.39E-11 0.00E+00 0.00E+00' O.00E+00L 7.48E Y 6.02E-07 0.00E+00 1.61E-08 0.00E+00 0.00E+00 0.00E+00 8.02E-05

'Y-92 3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E+00 1.04E-04 Y-93 1.14E-08 0.00E+00 3.13E-10 0.00E+00 0.00E+00 0.00E+00 1.70E-04 2r-95 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 0.00E+00 8.23E 0.00E+00 "1.62E-05 Nb-97 2.17E-10 3.92E-11 1.83E-11 0.00E+00 4.35E-11 0.00E+00 1.21E-05 No-99 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 0.00E+00 1.10E-05 Tc-99m 9.23E-10 1.81E-09 3.00E-08 0.00E+00 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 0.00E+00 2.81E-07 0.00E+00 1.84E-06 0.00E+00 1.89E-05' Ru-105 6.45E-08 0.00E+00 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21E-05 Ru-106 1.17E-05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E+00 1.82E-04 As-110m 5.39E-07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 Sb-124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 0.00S+00 6.16E-06 6.94E-05 00591 i

+ L-E< l-SQN ODCM l L Revision'23 Pa8e 92 of 146 Table 1.9 (6 of 8) 1 INGESTION DOSE FACTORS J (arem/pci ingested) CHILD bone liver t body thyroid kidney lung 31-111 8b-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-127a 2.89E-05' 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.00E+00 2.34E-05 Te-127 4.715-07 1.278-07 1.01E-07 3.26E-07 1.345-06 0.00E+00 1.84E, Te-129a 4.87E-05 1.36E-05. 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.94E-05 l Te-129 1.34E-07 3.748-08. 3.18E-08 9.56E-04 3.92E-07 0.00E+00 8.34E-06 Te-131a 7.20E-06 2.49E-06' 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E l Te-131 8.30E-08 2.53E-04 2.47E-08 6.35E-08 2.51E-07 0.00E+00 4.36E Te-132' 1.01E-05 4.478-06 5.40E-06 6.515-06 4.15E-05 0.00E+00 4.50E-05 L I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-00 0.00E+00 2.76E-06 I I-131 1.72E-05 1.73E-05. 9.83E-06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 ( I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 i 1-133 5.92E-06' 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 -2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.798-05 1.19E-06 0.00E+00 5.16E a-I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E 0.00E+00 2.40E-06' Co-134 2.345-04 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 2.273-06 J Cs-137 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.678-05 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 Ba-139 4.14E-07' 2.21E-10 1.20E-08 0.00E+00 1.93E-10 1.305-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 0.00E+00 2.37E-08 ~ 4.34E-08 4.21E-05 Ba-141 2.00E-07.1.12E-10 6.51E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.298-11 4.88E-09 0.00E+00 ~ 5.09E-11 3.70E 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 0.00E+00 0.00E+00- 0.00E+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 0.00E+00 0.00E+00 0.00E+00 :3.31E-05 Co-141 3.978-08 1.98E-08 2.94E-09 0.00E+00 8.68E-09 0.00E+00 2.47E-05 Co-143 6.99E-09 3.79E-06 5.49E-10 0.00E+00 1.59E-09 0.00E+00 5 55E-05 Co-144 2.08E-06 6.52E-07 1.11E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-04 Pr-143 3.93E-08: 1.18E-08 1.95E-09 0.00E+00 6.39E-09 0.00E+00 4.24E-05 Pr-144 1.29E-10 ~3.99E-11 6.492-12 0.00E+00='2.11E-11 0.00E+00 8.59E-08 Ed-147 2.79E-06 2.26E-08 1.75E-09 0.00E+00 1.24E-08' 0.00E+00. 3.58E-05 W-187 4.295-07 2.54E-07 1.14E-07 0.00E+00 0.00E+00 0.00E+00 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 0.00E+00 2.79E-05

References:

~ Regulatory Guide 1.109, Table E-13. k Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Ane Snecific Radiation Dose Commitment Factors for a One Year Chronic Intake November, 1977, Table 4 3, NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 00591

L 4 l SQN ODCM s Revision 23 r. Page 93 of 146 Table 1.9 (7-of 8) INGESTION DOSE FACTORS (mrem /pci ingested) INFANT bone liver t body thyroid kidney lung 31-111_ t i H-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 0-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00- 0.00E+00 2.30E-05 Cr-51 0.00E+00 0.00E+00 1.41E-06 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 0.00E+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06 0.00E+00 7.31E-06 Mn-56 0.00E+00 8.18E-07 1.41E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 '1.143-06 ? Fe-59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.598-05 2.57E-05 E Co-57 0.00E+00 1.15E-06 1.87E-06 0.00E+00 0.00E+00 0.00E+00 3.92E-06 Co-58 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00. 0.00E+00 :8.97E-06 l 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 N1-65 4.70E-06 5.32E 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.05E-05 L 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 Zn-69m 1.50E-06 5.06E-06 2.79E-07 0.00E+00 1.24E-06 0.00E+00 4.24E i - Br-82 0.00E+00 0.00E+00 1.27E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l' Br-83 - 0.00E+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00.0.00E+00 L Br-84 0.00E+00 0.00E+00 3.82E-07 0.00E+00 0.00E+00L 0.00E+00 0.00E+00 lL Br-85 0.00E+00 0.00E+00- 1.94E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 s 'Rb 0.00E+00 1.70E-04 8'.40E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 1 Rb-88 0.00E+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00. 0.00E+00 4.85E-07 Rb-89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-08 Sr-89= 2.51E-03 0.00E+00 7.20E-05 0.00E+00 0.00E+00 0.00E+00 5.16E-05 Sr-90 1.85E-02 0.00E+00 4.71E-03 0.00E+00 '0.00E+00' 0.00E+00 2 31E-04 Sr-91 5.00E-05 0.00E+00 1.81E-06 0.00E+00' O.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 1 Y-90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y-91m 8.10E-10 0.00E+00 2.76E-11 0.00E+00 0.00E+00 0.00E+00' 2.70E-06 Y-91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05 Y-92 7.65E-09 0.00E+00 2.15E-10 0.00E+00 0.00E+00 0.00E+00 1.46E-04 E Y-93 2.43E-08 0.00E+00 6.62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 2r-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 0.00E+00 _1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05 Nb-97 4.59E-10 9.79E-11 3.53E-11 0.00E+00 7.65E-11 0.00E+00 3.09E-05 i k, E Mo-99 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 W Tc-99m 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 Ru-105 1.36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41E-05 Ru-106 2.41E-05 0.00E+00 3.01E-06 0.00E+00 2.85E-05 0.00E+00 1.83E-04 A8-110m 9.96E-07 7.27E-07 4.81E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0.00E+00 1.34E-05 6.60E-05 j 00591

=. SQN ODCM Revision 23 Pa8e 94 of 146 ' i Table 1.9 (8 of 8) INGESTION DOSE FACTORS 3 (ares /pci ingested) INFANT bone liver t body thyroin kidney lung 31-111-Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72E-06 1.64E-05 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-5.45E-05 1.94E-05 7.08E-06 1.69E-05 1.*4E-04 0.00E400 2.36E-05 i Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.00E+00 2.10E-05 .Te-129a 1.00E-04 3.43E-05 1.54E-05 3.845-05 2.50E-04 0.00E+00 5.97E-05 Te-129 2 848-07 9.79E-08 6.63E-08 2.38E-07; 7.07E-07 0.00E+00 2.27E-05 Te-131m 1.525-05 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 E I-130 6.00E-06 1.325-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 L I-131 3.59E-05 4.238-05 1.86E-05 1.39E-02 4.94E-0b 0.00E+00 1.51E-06 p I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0.00E+00 2.73E-06 ~ L I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.00E+00 3.088-06 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 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81E-04 7.42E-05 1.91E-06 l. Cs-136 4.598-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 -2.05E-06 L Cs-137 5.228-04 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 L 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 17.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 Ce-143 1s48E-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 i;- Pr-143-8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05' l Pr-144 2.748-10 1.06E-10 1.38E-11" 0.00E+00 '3.84E 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 g l 'W-187 9.03E-07 6.28E-07 2.17E-07 0.00E+00- 0.00E+00 0.00E+00 3.69E-05 Np-239-1.11E-08 9.93E-10 5.61E-10 0.00E+00 1.98E-09 0.00E+00 '2.87E-05 References Re8ulatory Guide 1.109, Table E-14. Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Ane Snecific Radiation Dose Commitment Factors for a One Year Chronic Intake., November, 1977, Table 4. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 00591

F l a R H i i D4 SQN ODCM -j Revision 23: Page 95 of 146 Table 1.10 (1 of 3) RADIONUCLIDE DECAY AND STABLE ELEMINT TRANSFER DATA By Fmi Imi - Ifi Half-Life X i (minutes) (1/s) (cow) (goat) (beef) l H-3 6.46E+06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1.20E-02 C-14 3.01E+09 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 i Na-24 9.00E+02-1.28E-05 5.20E-02 4.00E 4.00E-02 3.00E-02 P-32 2.06E+04 5.61E-07 1.10E+00 2.50E-02 '2.50E-01 4.60E-02 Cr-51 3.99E+04 2.90E-07 2.50E-04 2.20E-03 2.205-03 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 2.50E-04 8.00E-04 Fe-05 1.42E+06 8.13E-09 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E 1.30E-04 1.20E Co-57 3.90E+05 2.96E-08 9.40E-03 1.00E-03 1.00E-03 1.30E-02 L Co-58 1.02E+05 1.13E-07 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-60 2.77E+06 4.17E-09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Ni-63 ~ 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Mi-65 1.51E+02 7.65E-05 1.90E-02 6.70E 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-01 3.002-02 2n-69m-8.26E+02 1.40E-05 4.00E-01 3.90E-02 3.90E-02 3.00E-02 .Zn-69 5.56E+01 2.08E-04 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Br-82 2.12E+03 5.45E-06 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br,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 2.60E-02 Br-85 2.87E+00' 4.02E-03 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Rb-86 2.69E+04 4.29E-07 1.30E-01 3.00E.02 3.00E-02 3.10E-02 Rb-88 1.78E+01 6.49E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-A9 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.00E-02 3.10E Sr-09 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr 1.50E+07 7.70E-10 1.701-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.03E-05 1.70i S2 1.40E-03 1.40E-02 6.00E-04 i 1 Sr-92

