Text

Annual Radioactive Effluent Release Rept for Jan-Dec 1994
	ML20087H495
Person / Time
Site:	Sequoyah
Issue date:	12/31/1994
From:	Shell R; TENNESSEE VALLEY AUTHORITY
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9505030181
	Download: ML20087H495 (240)
	v • d • e

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Tennessee Valley Authonty Post Oftce Box 2CKK) Sory Daisy Tennessee 37379 ;

April 26,1995 ,

i U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Mah of ) Docket Nos. 50-327 Tennes!ae Valley Authority ) 50-328 i

SEQUOYAH NUCLEAR PLANT (SON) - 1994 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR)

Enclosed is the ARERR fcr the period of January 1 to December 31,1994.

This report is being submitted in accordance with SON Technical Specification (TS) 6.9.1.8.

Enclosure 1 contains SQN's ARERR. Enclosure 2 provides the Radiological Impact Assessment Report for the period of January 1 to December 31,1994.

Enclosure 3 provides an entire copy of SON's Offsite Dose Calculation Manual (ODCM), which includes Revisions 32, 33, 34, and 35. These ODCM revisions occurred during this 1994 reporting period and are being provided in accordance with SON TS 6.14.

Please direct questior.s concerning this issue to D. V. Goodin at (615) 843-7734.

Sincerely, R. H. Shell Manager SON Site Licensing Enclosures //

cc: See page 2 "k I

9505030181 941231 PDR ADOCK 05000327 R PDR

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U.S. Nuclear Regulatory Commission ;

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(. April 26,1995 l cc (Enclosures): !

Mr. D. E. LaBarge, Project Manager !

Nuclear Regulatory Commission l One White Flint, North l 11555 Rockville Pike i Rockville, Maryland 20852-2739 i i

NRC Resident inspector ,

Sequoyah Nuclear Plant i 2600 Igou Ferry Road l Soddy-Daisy, Tennessee 37379-3624 Regional Administrator ;

U.S. Nuclear Regulatory Commission i Region il !

101 Marietta Street, NW, Suite 2900 '

Atlanta, Georgia 30323-2711 l l

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ENCLOSURE 1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD OF JANUARY 1 TO DECEMBER 31,1994 (S58 950414 801) l 4

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1994

1. REGULATORY LIMITS ,

i A. Gaseous Effluents

1. Dose rates due to radioactivity released in gaseous effluents from )

the site to areas at and beyond the unrestricted area boundary shall be limited to the folltwing:

a. Noble gases:- Less than or equal to 500 mrem / year to the total f body. l

- Less than or equal to 3000 mrem / year to the skin. j i

b. Iodine-131, iodine-133, tritium, and all radionuclides in >

particulate form with half-lives greater than 8 days: ;

- Less than or equal to 1500 mrem / year to any ,

organ. j

2. Air dose due to noble gases released in gaseous effluents to areas .

at and beyond the unrestricted area boundary shall be limited to !

the following: .

a. Less than or equal 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation during any calendar quarter. i

b. Less than or equal to 10 mrad for gamma radiation and less ,

than or equal to 20 mrad for beta radittion during any calendar year, j

3. Dose to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released to areas at and beyond the unrestricted area boundary shall be limited to the following:

a. Less than or equal to 7.5 mrem to any organ during any ,

calendar quarter.

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b. Less than or equal to 15 mrem to any organ during any calendar l

year.

B. Liquid Effluents

1. The annual average concentration of radioactivity released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in Title 10 of the Code of Federal Regulations, Part 20 (Standards for Protection Against Radiation),

Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 microcuries/ milliliter (pCi/ml) total activity. l PLO20201/5800/2 l

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT ,

SUPPLEMENTAL INFORMATION 1994

2. The dose or dose commitment to a member of the public from radioactivity in liquid effluents released to unrestricted areas shall be limited to:

a. Less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ during any calendar quarter.

b. Less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ during any calendar year.