1.63E+02' 7.09E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Y-90' 3.85E+03 3.00E-06 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-Gla 4.97E+01' 2.32E-04 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03

? Y-92 2.12E+02 5.45E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-93 6.06E+02 1.91E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Zr-95 9.22E+04 1.25E-07 1.70E-04 5.00E-06 5.00E-06 3.40E-02 4: Zr-97 1.01E+03 1.14E-05 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95 5.05E+04 2.29E-07 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Rb-97 1.21E+01 1.60E-04 9.40E 2.50E-03 2.50E-03 2.80E L 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 4.00E-01 l-Ru-103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E-01 l Ru-105 2.66E+02 4.34E-05 5.00E-02 1.00E-06 1.00E-06 4.00E-01 L Ru-106' 5.30E+05 2.18E-08 5.00E-02 1.00E-06 1.00E-06 4.00E-01 As-110m 3.bOE+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 00591 l I' I i

l SQN ODCM Revision 23 i PaSe 96 of 146 Table 1.10 (2 of 3)- I EADIONOCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life 1 81y Fai Imi Fri (minutes) (1/s) 8b-124 (cow) (8ont) (beef) ~ 8.67E+04 1.333-07 N/A 1.50E-03 1.50E-03 N/A -8b-125 1.46E+06 7.91E-09 N/A 1.50E-03 '1.50E-03= -N/A Te-125m 8.35E+04 1.385-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 1 Te-127m 1.575+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-129s 4.84E+04 2.39E-07 1.30E+00 1.00E 1.00E-03 7.70E-02 Te-129 '6.96EtL1 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 1.003-03 1.00E-03 7.70E-02 To-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 1.168+04 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 r I-132 1.388+02 8.378-05 2.00E 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 2.905-03 I-134 5.26E+01 2.20E-04 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-135 3.975+02 2.91E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 Cs-134 1.08E+06 1.068-08 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 1.598+07 7.268-10 1.00E-02 8.005-03 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 l' Ba-139-8.31E+01 1.39E-04 5.00E-03 4.00E-04 .4.00E-04 3.20E-03 t 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 i u Ba-142 1.07E+01 1.08E-03 5.00E-03 4.00E 4.00E-04 3.20E-03 L t La-140 2.41E+03 4.79E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 La-142 9.54E+01 1.21E 2.50E-03 5.005-06 5.00E-06 2.00E-04 Co-141 4.68E+04 2.47E-07 2.50E-03 1.00E-04 1.00E-04 1.205-03 Co-143 1.98E+03 5.83E 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Co-144 4.09E+05 2.82E-08 2.50E-03 1.005-04 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-144J 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 Mp-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-83a 1.10E+02 1.05E-04 N/A N/A N/A N/A L Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A N/A 1 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 1.70E+02 6.79E-05 N/A N/A N/A N/A Kr-89 3.162+00- 3.66E-03 N/A N/A N/A N/A Kr-90 5.39E-01 2.14E N/A N/A N/A N/A Xe-131m 1.70E+04 6.793-07 N/A N/A N/A N/A y Xe-133m 3.15E+03 3.67E-06 N/A N/A N/A N/A 00591 l' \\,

t ( N SQN ODCM Revision 23 Page-97 of 146 i Table 1.10 (3 of 3) ~; RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA By Fmi Imi Fri ) Half-Life 1 i (cow) (goat) (beef) .(minutes) (1/s). t., Xe-133 7.55E+03 1.53E-06 N/A N/A N/A-N/A Xe-135m 1.54E+01 '7.50E-04 N/A N/A N/A N/A Xe-135 5.47E+02 2.11E-05 N/A N/A N/A N/A Xe-137 3.83E+00 3.02E-03 N/A N/A N/A N/A Xe-138-1.41E+01 8.19E-04 N/A N/A N/A N/A Referencest' 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 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. L0 00591 l-1

e i I SQN ODCM Revision 23 Page 98 of 146 Table 1.11 (1 of 2) DOSE CALCULATION FACTORS Factor. Value Units Reference i bra (infant) 1400 m3/ year. ICRP 23 bra (child): 5500 a8/ year ICRP 23 bra (teen) 8000 m8/ year ICRP 23 bra (adult) 8100 m8/ years ICRP 23 f 1 TVA Assumption g., fL. 1 R. G. 1.109 (Table E-15) f 1 TVA Assumption p is 0 TVA Assumption R 9 g/a8. TVA Value K 0.072 L/ks-hr R. G. 1.109 (Section 2.C.) e M 40 kg/ma R. G. 1.109 (Section 2.C.) P 240 kg/ma R. G. 1.109 (Table E-15) Qg (cow) 64 kg/ day .NUREG/CR-1004-(Sect. 3.4) . Qg (goat) 08 kg/ day 'NUREG/CR-1004 (Sect. 3.4) r 0.47 NUREG/CR-1004 (Sect. 3.2). tb 4.73E+08 seconds R. G. 1.109.(Table E-15) (15 years) tcb 7.78E+06 seconds SQN FSAR Section 11.3.9.1 (90 days) teeg 1.56E+07 seconds SQN FSAR Section 11.3.9.1 (180 days) t 5.18E+06 seconds R. G. 1.109 (Table'E-15) o (60 days) top 2.59E+06, seconds-R. G. 1.109 (Table E-15) (30 days) t,,g 7.78E+06 seconds R. G. 1.109-(Table E-15) (90 days) tfa 8.64E+04 seconda SQN FSAR Section 11.3.9.1 (1 day) the 8.64E+04 seconds NUREG/CR-1004, Table 3.40 (1 day)- t 1.12E+06 seconds NUREG/CR-1004, Table 3.40-s (13 days) t 2.38E+07 seconds SQN FSAR Section 11.3.9.1. oy. (275 days) Una (infant) 0 kg/ year R. G. 1.109 (Table E-5) Usa (child) 41 kg/ year R. G. 1.109 (Table E-5) Uam (teen) 65 kg/ year R. G. 1.109 (Table E-5) Una (adult) 110 kg/ year R. G.'1.109 (Table E-5) U. (infant) 330 L/ year R. G. 1.109 (Table E-5) U. (child) 330 L/ year R. G. 1.109 (Table E-5) Ua (teen) 400 L/ year R. G. 1.109 (Table E-5) L U (adult) 310 L/ year R. G. 1.109 (Table E-5) a 00591 E.-

~-.,_ _ sil g; SQN.0DCM Revision 23 Page 99 of 146 4 Table 1.11 (2 of 2) DOSE CALCULATION FACTORS 'I Factor' Value Units Reference I 'Ufa(infant) 0. kg/ year R. G. 1.109.(Table E-5) I U a(child) 6.9 kg/ year R.'G. 1.109 (Table E-5) { f U a(teen)~ 16 kg/ year R. G. 1.109 (Table E-5) 1 f U a(adult) 21 kg/ year R. G. 1.109 (Table E-5)- f

UFLa (infant)-

0 kg/ year 'R. G. 1.109 (Table B-5)' UFLa (child). 26-kg/ year R. G. 1.109 (Table E-5) UFLa (teen) 42 kg/ year R. G. 1;109 (Table E-5) J UFLa (adult) 64 kg/ year R.'G.'1.109 (Table E-5) h U a.(infant) 0 kg/ year R. G. 1.109 (Table E-5)' S U a (child) 520 kg/ year R. G. 1.109 (Table E-5)- S U a-(teen) 630 kg/ year R. G.:1.109 (Table E-5) S .U a (adult) 520 kg/ year R. G. 1.109 (Table-E-5) S L Uwa(infant) 330 L/ year-R. G. 1.~109 (Table E-5). l~ Uv.(child) 510 L/ year-R. G. 1.109-(Table E-5). Uwa(teen) 510 L/ year R. G. 1.109 (Table'E-5) Uwa(adult) 730 'L/ year R. G. 1.109 (Table E-5) W-0.3 none R. G. 1.109 (Table A-2) Yg 1.85 kg/ma NUREG/CR-1004 (Table 3.4)- Y 1.18 kg/ma p NUREG/CR-1004 (Table 3.3) Yag 0.64 kg/ma NUREG/CR-1004 (Table 3.3). Ysy 0.57 kg/ma HUREG/CR-1004 (Table 3.4) (value selected is for non-leafy. vegetables) .N (iodines) 7.71E-07.see-1 NUREG/CR-1004 (Table'3.10) i (15.4 d half-life) N (particulates) 5.21E-07 sec-1 NUREG/CR-1004 (Table 3.10) (10.4 d half-life) 00591 l l u ..f-

o SQN ODCM Revision 23 Pate 100 of 146 Table 1.12 (1 of 8) INHALATION DOSE FACTORS (aram/pc1 inhaled) ADULT bone Ifver t body thyroid kidney lung gi-111 H-3 1.54E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.54E C-14 2.275-06 4.262-07 4.26E-07 4.26E-07 4.262-07 4.26E-07 4.26E-07 Ra-24 1.285-06 1.285-06 1.24E-06 1.28E-06 1.28E-06 1.283-06 1.24E P-32 1.655-04 9.648-04 6.26E-06 0.00E+00 0.00E+00 0.00E+00 1.08 Cr-51 0.00E+00 0.00E+00 1.25E-06 7.448-09 2.85E-09 1.403-06 4.15E-0 Mn-54 0.00E+00 4.95E-06 7.4ft-07 0.00E+00 1.23E-06 1.753-04 9.678-0 Mu-56 0.00E+00 1.55E-10 2.29E-11 0.00E+00 1.638-10 1.18E-06 2.538 Fe-55 3.07E-06 2.125-06 4.93E-07 0.00E+00 0.00E+00 9.01E-06 7.54E Fe-59 1.478-06 3.47E-06 1.328-06 0.00E+00 0.00E+00 1.272-04 4.35 Co-37 0 00E+00 8.65E-08 8.398-08 0.00E+00 0.00E+00 4.62E-05 3.93E Cn-32 0.00E+00 1.98E-07 2.59E-07 0.00E+00 0.00E+00 1.13E-04 1.33 'Co-60 0.00E+00 1.44E-06 1.45E-06 0.00E+00 0.00E+00 7.465-04 3.56 R1-63 5.40E-05 3.93E-06 1.818-06 0.00E+00 0.00E+00 2.23E-05 1.57 Ri-65 1.92E-10 2.628-11 1.14E-11 0.00E+00 0.00E+00 7.00E-07 1.54 Cu-64 0.00E+00 1.838-10 7.69E-11 0.00E+00 5.74E-10 8.48E-07 6.12E En-65 4.058-06 1.295-05 5.42E-06 0.00E+00 8.625-06 1.08E-04 6.68E-En-69 4.138-12 8.14E-12 5.65E-13 0.00E+00 5.27E-12 1.15E-07 2.045 2n s9s 1.02F-09 2.45E-09 2.24E-10 0.00E+00 1.48E-09 2.38E-06 1.71 Br-82 0.00E+00 0.00E+00 1.69E-06 0.00E+00 0.00E+00 0.00E+00 1.30 Br-83 0.00E+00 0.00E+00 3.013-08 0.00E+00 0.00E+00 0.00E+00 2.9 Er-84 0.00E+00 0.00E+00 3.91E-04 0.00E+00 0.00E+00 0.00E+00 2.0 Br-45 0.00E+00 0.00E+00 1.60E-09 0.00E+00 0.00E+00 0.00E+00 0.0 i Rb-86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E+00 2.0 Rb-88 0.00E+00 4.84E-08 2.41E-08 0.00E+00 0.00E+00 0.00E+00 4.18 Eb-89 0.00E+00 3.20E-08 2.12E-08 0.00E+00 0.00E+00 0 00E+00 1.1 $r-89 3.80E-05' O.00E+00 1.09E-06 0.00E+00 0.00Z+00 1.75E-04 4.3 3r-90 1.24E-02 0.00E+00 7.62E-04 0.00E4 00 0.00E+00 1.20E-03 9.0 St-91 7.74E-09 0.00E+00 3.13E-10 0.00E+00 0.00E+00 4.56E-06 2.3 Sr-92 8.435-10 0.00E+00 3.64E-11 0.00E+00 0.00E+00 2.06E-06 S.3 Y-90 2.61E-07 0.00E+00 7.01E-09 0.00E+00 0.00E+00 7.12E-05 6.3 Y-91a 3.26E-11 0.00E+00 1.27E-12 0.00E+00 0.00E+00 2.40E-07 1.6 Y-91 5.785-05 0.00E+00 1.558-06 0.00E+00 0.00E+00 2.13E-04 4.8 Y-92 1.298-09 0.00E+00 3.77E-11 0.00E+00 0.00E+00 1.96E-06 9. Y-93 1.185-08 0.00E+00 3.26E-10 0.00E+00 0.00E+00 6.06E-06 5.2 Er-95 1.34E-05 4.30E-06 2.91E-06 0.00E+00 6.77E-06 2.21E-04 1.8 Er-97 1.21E-08 2.45E-09 1.135-09 0.00E+00 3.71E-09 9.84E-06 6.54E Nb-95 1.76E-06 9.77E-07 5.26E-07 0.00E+00 9 67E.r.? 6.31E-05 1.30 Nb-97 2.788-11 7.03E-12 2.56E-12 0.00E+00 8.18E-14 3.00E-07 3.02E Mo-99 0.00E+00 1.51E-08 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.10E Tc-99m 1.295-13 3.64E-13 4.63E-12 0.00E+00 5.52E-12 9.55E-08 5.20E Tc-101 5.22E-15 7.52E-15 7.38E-14 0.00E+00 1.35E-13 4.99E-08 1.36E Ru-103 1.91E-07 0.00E+00 8.23E-08 0.00E+00 7.29E-07 6.31E-05 1.38E Ru-105 9.885-11 0.00E+00 3.89E-11 0.00E+00 1.27E-10 1.37E-06 6.02E-Ru-106 8.64E-06 '0.00E+00 1.09E-06 0.00E+00 1.67E-05 1.17E-03 1.14E-0 A4-130w 1.35E-06 1.25E-06 7.43E-07 0.00E+00 2.46E-06 5.79E-04 3.78E Sb-124 3.90E-06 7.36E-08 1.K5E-06 9.44E-09 0.00E+00 3.10E-04 5.08E-0 00591

SQN ODCM Revision 23 i Pa8e 101 of 146 j i Table 1.12 (2 of 8) INHALATION DOSE FACTORS (mrem /pc1 inhaled) ADULT [ bone liver t body thyroid kidney lung 81-111 Sb-125 6.67E-06 7,44E-08 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.26E-05 [ Te-125a 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127a 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 4.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129a 1.228-06 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-131a 4.748-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 i Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 ( I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0.00Z+00 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.00E+00 5.08E-08 I-133 1.04R-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 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07 i 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 4.84E-06 1.83E-05 1.38E-05 0.00E+00 1.07E-05 1.50E-06 1.46E-06 Co-137 5.98E-05 7.76E-05 5.35E-05 0.00E+00 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 0.00E+00 6.00E-08 6.07E-09 2.33E-13 Ba-139-1.17E-10 8.32E-14 3.42E-12 0.00E+00 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 0.00E+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 0.00E+00 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 0.00E+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 0.00E+00 0.00E+00 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 0.00E+00 0.00E+00 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 0.00E+00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-04 1.72E-08 1.91E-09 0.00E+00 7.60E-09 9.97E-06 2.83E-05 Co-144 4.29E-04 1.79E-04 2.30E-05 0.00E+00 1.06E-04 9.72E-04 1.025-04 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 Mp-239 2.878-08 2.82E-09 1.55E-09 0.00E+00 8.75E-09 4.70E-06 1.49E-05 I Reference Re8ulatory Guide 1.109, Table E-7. Dose factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Ane Seeelfic Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 4. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 00591 w

SQN ODCM Revision 23 Pa8e 102 of 146 ) Table 1.12 (3 of 8) INEALATION DOSE FACTORS (ares /pci inhaled) 1 TEEN i bone liver t body thyroid kidney lung 81-111 E-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-0 C-14 3.258-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07; Na-24 1.728-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-0! P-32 2.368-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1.16E-Cr-51 0.02E+00 0.00E+00 1.69E-08 9.37E-09 3.84E-09 2.6tt-06 3.75E-0t Mn-54 0.00E+00 6.39E-06 1.0$E-06 0.00E+00 1.59E-06 2.48E-04 8.35E-Mn-56 0.00E+00 2.128-10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 7.18E Fe-55 4.143-04 2.988-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E Fe-59 1.998-06 4.62E-06 1.79E-06 0.00E+00.0.00E+00 1.91E-04 2.2 Co-57 0.00E+00 1.18E-07 1.15E-07 0.00E+00 0.00E+00 /.33E-05 3.93E i Co-58 0.00E+00 2.59E-07 3.47E-07 0.00E+00 0.00E+00 1.682-04 1.19 Co-60 0.00E+00 1.89E-06 2.48E-06 0.00E+00 0.00E+00 1.095-03 3.24 Ni-63 7.255-05 5.43E-06 2.47E-06 0.00E+00 0.00E+00 3.845-05 1.77 N1-65 2.733-10 3.66E-11 1.59E-11 0.00E+00 0.00E+00 1.17E-06 4.59 Cu-64 0.00E+00 2.545-10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.68 En-6b 4.825-06 1.67E-05 7.40E-06 0.00E+00 1.08E-05 1.55E-04 5.83 En 6.045-12 1.15E-11 8.07E-13 0.00E+00 7.53E-12 1.98E-07 3.56E En-69e 1.448-09 3.39E-09 3.11E-10 0.00E+00 2.06E-09 3.92E-06 2.14 Br-82 0.00E+00 0.00E+00 2.28E-06 0.00E+00 0.00E+00 0.00E+00 0.i Br-83 0.00E+00 0.00E+00 4.30E-04 0.00E+00 0.00E+00 0.00E+00 0. Br-84 0.00E+00 0.00E+00 5.41E-08 0.00E+00 0.00E+00 0.00E+00 0.0 Br-85 0.00E+00 0.00E+00 2.29E-09 0.00E+00 0.00E+00 0.00E+00 0.0 Rb-86 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.2 Rb-88 0.00E+00 6.82E-08 3.40E-08 0.00E+00 0.00E+00 0.00E+00 3.6 Rb-89 0.00E+00 4.40E-08 2.91E-08 0.00E+00 0.00E+00 0.00E+00 4.2 I Sr-89 5.438-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4 Sr-90 1.35E-02 0.00E+00 8.35E-04 0.00E+00 0.00E+00 2.06E-03 9 St-91 1.103-08 0.00E+00 4.39E-10 0.00E+00 0.00E+00 7.59E-06 3 Sr-92 '.19E-09 0.00E+00 5.08E-11 0.00E+00 0.00E+00 3.43E-06 1.4 Y-90 3.73R-07 0.00E+00 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.99 i Y-91m 4.63E-11 0.00E+00 1.77E-12 0.00E+00 0.00E+00 4.00E-07 3.77 Y-91 8.265-05 0.00E+00 2.21E-06 0.00E+00 0.00E+00 3.67E-04 5.112 Y-92 1.84E-09 0.00E+00 5.36E-11 0.00E+00 0.00E+00 3.35E-06 2.06 Y-93 1.698-04 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24 Er-95 1.828-05 5.138-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.86E 1 Er-97 1.725-04 3.40E-09 1.57E-09 0.00E+00 5.15E-09 1.62E-05 7.88E l Nb-95 2.323-06 1.298-06 7.08E-07 0.00E+00 1.25E-06 9.39E-05 1.21E-0 Nb-97 3.928-11 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2.71E-0 Mo-99 0.00E+00 2.11E-08 4.03E-09 0.00E+00 5.14E-08 1.92E-05 3.36E ~' Tc-99m 1.738-13 4.83E-13 6.24E-12 0.00E+00 7.20E-12 1.44F-07 7.66E-Tc-101 7.40E-15 1.05E-14 1.03E-13 0.00E+00 1.90E-13 8.342-08 1.09E-Ru-103 2.63E-07 0.00E+00 1.12E-07 0.00E+00 9.29E-07 9.79E-05 1.36E-Ru-105 1.40E-10 0.00E+00 5.42E-11 0.00E+00 1.76E-10 2.27E-06 1.13E Ru-106 1.23E-05 0.00E+00 1.55E-06 0.00E+00 2.38E-05 2.01E-03 1.20E-A8-110s 1.73E-06 1.64E-06 9.99E-07 0.00E+00 3.13E-06 8.44E-04 3.41E-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 00591 L s

I SQN ODCM Revision 23 Pate 103 of 146 Table 1.12 (4 of 8) INilALATION DOSE TACTORS (mrem /pCi inhaled) TEEN bone liver t body thyroid kidney lung 41-111 $b-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-05 Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 0.00E+00 6.70E-05 9.38E-06 Te-127a 2.255-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.515-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129a 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131a 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-11 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-04 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.862-04 3.44E-06 0.00E+00 1.14E-06 1-131 4.435-06 6.14E-06 3.30E-06 1.83E-03 1.0$E-05 0.00E+00 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-07 1-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E-06 I-134 1.118-07 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 6.285-05 1.41E-04 6.86E-05 0.00E+00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 0.00E+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 0.00E+00 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 0.00E+00 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.54E-04 2.86E-05 Bo-141 1.78E-11 1.32E-14 5.93E-13 0.00E+00 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 0.00E+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-04 2.95E-08 7.82E-09 0.00E+00 0.00E+00 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 0.00E+00 0.00E+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 0.00E+00 1.11E-06 7.67E-05 1.58E-05 Co-143 3.32E-08 2.42E-08 2.70E-09 0.00E+00 1.08E-08 1.63E-05 3.19E-05 Co-144 6.11E-04 7.53E-04 3.28E-05 0.00E+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 0.00E+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 0.00E+00 1.26E-12 2.19E-07 2.94E-14 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-0; 2.21E-09 0.00E+00 1.25E-08 8.11E-06 1.65E-05 References g Regulatory Guide 1.109, Table E-8. Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Ane Soecific Radiation Dose Commitment factors for a One Yeat_ Chronic Intake. November 1977 Table 8. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 00591

I i l SQN ODCM i Revision 23 Page 104 of 146 l Table 1.12 ($ of 8) l INEALATION DOSE FACTORS (aram/pC1 inhaled) CHILD l bone liver t body thyroid kidney lung gi-?1i H-3 3.043-07 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 i Na-64 4.35E-06 4.353-06 4.353-06 4.35E-06 4.35E-06 4.353-06 4.35E-06 P-32 7.045-04 3.09E-05 2.678-05 0.00E+00 0.00E+00 0.00E+00 1.14E-05 Cr-51 0.00E+00 0.00E+00 4.173-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 i 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 0.00B+00 4.488-10 8.43E-11 0.00E+00 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.24E-05 6.808-06 2.10E-06 0.00E+00 0.00E+00 3.00E-05 7.75E-07 Fe-59 5.593-06 9.04E-06 4.51E-06 0.00E+00 0.00E+00 3.43E-04 1.91E-05 t Co-57 0.00E+00 2.44E-07 2.88E-07 0.00E+00 0.00E+00 1.37E-04 3.58E-06 Co-58 0.00E+00 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2.99E-04 9.29E-06 l 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 8.085-10 7.99E-11 4.44E-11 0.00E+00 0.00E+00 2.21E-06 2.27E-05 Cu-64 0.00E+00 5.39E-10 2.90E-10 0.00E+00 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.158-05 3.06E-05 1.90E-05' O.00E+00 1.93E-05 2.69E-04 4.41E-06 En-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 0.00E400 Br-83 0.00E+00 0.00E+00 1.28E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 1.48E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-45 0.00E+00 0.00E+00 6.84E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Eb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+00 2.16E-06 Rb-88 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E-09 Rb-49 0.00E+00 9.33E-08 7.83E-08 0.00E+00 0.00E+00 0.00E+00 5.11E-10 Sr-89 1.628-04 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr-90 2.735-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 St-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 St-92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E-06 6.5bE-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-91a 1.375-10 0.00E+00 4.98E-12 0.00E+00 0.00E+00 7.60E-07 4.64E-07 i Y-91 2.478-04 0.00E+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.97E-05 i Y-92 5.50E-09 0.00E+00 1.57E-10 0.00E+00 0.00E+00 6.46E-06 6.46E-05 Y-93 5.045-08 0.00E+00 1.38E-09 0.00E+00 0.00E+00 2.01E-05 1.05E-04 Zr-95 5.135-05 1.135-05 1.00E-05 0.00E+00 1.61E-05 6.03E-04 1.65E-05 2r-97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.481-06 1.77E-06 0.00E+00 2.33E-06 1.66E-04 1.00E-05 Nb-97 1.16E-10 2.08E-11 9.74E-12 0.00E+00 2.31E-11 9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99a 4.818-13 9.41E-13 1.56E-11 0.00E+00 1.37E-11 2.57E-07 1.30E-06 l Tc-101 2.19E-14 2.30E-14 2.91E-13 0.00E+00 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 0.00E+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 0.00E+00 1.50E-10 0.00E+00 3.63E-10 4.30E-06 2.69E-05 l Ru-106 3.68E-05 0.00E+00 4.57E-06 0.00E+00 4.97E-05 3.87E-03 1.16E-04 i As-110m 4.56E-06 3.08E-06 2.47E-06 0.00E+00 5.74E-06 1.48E-03 2.71E-05 Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 0.00E+00 8.76E-04 4.43E-05 00591

v SQN ODCM Eevision 23 Page 105 of 146 i i Table 1.12 (6 of 8) INHALATION DOSE FACTORS (mrem /pci inhaled) CilILD bone liver t body thyroid kidney lung gi-111 i $b-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.00E400 6.27E-04 1.09E-05 Te-125a 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.00E+00 1.29E-04 9.13E-06 l Te-127a 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 l Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129s 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 i Te-131a 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0.00E+00 1.38E-06 f I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0.00E+00 7.68E-07 1-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0.00E+00 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0.00E+00 1.48E-06 t-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.00E+00 2.58E-07 1-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0.00E+00 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 0.00E+00 8.93E-05 3.27E-05 1.04F-06 Co-136 1.76E-05 4.62E-05 3.14E-05 0.00E+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 0.00E+00 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 0.00E+00 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 0.00E+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 0.00E+00 0.00E+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 0.00E+00 0.00E+00 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.2BE-06 7.83E-07 0.00E+00 2.31E-06 1.47E-04 1.53E-05 Co-143 9.89E-08 5.37E-08 7.77E-09 0.00E+00 2.26E-08 3.12E-05 3.44E-05 Co-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.0$E-04 [. Pr-143 4.99E-06 1.50E-06 2.47E-07 0.00E+00 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 0.00E+00 2.64E-12 4.23E-07 5.32E-08 i Nd-147 2.92E-06 2.36E-06 1.84E-07 0.00E+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 0.00E+00 0.00E+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.57E-05 1.73E-05 l References. 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 NUREG-0172 Aae Soeelfle Radiation Dose Commitment Factore for a One Year l Chronic Intake. November 1977, Table 8. l L NOTE: The tritium dose factor for bone is assumed to be equal to the l total body dose factor. l 00591 l l l

i SQN ODCM l Revision 23 { Pete 106 of 146 I l Table 1.12 (7 of 8) INEALATION DOSE FACTORS (area /pci inhaled) j INTANT bone liver t body thyroid kidney lung 41-111 H-3 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 i C-14 1.898-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.798-06 3.79E-06 Na-24 7.545-06 7.548-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.455-03 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 6.393-04 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 5.048-06 Mn-56 0.00E+00 1.10E-09 1.58E-10 0.00E+00 7.46E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 Fe-59 9.698-06 1.688-05 6.77E-06 0.00E+00 0.00E+00 7.25E-04 1.77E-05 Co-57 0.00E+00 4.65E-07 4.582-07 0.00E+00 0.00E+00 2.71E-04 3.47E-06 i Co-58 0.00B+00 8.71E-07 1.30E-06 0.00E+00 0.00E+00 5.55E-04 7.955-06 Co-60 0.00E+00 5.73E-06 8.41E-06 0.00E+00 0.00E+00 3.22E-03 2.28E-05 i Ni-63 2.423-04 1.46E-05 8.29E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 Ni-65 1.715-09 2.03E-10 8.79E-11 0.00E+00 0.00E+00 5.80E-06 3.58E-05 Cu-64 0.00E+00 1.34E-09 5.53E-10 0.00E+00 2.84E-09 6.64E-06 1.07E-05 L Zn-65_ 1.385-05 4.47E-05 2.220-05 0.00E+00 2.32E-05 4.62E-04 3.67E-05 En-69 3.853-11 6.91E-11 5.13E-12 0.00E+00.t.87E-11 1.05E-06 9.44E-06 En-69a 8.983-09 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 0.043+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 2.72E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 2.86E-07 0.00E+00 0.00E+0b 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 0.002+00 0.00E+00 4.87E-08 St-89 2.84B-04 0.00E+00 8.15E-06 0.00E+00 0.00E+00 1.45E-03 4.57E-05 St-90 2.928-02 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr-91 6.833-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05 St-92 7.50E-09 0.00E+00 2.79E-10 0.00E+00 0.00E+00 1.70E-05 1.00E-04 Y-90 2.35E-06 0.00E+00 6.30E-08 0.00E+00 0.00E+00 1.925-04 7.43E-05 l Y-91m 2.915-10 0.00E+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 i Y-91 4.205-04 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1.75E-03 5.02E-05 l Y-92 1.175-04 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.75E-05 9.04E-05 Y-93 1.078-07 0.00E+00 2.91E-09 0.00E+00 0.00E+00 5.46E-05 1.19E-04 Zr-95 8.245-05 1.99E-05 1.45E-05 0.00E+00 2.22T-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 1.125-05 4.598-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.05E-06 Nb-97 2.448-10 5.21E-11 1.88E-11 0.00E+00 4.07E-11 2.37E-06 1.92E-05 Mo-99 0.00E+00 1.18E-07 2.31E-08 0.00E+00 1.89E-07 9.63E-05 3.48E-05 Tc-99a 9.98E-13 2.06E-12 2.66E-11 0.00E+00 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-04 5.80E-13 0.00E+00 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 0.00E+00 4.85E-07 0.00E+00 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 0.00E+00 2.93E-10 0.00E+00 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 0.00E+00 7.77E-06 0.00E+00 7.61E-05 8.26E-03 1.17E-04 As-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 00591 ~

L SQN OD;M Revision 23 Page 107 of 146 Table 1.12 (8 of B) INHALATION DOSE TACTORS (mrem /pCi inhaled) INFANT bone liver t body thyroid kidney lung gi-111 Sb-125 3.69E-05 3.41E-07 7.7BE-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.48E-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. ?.0E-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 l

Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E+00 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.00E+00 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 I-134 6.583-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.0$E-06 0.00E+00 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 0.00E+00 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 0.00E+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 0.00E+00 1.23E-04 5.09E-05 9.53E-07 Co-138 3.61E-07 5.58E-07 2.84E-07 0.00E+00 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 0.00E+00 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 0.00E+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 0.00E+00 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 0.00E+00 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 0.00E+00 0.00E+00 1.20'-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 0.00E+00 0.00E+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 0.00E+00 4.03E-08 8.30E-05 3.55E-05 Co-144 2.28E-03 8.65E-04 1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 0.00E+00 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 0.00E+00 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 0.00E+00 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 0.00E+00 0.00E+00 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 0.00E+00 4.73E-08 4.25E-05 1.78E-05

Reference:

Re8ulatory 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 Ane Specific Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 8. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 00591 I l l

!h 1 SQN ODCM Revision 23 f Page 108 of 146 l Table 1.13 (1 of 2) EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND a (ares /h per pCi/m ) i i Nuclide Total Body. Skin l N-3 0.0 0.0 I C-14 0.0 0.0 l Na-24 2.50E-04 2.90E-04 P-32 0.0 0.0 i Cr-51 2.20E-10 2.60E-10 t Nn-54 5.40E-09 6.80E-09 t l-Mn-56 1.10E-08 1.30E-08 - i Fe-55 0.0 0.0 I Fe-59 8.00E-09 9.40E-09 Co-57 1.77E-09 2.21E-09 f Co-58 7.00E-09 4.20E-09 i Co-60 1.70E-04 2.00E-08 Ni-63 0.0 0.0 N1-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 2n-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 En-69m 5.50E-09 6.59E-09 i Br-42 3.18E-08 3.90E-08 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0' Rb-86 6.30E-10 7.20E-10 Rb-48 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.60E-08 i Sr-89 5.60E-13 6.50E-13 8r-91 7.105-09 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 Er-95 5.00E-09 5.80E-09 L Zr-97 5.50E-09 6.40E-09 l Nb ^* 5.10E-09 6.00E-09 l Nb-97 8.11E-09 1.00E-08 No-99 1.90E-09 2.20E-09 Tc-99a 9.60E-10 1.10E-09 l Tc-101 2.70E-09 3.00E-09 20-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 As-110s 1.80E-08 2.10E-04 Sb-124 2.17E 08 2.57E-08 00591 i ~

P SQN ODCM Revision 23 Pa8e 109 of 146 i Table 1.13 (2 of 2) EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND l (aram/h per PC1/at) Nuclide Total Body Skin i Sb-125 5.48E-09 6.80E-09 Te-125a 3.50E-11 4.80E-11 Te-127a 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129s 7.70E-10 9.00E-10 i Te-129 7.10E-10 8.40E-10 { Te-131a 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 2.80E-09 3.40E-09 o I-132 1.70E-08 2.00E-08 i I-133 3.70E-09 4.50E-09 1-134 1.60E-08 1.90E-08 1-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 l Cs-136 1.50E-04 1.70E-08 Co-137 4.20E-09 4.90E-09 Co-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 r 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 Co-141 5.50E-10 6.20E-10 Co-143 2.20E-09 2.50E-09 Co-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 > 60E-09 Np-239 9.50E-10 1.10E-09 I

References:

Regulatory Guide 1.109, Table E-6. h" Dose Factors for Co-57, 2n-69a, Br-82, Nb-97, Sb-124 and Sb-125 are from Dona-Rate Conversion Factors for External Ernosure to Photon and Electron Radiation from Radionuclides Occurrina in Routine Releases from Nuclear Fuel Cycle Facilities. D. C. Kocher, Health Physics Volume 38, April 1980. 00591 i 1

I sqN oDCu Revision 23 Page 110 of 146 Table 2.1 (Page 1 of 4) RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAN ~ Liquid l l Minimum ITyPe of ILower Limit of Release i Sampling l Analysis lActivity IDetection (LLD) Type I yrequency l Prequency lAnalysis f(pC1/ml)a I I I I A. Batch Waste i P l P l l Release l Each Batch i Each Batch l Principal l 5x10-7 Tanked I l l Camuna I l l I taittersf i

1. Weste Con-1 I

I I densate l l l I-131 1 1X10-* l Tanks (3) l I I l l i i 1 i

2. Cask Decon-l P

l N IDissolved/ I 1x10-8 tamination lone B tch/M i lEntrained l Tank I l IGases (Gansea l l l IEmitters) l

3. Laundcy l

I I I Tanks (2) l P l M l H-3 l 1x10-8 ) i Rach Batch ICompositab l 1

4. Chemical l

I I Gross i 1x10-' Drain Tank l 1 l Alpha l l l l l

5. Monitor Tank I i

l l l l l l ]

6. Distillate i

i l l Tanks (2) i I I I l P l Q l I

7. Condensate l Each Batch ICospositeb i Sr-89, l 5x10-e Domineraliser i l

I sr-90 I Waste l I i I tvaporator l l l Fe-55 l 1x10-* Blowdown I i l l Tank (1) 1 I i i B. Continuous 1-D l W IPrincipal I 5x10-' Releasese IGrab Sample lComptsitec lGasuna l i I Itaittersf I I I I I i

1. Steam i

I I i ) Generatorh l l l y_131 l 1xio-o r Blowdown l I I I i l-l M i M IDissolved/ I 1x10-' 4

2. Turbine IGrab Sample l

l Entrained I l i I IGases (Ganuna i Buildingh l I IEmitters) l Sump l D l M l H-3 1 1x10-5 IGrab Sample ICompositec l I ,1 l l Gross Alpha i 1x10-' Grabhample comphsite c sre->> 1xta = 1 I I l 00591 1 .._____.._.______~.j

~ l t L 1 i SQE ODCE~ Revision 23 Page 111 of 146 Table 2.1 (Page 2 of 4) RADICACTIVE LIQUID WASTE SANFLING AND ANALYSIS PROGRAM Liquid 1 IMinisua IType of .ILower Limit of Release i Sampling lAnalysis lActivity IDetection (LLD) Type i Prequency IFrequency lAnalysis l(yCi/al)a 1 I i I C. Periodic l l W l Principal 1 5x10-' Continuous lContinuousE ICompositec IGamuna 1 Releases #eh l l lEmitteraf I I I I I 4 I I I I-131 1 1x10-*

1. Non-Reclais-I l

l I able Weste l NS l M IDissolved i 1x10-8 I Tank l Grab Sample I land i I l l Entrained I I I IGases i 4

2. High Crud i

I l(Gamma 1 Tanks (2) l I l Emitters) l 3 I l l I 1 I M l H-3 l 1x10-5

3. Woutraliser lContinuoust lcompositec l

l Tank l l 1 Gross l 1x10-' l l l Alpha l l l I I l l Q l Sr-89, l 5x10-* IcontinuousS ICompositec l Sr-90 1 I I l I I l l Fe-55 l 1x10-* 1 l I I i 00591

) 1 SQN ODCM Revision 23 J Page 112 of 146 ) Table 2.1 (Page 3 of 4) RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION i P = Completed prior to each release Q = At least once per 92 days D = At least once per 24 hours i N. A. Not Applicable M = At least once per 31 days I "The LLD is defined for the purpose of these specifications as the smallest a concentration of radioactive material in a sample that will yield a not count above system background that will be detected with 951 probability with only a $5 probability of falsely concluding that a blank observation represents a "real" signal. For a particular measure system (which may include radiochemical I separation): 4.66sb LLD = 1F" V 2.22x10' Y exp (-AAt) Wheret LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume, ob is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency as counts per disintegration, l V is the sample size in units of mass or volume, 2.22x10s is the number of disintegrations per minute per microcurie, Y is the fractions 1 radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, and At from plant effluents is the elapsed time between midpoint of sample collection and time of cottating (midpof nt). It should be recognized that the LLD is defined as an g_,qriori (before the fact) limit representing the capability o. a measurement system and not an a nesteriori (after the fact) limit for a particulate measurement. b A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a spr.cimen which is representative of the liquids released. 00591 o I

1 i SQN ODCM i Revision 23 Page 113 of 146 Table 2.1 (Page 4 of 4) RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION Prior te analyses, all samples taken for the composite shall be throughly 1 c mixed in order for the composite sample to be representative of the j effluent release. d A batch release is the discharge of liquid westes of a discrete volume. ,, Prior to sampling for analyses, each batch shall be isolated, and then thoroughly sized, by the method described in Section 2.3.2, to assure representative sampling. ] e A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release. f The principal gasmaa esittars for which the LLD specification applies exclusively are the following radionuclides Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141. Ce-144 shall also be measured with an LLD of 5x10-6 This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified ~, and reported. 8 Releases from these tanks are continuously composited during releases. With the composite sampler or the sampler flow monitor inoperable, the sampling frequency shall be changed to require representative batch saap?.go from each tank to be released to be taken prior to release and manually composite for these analyses. h Applicable only during periods of primary to secondary leakage or the r release of radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of 11x10-8 pC1/mi and allowing for background radiation during periods when primary to secondary leakage is not occurring. i 00391

l e SQN ODCM Revision 23 PaSe 114 of 146 Table 2.2 (Page 1 of 3) RADIDACTIVE LIQUID EITLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT QfERABLE ACTION 1. GROSS RADICACTIVITT MONITOR 8 PROVIDING AUTOMATIC i TERMINATION OF RELEASE j a. Liquid Radwaste Effluent Line 1 30 i b. Steam Genrrator Blowdown Effluent Line 1 31 c. Condensate Domineralizer Effluent Line 1 30 2. GROSS RAD 10ACTIVITT MONITOR 8 NOT PROVIDING AUTOMATIC i TERMINATION OF RELEASE a. Easential Raw Cooling Water Effluent Header ** 1 32 b. Turbine Building Sump Effluent Line 1 32 3. FLOW RATE MEASUREMENT DEVICE 8 a. Liquid Radweste Effluent Line 1 33 b. Condensate Deatneraliser Effluent Line 1 33 c. Steam Generator Blowdown Efiluent Line 1 33 i d. Cooling Tower Blowdown Effluent Line 1 33 4. TANK LEVEL INDICATING DEVICES a. Condensate Storage Tank 1 34 b. Steam Generator Layup Tank

• 1 34 i

5. CONTINU0US COMPOSITE SAi K TR AND SAMPLE FLOW MONITOR a. Condensate Domineralizer Regenerant Effluent Line 1 35 6 1 h

• Required whr. connected to the secondary system
  • Requires minimum of 1 Channel / Header to be operable.

00591

l SQN ODCM Revision 23 .Page 115 of 146 J i Table 2.2 (Page 2 of 3) EADICACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 1 TABLE NOTATION i ACTION 30 With the number of channels CPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a releases

a. At least two independent samples are analyzed in accordance with Section 2.3.2, and

b. At least two technically qualified members of the. Facility Staff independently verify the release rate calculations and discharge line valving; otherwise, suspend release of radioactive affluents via this i

pathway. 1 ? ACTION 31 With the number of channels OPERABLE less than required by the L Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross l radioactivity gamma at a limit of detection of at least 10-7 microcuries/ gram l

a. At least once per.12 hours when the specific activity of the secondary coolant is greater than or equal to s

0.01 microcuries/ seam DOSE EQUIVALENT I-131. L

b. At. least once per 24 hours when the specific activity of the l '

secondary coolant is less than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT I-131. ACTION 32 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this. pathway may continue provided that, at least once per 12 hours, grab samples are collected and analyzed for gross radioactivity gamma at a limit of detection of at least 10-7 aicrocuries/al. ACTION 33 With the number of channels OPERABLE less than required by the-i Minimum Channels OPERABLE requirement, effluent releases via this s l. pathway may continued provided the flow rate is estimated at least once per 4 hours during cetual releases. Pump curves may be used to estimate flow. ACTION 34 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this j tank may continued provided the tank liquid level is estimated during all liquid additions to the tank. 00591 l k e-,--e - -, - -..-e m... w. ,_--,-___-e---

i SQN ODCM Revision 23 Page 116 of 146 Table 2.2 (Page 3 of 3) RADICACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION ACTION 35 With the number of channels OPERABLE less than required by the Minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided representative batch samples of each tank to be released are taken prior to release and composited for analysis according to Table 2.1, footnote 3 s l' 00591

I l l. i SQN ODCM Revision 23 Page 117 of 146 Table 2.3 (Page 1 of 2) RADICACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION i SURVEILLANCE REQUIREMENTS l CHANNEL CHANNEL SOURCE CNANNEL FUNCTIONAL INSTRUMENT CHECK., CHECK. CALIBRATION TEST 1. GROSS BETA OR GAMA RADI0 ACTIVITY t MONIT0k8 PROVIDING ALARM AND 'AUTOM TIC TERMINATION OF RELEASE A 1 a. Liquid Radweste Effluente Line D P R(3) Q(1) b. Steam Generator Blowdown Effluent Line D M R(3) Q(5) c. Condensate Desineraliser Effluent Line D M R(3) Q(5) l 2. GR088 SETA OR GAMA RADI0 ACTIVITY i MONITORS PROVIDING ALARM BUT NOT PPOVIDING AUTOMATIC TERMINATION OF RELEASE a. Essential Raw Cooling Water Effluent Line D M R(3) Q(2) b. Turbine Building Susp Effluent Line D M R(3) Q(2) 3. FLOW RATE MEASUREMENT DEVICE 8 l a. Liquid Radweste Eifivent Line D(4) N.A. R Q l b. Steam Generator Blowdown Effluent Line D(4) N.A. R Q c. Condensate Desineraliser Effluent Line D(4) N.A. R Q l d. Cooling Tower Blowdown l 3ffluent Line D(4) N.A. R Q l 4. TANK LEVEL INDICATING DEVICES a. Condensate Storage Tank D* N.A. R Q b. Steam Generator Layup !lank Da N.A. R N.A. 5. CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR ^ a. Condensate Deatneraliser Regenerant Effluent Line P N.A. R N.A. 00591 l l e ---e-a-4 a- - w--- e=- w e- ---a -m

E ] 1 l SQN ODCM Revision 23 ) Page 121 of 146 Table 3.1 (Page 1 of 3) 'l MINIMUM REQUIRED RADIOLOGICAL T.NVIR0letENTAL MONITORING PROGRAM j Rxposure Pathway Number of Samples and/or and Sampling and Type and Trequency ' Samole S =mie Locationa** Collection Freauenev of Analvata

1. AIRBORNE l

t Radioiodine and minimum of 5 Continuous operation Radiciodine canisters Particulates locations of sampler with Analyse at least once sample collection as per 7 days for I-131. required by dust l loading but at least Particula:e sampler [ once per 7 days. Analyse for gross beta radioactivity 1 24 hours following filter change. Perform samma isotopic analysis on t each sample when gross beta activity 1s > J0 times the yearly mean of control samples. Perfora sanna isotopic analysis on composite (by l location) sample at-least-once per 92 days.

2. DIRECT 35 to 40 At least once per Gamma Dose. At least RADIATION locations with 92 days.

once per 92 days. 1 2 dosimeters for continuously measuring and t recording dose rate at each location.

• • Sample locations are given in Table 3.4.

i 00591

SQN ODCM Revision 23 Page 122 of 146 Table 3.1 (Page 2 of 3) MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and sampling and Type and Frequency Sample Bannie Locationa** Collection Frecuenev of Analvain

3. WATERBORNE

s. Surface 3 locations Composite

• sample Gamma isotopic collected over a analysis of.each period of 1 31 days. composite sample.

Tritium analysis of composite sample at least once per 92 days. .i

b. Ground 2 locations At least once per Gamma isotopic and j

92 days. tritium analyses of each sample. j

c. Drinking Minimum of 1 Composite

• sample Cross beta and samma L

location collected over a isotopic analysis of period of 1 31 days, each composite sample, j 2 locations Monthly single Tritium analysis of aample. eompoeite eample at least once per 92 days. e

d. Sediment Minimum of 2 At least once per Samma isotopic from locations.

184 days analysis Shoreline c4 each sample, locations

• Composite samples shall be collected by collecting an aliquot at intervals not ascoeding 2 hours.

L

• • Sample locations are given In Table 3.4.

h l l 00591 l l l l'

I i l i SQN ODCM Revision 23 Page 123 of 146 Table 3.1 (Page 3 of 3) MINIMUM REQUIRID RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i Exposure Pathway Number of Samples and/or and Sampling and Type and Frequency l 'Jancie Samnia Locationa** Collection Frecuenev of Analvain

4. INGESTION

a. Milk 3 locations At least once per 15 Gamma isotopic and Samples of broad days when animals 1-131 analysis leaf vegetation are on paature; of each sample, at offsite at least once per' location of 31 days at other highest D/Q if times.

milk sample is not available. i

b. Fish and 3 locations one sample in Gamma isotopic Invertebrates season, or at least analysis on edible once per 184 days portions.

if not seasonal. One sample of each of the following species: 1. Channel Catfish 2. White Crapple 3. Smallmouth Buffalo

c. Food Products Minimum of 2 At time of harvest.

Gamma isotopic locations One sample of each analysis on edible of the following portion. classes of food products. 1. Lettuce and/or cabbage 2. Corn 3. Beans 4. Tomatoes

• • Sample locations are given in Table 3.4 h

00591 _,.,n, ...-,,---n, ---.....-n -,n v.-,.ne. ~, -

SQN ODCM ) Revision 23 Page 124 of 146 1 Table 3.2 (Page 1 of 2) MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b i Airborne Particulate l. Water or Cases Fish N11k Food Products Sediment Analvais (nci/L) (DC1/m8),_ (nC1/Ka. vet) (nci/L) (nci/Km.wat) foci /Km.drvi i gross beta 4 1x10-a M.A. N.A N.A. N.A. E-3 2000* N.A N.A N.A N.A. N.A. + t Ph-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. N.A. N.A. l Zn-65 30 N.A. 260 N.A. N.A. N.A. 2r-95 30 N.A. N.A. N.A. N.A. N.A. i Nb-95 15 N.A. N.A. N.A. N.A. N.A. 1-131 1** 7x10-a N.A. 1 60 N.A. Co-134 15 5x10-8 130 15 60 150 co-137 18 6x10-8 150 18 80 180 Ba-140 60 N.A. N.A. 60 N.A. N.A. La-140 15 N.A. N.A. 15 N.A. N.A.

• If no drinking water pathway exists, a value of 3000 pCi/L-may be used.
  • If no drinking water pathway exists, a value of 15 pCi/L may be used.

l' 00591 - - - - - - - - - - - - - - - - - - - + -

L-i SQN ODCM Revision 23 page 125 of 146 l ) Table 3.2 (page 2 of 2) MARINUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b TABLE NOTATION a The LLD is defined, for the purpose of these specifications, as the smallest concentration of radioactive material in a sample that will yield a not count above system background that will be detected with 95% probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. l For a particular measurement system (which may include radiochemical separation): 4.66sb E V 2.22 Y exp(-14t) Whore: LLD is the "a priori" lower limit of detection as defined above in picoeurie per unit mass or volume, ob is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picoeurie. Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting. 3 It should be recognised that the LLD is defined as an a orlori (before the fact) limit representing the capability of a measurement system and not an a sosteriori (after the fact) limit for a particular measurement. Analysis will be perforined in such a manner that the stated LLDs will be achieved under routine conditions. I b Other peaks which are measurable and identifiable, together with the radionuclides in Table 3.2, shall be identified and reported. l l l l 00591 t

i l SQN ODCM Revision 23 'l Page 126 of 146 i Table 3.3 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMP{ Airborne Particulate Water or gases. Fish Milk Food Products Analvais (oci/L) foci /m81 foci /h. wati LDCi/L) (nci/ h '. wat ). i N-3 2 x 104(a) N.A N.A N.A. N.A. Mn-54 1 x 108 N.A. 3 x 104 N.A. N.A. i Fe-59 4 x 108 N.A. 1 x 108 N.A. N.A. Co-58 1 x 108 N.A. 3 x 108 N.A. N.A. [ Co-60 3 x 10: N.A. l'x 108 N.A. N.A. 2n-65 3 2 los N.A. 2 x 108 N.A. N.A. ~, 2r-Nb-95 4 x 108 N.A. N.A. N.A. N.A. I-131 2(b) 0.9 N.A. 3 1 x 108 Cs-134 30 10 1 x 108 60 1 x 108 Co-137 50 20 2 x los 70 2 x 108 Ba-La-140 2 x 102 N.A. N.A. 3 x 10a N.A. P (a). For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/L may be used. (b) If no drinking water pathway exists, a value of 20 pCi/L may be used. r L L 00591 t C ^ ^ ~ ' ^ ~ ~ ' - - - - ~ ~

SQN ODCM Revision 23 Page 127 of 146 j Table 3.4 (Sheet 1 of 4) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l Exposure Pathway Sampling and Type and Frequency j and/or Samnie Sammle Locationa* Collection Freauenev of Analvais i AIRBORNE Particulates 4 samples from loca-Continuous sampler Analyse for gross I tions (in different operation with beta radioactivity sectors) at or near sample collection 1 24 hours follow-the site boundary once per 7 days ing filter change. 1 (LM-2,3,4,and 5) (more frequently Perform samma iso-if required by dust topic analysis on 4 samples from com-loading) each sample if munities approx-gross beta > 10 1 instely 6-10 miles times yearly mean distance from the of control sample, plant. (PM-2,3,8,and 9) Composite at least l-once per 31 days i (by location for 4 samples from control locations greater than ) 10 miles from the plant (RM-1,2,3,and 4) Radiciodine Samples from same Continuous sampler I-331 at least location as air operation with fil-once per 7 days particulates. ter collection once per 7 days i Soil Samples from same Once per year Gamma scan, Sr-89, locations as air Sr-90 once per particulates 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 j the 16 sectors.- 2 or more dosimeters placed at stations located >5 miles from the plant in each of the 16 sectors

• Sample locations are listed in Tables 3.5 and 3.6 and shown on Figures 3.1, 3.2 and 3.3 00591 I

{T, I SQN ODCM Revision 23 Page 128 of 146 Table 3.4 (Sheet 2 of 4) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Frequency and/o_r E== ale E==le Locationa* Collection Franuanev of Analvain DIRECT 2 or more dosimeters RADIATION in at least 8 additional (continued) locations of special I interest. t WATER 80RNE Surface TRM 497.0 Collected by auto-Cassa scan of each TRM 483.4 matic sequential-composite sample. i TRM 473.2 type sampler ** with Composite for N-3 composite samples analysis at least collected at least once per 92 days i once per 31 days i Ground 1 sample adjacent to At least once per Gross beta and l plant (location W-6) 92 days samma scan, 8r-89 3r-90 and M-3 an-1 sample from ground analysis at least [ water source up-once per 92 days i gradient Drinking 1 sample at the first Collected by auto-Gross beta and potable surface water natic sequential samma scan of each supply downstress type sampler ** with composite sample. f from the plant composite sample Composite for B-3 l (TRA 473.0) collected at least 8r-89, 3r-90 at 3 once per 31 days least once per 1 sample at the next Grab sample once 2 downstreaa potable per 31 days surface water sup-f' pliers (greater th '. t 10 miles downstream) (TRM 470.5 and 465.3) 2 samples at control 8amples collected by locations (TRM 497.0 automatic sequential i and 503.8)*** type sampler with com-posite sample collected at least once per 31 days.

• Sample locations are listed in Tables 3.5 and 3.6 and shown on Figures 3.1, 3.1 and 3.3
  • Samples shall be collected by collecting an aliquot at intervale not exceeding 2 hours.
    • The surface water sample collected at TRM 497.0 is considered a control for the raw drinking water sample.

00591

• --v

,w. . _.-.-y a,,.--et-~ eea-4 -

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i i SQN ODCM i Revision 23 Page 129 of 146 Table 3.4 (Sheet 3 of 4) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM s Exposure Pathway Sampling and Type and Frequency and/or E== ale Samela Locationa* Collection Frecuenev of Analvaia WATERBORNE ^"-' (continued) Sediment TRN 496.5, TRM 483.4 At least once per Gamma scan of each TRN 480.8, TkN 472.8 184 days sample. Shoreline TRN 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. 8r-89 dicated by the cow St-90 once per i census where doses are quarter calculated to be highest. If samples are not avail-i able from a milk animal location, doses to that i area vill be estimated by projecting the doses from l concentrations detected in milk from other sectors or samples of vegetation will be taken monthly where i milk is not available l (Table 3.1, 4d) At least 1 sample from a control location Fish 1 sample each from At least once per Gamma scan on Nickajack, Chicka-184 days. One sam-edible portion mauga, and Watts ple of each of the j Bar Reservoirs following species - Channel Catfish Crapple Smallmouth Buffalo L l

• Sample locations are listed in Tables 3.5 and 3.6 and shown on Figures 3.1, 3.2 and 3.3 l

00591

I' l f SQN ODCM 4 Revisicn 23 Page 130 of 146 I 4 of 4) Table 3.4 (Sheet RING PROGRAM RADIOLOGICAL ENVIRONMENTAL MONITO Type and Trequency_ Sampling and of Analvata Collection Treauenev _ __ [ Exposure Pathway 5 = ale Locationa* __=ad/or A--ale Gamma scan on INGESTION At least once per edible portion I

• • 184 days l

(continued) 2 samples. downstream (Asiatic Class) from plant discharge Invertebrates

1. sample upstream l

from the plant ** Gamma scan on At least once per edible portion 1 sample each of 365 days at time of The types Food principal food harvest. Products products artwn at of foods available for sampling vill vary. private gardens and/or farms in the Following is a list of l innsdiate vicinity typical foods which may be available of the plant Cabbage and/or Lettuce Corn Green Beans Potatoes Tomatoes 1-131 and somma At least once per scan at least once Samples from farms 31 days per 31 days. Vegetation producing milk St-89, 8r-90 anal-but not providing ysis at least once a milk sample per 92 days. (Fare Es) 1 3 5 and 3 6 and shown on Figures 3.,

• Sample locations are listed in TablesLocations depend on availab
  • No permanent stations established.

3.2 and 3.3 class. 00591

'MO SQN ODCM Revision 23 Page 131 of 146 Table 3.5 (1 of 2) ElfVIRONMEh.d. RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map Approximate Indicator (I) Location Distance or Samples Rumter a Station Sector (Miles) Control (C) CollectedD 2 W2 N 0.8 I AP, CF, S 3 W3 SSW 1.2 I AP, CF, S 4 LM-4 NE 1.5 I AP, CF, 5 5 W5 NNE 1.8 I AP, CF, S 7 PM-2 SW 3.8 I AP, CF, S 8 %3 W 5.6 I AP, CF, S 9 PM-8 SSW 8.7 I AP, CF, S 10 N9 WSW 2.6 I AP, CF, S 11 RM-1 SW 16.7 C AP, CF, S 12 E2 NNE 17.8 C AP, CF, S 13 EM-3 RSE 11.3 0 AP, CF, S 14 RM-4 WNW 18.9 C AP, CF, S 15 Farm B R3 43.0 C M 16 Farm C NE 16.0 C M 17 Farm 8 NNE 12.0 C M 18 Fara J WNW 1.1 I M 19 Farm BW NW 1.2 I M, Wc 20 Fara BM N 2.6 I V 24 Well No. 6 NNE 0.15 I W 31 TRMd 473.0 11.5C I PW (C. F. Industries) 14.08 I PW 32 TBM 470.5 (R. I, DuPont) 19.2e g py 33 TRM 465.3 (Chattanooga) 12.58 Cf SW 94 TRM 497.0 19.3e C PW 35 TRM 503.8 (Dayton) 12.0e C SD 36 TRM 496.5 0.5e C SS 37 TRN 485.0 1.le I SD, SW 38 TRM 483.4 3.7e g gn 39 TRM 480.8 40 TRM 477.0 7.5e I gg 41 TRM 473.2 11.3e I gy 42 TRM 472.8 11.7e I SD 44 TRM 478.8 6.58 I SS F G 00591 1

. _ _ _ _ _ ~_ l SQN ODCM Revision 23 l Pa8e 132 of 146 ) Table 3.5 (2 of 2) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map. Approximate Indicator.(I). JD Location Distance or Samples Number a Station Sector (Miles) Control (C) Collectedb 45 TRM 425-471' I F (Nickajack) ,.:, v , Reservoir) I ^ '46-TRM 471-530 I F, CL 'I (Chickamauga Reservoir) 47 TRM 530-602 C F-i (Watts Bar Reservoir) 'l 48 Fara M . NE 4.2 I M r ( T

• See-figures 3.1, 3.2, and 3.3 b Sample Coden l:

l AP's Air particulate filter l [' -CF = Charcoal' filter-l CL = Claam F = Fish L M = Milk I FW = Public water R = Rainwater 8 = Soil L SD = 8ediment i 85 e Shoreline sediment l. SW = Surface water l -V = Vegetation-I~ W- = Well water' d t, e A control for well water.. d TRM = Tennessee River Mile. l. l e Distance from plant dischar8e (TRM 484.5) f Surface water sample also used as a control for public water. I 00591 l' t s i @~

I c I SQN ODCM Revision 23 Pa8e 133 of 146 Table 3.6 (1 of 2) THERM 0 LUMINESCENT DOSIMETRY LOCATIONS Map . Approximate Onsite (On)a-i Location Distance or ) ni-he r Station Sector (Miles) Offaite (off) 3 88W-1A SSW 1.2 On 4 E-1A NE 1.5 On 5 NNE-1 NNE 1.8 On ( 7 8W-2 SW 3.8~ Off i 8 W-3 W 5.6 Off 9 88W-3 SSW 8.7 off 10 W8W-2A-WSW 2.6 Off. -11 SW-3 SW 16.7 Off 12 NNE-4 NNE 17.4 Off-p 13 ESE-3 ESE 11.3 Off 14 WNW-3L WNW 18.9 Off 5 49 N-1 N 0.6 On 50-N-2' N 2.1 0ff 51 -N-3 N 5.2 Off 52 N-4 N 10.0 0ff 53 NME-2 ME -4.5 Off l-54 NNE-3 NR 12.1 0ff l 55-NE-1 'NE 2.4 Off 56 NE-2 NE 4.1 Off l-57 EM-1 ENE 0.4-On l 58 ENE-2 ENE .5.1 off L 59 E-1 E 1.2 On 60 E-2 I 5.2 Off 61: ESE-A E8E 0.4-On 62-385-1 E8E 1.2 On 63 ESE-2 ESE 4.9 Off' 64 88-A 8E 0.4-On 65 85-E SE 0.4 On-I l-66 SE-1 SE 1.4 On ' L-67 88-2 SE 1.9 On I L 68 SE-4 8.E 5.2 Off L 69 885-1 SSE-1.6

On N

70 88R-2 SSE 4.6' Off 71 e~ S 1.5 - On 72 8-2 S 4.7 Off W 73 SSW-1 SSW 0.6 Os 74 88W-2 88W 4.0 Off 75 SW-1 SW 0.9 On 76 W8W-1 -WSW 0.9 On-3 1 00591 6=. w --. -p.

l P; != SQN ODCM 1 F Revision 23 Page 134 of 146~ Table 3.6 (2 of 2) TERM 0 LUMINESCENT D0SIMETRY LOCATIONS ~ r Map Approximate; Onsite (On)a l Location Distance or 3'i Ib=he r station Sector (Miles) Offsite (Off 77 WSW-2 WSW 2.5 Off. 78 W8W-3 WSW 5.7 ~0ff' 79 W8W-4 WSW 7.8 Off 80 W8W-5 WSW 10.1 off-i 41 W-l ' W 0,8 On 82 W-2 W 4.3 Off 83 WNW-1 WNW 0.4 On 5 84 ' WNW-2 WNW 5.3 Off 85 W-1 NW 0.4 00 86 NW-2 NW 5.2 Off 87-NNW-1 NNW 0.6 On l 88 NNW-2 NNW 1.7 On 49 NRW-3 NNW 5.3 Off i 'I i' P 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 l: plant.. l '.. i :- 00591 L 1 I

-- ~. ___ / SQN ODCM Revision 23 l Page 135 of 146 Figure 1.1. a' GASEOUS ETTLUENT RELEASE POINTS . Condenser Vacuum Exhaust! Shield Building Vent (one per unit) (one per unit) l j j - (outelde *) l 1,2-Ru-So-100 CI SUPPLY () 1,2-RE-to-119.99 iwAsTtcAS l. 5""*E cowreasur l TMS 4 PURot NCoRE MST. l L CONDENSER Roou puRot j o-Re-,o-ii c3 ca l.2-Ru-no-is0.1 st i ............................... 3 5 p 3 p l 'ServiceBuildingVentl j g umum smo, r i 4 L 1 L i oAS m mtwr asRoswa miru(AscrS) on$ w rurwr () 0-"E-80-132 C j SYmu (car $) Auxiliary Building Vent m now L ,! (outside *) .j L t "00" l l SUPPLY l. - l [] 0-RE-to-101 + CHEu tAs j i l courAmutur j mium wwr l suiLDWo + war SHOP ANNUWS VACUUu L l PRENNo MS HEu.TH ( ANNULUS + PHYSICS LAS (2 PER UNir) i l egodem11 l 00591 h i o l o m-- ,e

R i L SQN ODCM Revision'23 Page 136'of 146 l Figure 1.2 -AUXILIARY AND SHIELD BUILDING VENTS (DETAIL) l Shield y Building Vent Cl 1,2-RW-90-t oo ~ "NQt Roorrg g 4 Asea I sera ens t C

== 4-10 ' Containment centehenent MN 4 h Purge Exhouet r' 7' Pwee suppsy l, 1 > ?; l gg C IBureesi hM [; FIters Annulus (0.50 Inshee of water voeuum) I b t.l-ma - M ,e I EGTS containment (eenerete)g / WDOTe f Shleid (MN 'i Aus111ery i m SW11 ding t Vent L =emme wasuwn J (.' IJ prenme rene ( l; 1 I I en ens l 4 oweess + A8GT3 ' o-RW-90-101[] - en e Aux.ld.ory+

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a ,t. . i 'b, yrb r 1 SQN ODCM j Revision 23-s b Page 138 of 146 Figure 1,4 GASEOUS RADWASTE TREATMENT SYSTEM 1, t. CVCS VCT . yng, Y eVCS vCT < s Wdt 2 i -n i' CVCS NT q' L"CS RCOT 1 UnR 1 j s 7 TfCS RCOT C Unk 2 / ~} (: Woote Gee : t [ I CeTv :_::- Posiege Vent 'f (typleol of 2) CVCS M &2 't - Units 142/ 7' c I ' CVCS NT E / d b. l ma t - ri 1 P 4 d b 7% Westo Gee Weste Gee Woote Gee Deoey Tonk Decoy Tonk Desey Tonk E, W 8End) $Wes#N) OssAssed) Oposse se 7) l v v v -1 00591 i :.- 4 e e m = m

.}=' 1 SQN ODCM l Revision 23 Page 139 of 146 ] t Figure 1.5 PLVME DEPLETION EFFECT FOP.GROLND LEVEL RELEASES. (All Stability Classes) y 1 ~ .3 + ) .1 ,= .9 g N s .8 's g t. u.,. I .5 N g %y 4 I,3 .2. .1 ..k. L 10 ib0 200-PLUhE TRAVD. DISTANCE (10LOWEmtS) j o 00591 j l

v; 4: >i SQN 0DCM Revision 23 Page 140 of 146 Figure 1.6 VERTICAL STANQARD DEVIATION OF MATERIAL IN A PLUME 1000 = V I I A I J I I / I / / l / / r r r r s A } , A 2 f p j r 8 f / / / / / f / f A A-A ,f 100 ) 1 1 7 7 E J / . sf' _meus J f , V , V } J J V f . f a.$ / f /" u ) f ) / -) ^ n f / / / cff f / n m v / / I r f /,f f y / / / v f f A , F 1 \\ /, r 3 2 r r l l -l f } l A / / . / l '/ / l[ f f / f 0.1 1.0 10 100 PLUME TRAVEL DISTANCE (K;LOMETERS) J o Vertieel Standard Davistion of Maeorial in a Plume (Letters denots Pseguill Stability Class) / 00591 (is r ^ ~*

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s. SQN ODCM. Revision ~23 ~ Page 141 of.146' Figure 1.7 -RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES (All Stability Classes) e i i 3-f f 1E-3 '^ u 2 1E m ^E + k " A N N W s g i % g-g L 1E-s-L 1 s l g L ' s 1 m 'k , E_.. E p l' '1E-7 .d i 10-100,200 PLUME TRAVEL DISTANCE (KILOMETERS) ' 4. 00591 1 l

s 3- ~ k. i Condensate Demineralizer'i Steam Generator Slowdown j Turbine Building-Systee j hit i h it 2' i ' Sump Crud W em j# 3 S Sjt SfC S/C S/C l 7 edt 1 4 _j 1 2 3 4 f1 y2 f3 J4 l Turtnin. BuBsAng ~f a. -e HIgh Crud j Tener 2 Y .e e-o.es ( ) (anoon o j 1 f -} r e. l l***"l I

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.l ny + i SQN ODCM Revision 23 { Page 143 of 146 j Figure 2.2 1.IQUID RADWASTE SYSTEM Reacter Building Auvillery Bullding j Dreine Droins L I 4 3 Tritisted Drein ~ L Causator Tonk 7 l; Floor Drain ..v Collester Tank m l: (oosesional use) - L g g enemien or*. 20 g,m Tank A I'* I L: venser nos.eete Dominerosser Weste Ewepareter i'

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Het Shower l I { { (enke A er 3 - 20 g,. (800 gel) Weste Olethlete l-Tanks lc Cook Desen (8800gol) ? [ Wonitor Tank CeNester Tank (22000 gel) (15000 gel) L 128 gym 125 gem 1 I (routine roleses path) I (eeeee:ene' rwoose peth) ^ y 0-RW-90-122 ll 1 fTO COOLING TOWER BLOWDOWN 00591

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_.. ~. / SQN ODCM. Revision 23. Page 144 of 146 Figure 3.1 Environmental Radiological Sampling Locationsf Within 1 Mile of Plant 'l ? 348.75 N' ' 11.25 NNW. NNE ~ 326,25 33.75'

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NW_. 2 7 NE 3o3.75-4 f .c o.2 5 \\ '87{

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3 f l WNW \\,,# ENE 85 K.* ,e. / e 2'81.25 N M v * .) 78.75 EQUOYAH W-NUCLEAR - E _: e-PLANT- \\ju l -258.75 - 101.25) 5 s 76 4 3 / I I l ESE WSW y. ? [5 '**'#5 236.25' \\/ 73 ~ 966 SW-v# gsS'E# SE i 146.25 213.75 SSW [ SSE i '7' 191.25 S scale 0 Mlle 1 e 4 Jn i

3- -3 --v - ~ 'w l 50:1 ODCM .1 [< Pavision 23 4 it Page 145'of 146 Figure 3.2 Environmental Radiological Sampling Locations L From 1 to 5 Miles From The Plant \\ 7 s i l s4s.7s N 11.as NNW Mr NNE j j# 3.,j n.as u.7s. NW .NE-l- s03.7s R s8.2 s. 48 56 WNW 8 i L 65 ENE-1 s ~- ast.as 4 j@ g re.7s 83 1 po$ @ g d. l* -- 1: \\ q 1 W- -E-10 2 b; ass.7s 77 o d6-101.2s i 6g-73 WSW-ge - 63 ESE' 5 12.... SW SE 213.7s 14e.2s SSW SSE i g 1e 1.25 g 1es.7s scALs amm--mmmmmmmmmm. 0 1 2 ~ MILES l' b [ iji )@ q,

l s. is ~ * ' SQN ODCM- ., g ' Revision 23 Page 146 of 246-i; Figure 3.3' Environmental Radiological Sampling Locations-1 Greater Than '5 Miles.From The Plant i. l y+' asa.7s ? 11.as '""=E

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m. >ti C 326.28 '83.78 i g }h I ww l '? I. f. 308.75 ,g ag,gg. lrl.. a t .www 84v7 ENE 12 I' 'i R 881 RS yg,yg [ p t4 2 owan t gg y-w- me as%ames vetano .)_ L 'i . 384,7 r d 101.28: g' f ! f. I' CseATTAN004A gaggagp0RT I wow / ses / see.as s x La#AYSTTE I g Ow Y gg t i-213.75 144.25 ? 88W seg lei.as 1se.7s SCALE O 5 - to 6 4~MS estas j j, f + . L. --,5 x-

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