2. EFFLUENT CONCENTRATION LIMITS A. Liquids

l. The Effluent Concentration Limits (ECL) for liquids are those listed in 10 CFR 20, Appendix B, Table 2, Column 2. For dissolved and entrained gases the ECL of 2.0E-04 pCi/ml is applied. This ECL is based on the Xe-135 concentration in air (submersion dose) converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP), .

Publication 2. l l

B. Gaseous I

1. The maximum permissible dose rates for gaseous releases are defined in plant Offsite Dose Calculation Manual (ODCM),

a. Noble gas dose rate at the unrestricted area boundary:

- Less than or equal to 500 mrem / year to the total body,

- Less than or equal to 3000 mrem / year to skin.

b. Iodine-131, iodine-133, tritium, and particulates with half-lives greater than eight days dose rate at the l unrestricted area boundary:

- Less than or equal to 1500 mrem / year to cny organ.

3. AVERAGE ENERGY l Sequoyah's ODCM limits the dose equivalent rates due to the release of I noble gases to less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the skin. Therefore, the average beta and gamma energies (E) for gaseous effluents as described in Regulatory Guide 1.21, " Measuring, Evaluation, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," are not applicable.

These values are used as applicable limits for liquid and gaseous effluents.

i EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION

.1121

4. Measurements and Approximations of Total Radioactivity NOTE: Every effort is made to ensure that effluent releases from Sequoyah are conducted such that all Offsite Dose Calculation Manual (ODCM) Lower Limit of Detection (LLD) values are met.

Whenever an analysis does not identify a radioisotope, a "0.00E-01 Ci" is recorded for the release. This does not necessarily mean that no activity was released for that particular radionuclide, but that the concentration was below the ODCM and analysis LLD.

Refer to Tables A and B for estimates of these typical LLD values,

a. Fission and Activation Gases Airborne effluent gaseous activity is continuously monitored and recorded. Additional grab samples from the shield building, auxiliary building, service building, and condenser vacuum exhausts are taken and analyzed at least monthly to determine the quantity of noble gas activity releesed for the month based on the average vent flowrates '

recorded for the sample period. Also, noble gas samples are collected and evaluated for the shield and auxiliary buildings following startup, shutdown, or rated thermal power change exceeding 15 percent within one hour (sampling only required if dose equivalent I-131 concentration in the primary coolant or the noble gas activity monitor shows that the containment activity has increased more than a factor of 3).

The quantity of noble gases released through the shield and auxiliary building exhausts due to purging or venting of containment and releases of waste gas decay tanks are also determined.

The total noble gas activity released for the month is then determined by summing all of the activity released from each vent for all ;

sampling periods.

b. Iodines and Particulates Iodine and particulate activity is continuously sampled. Charcoal and particulate samples are taken from the shield and auxiliary building ,

exhausts and analyzed at least weekly to determine the total activity l released from the plant based on the average vent flowrates recorded l for sampling period.

Also, particulate and charcoal samples are taken from the auxiliary and shield building exhausts once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for 2 days following startup, shutdown, or a rated thermal power change exceeding 15 percent within one hour. The quantity of iodine and particulate released from each vent during each sampling period is then determined using the average vent flowrates recorded for the sampling period and activity concentration.

The 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 exhausts for all sampling periods.

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1994

4. Measurements and Approximation of Total Radioactivity (continued)

c. Liquid Effluents Batch (Radwaste and during periods of primary to secondary leakage, condensate regenerants to cooling tower blowdown) l Total gamma isotopic activity concentrations are determined on each batch of liquid effluent prior to release. The total activity 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 ot* each batch discharged during the month.

Continuous Releases and Periodic Continuous Releases (Condensate regenerants, turbine building sump and steam generator blowdown)

Total gamma isotopic activity concentration is determined daily on a composite sample from the condensate system and turbine building sump and weekly for steam generator blowdown. The total activity 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 the month.

5. Batch Value Units 1st 2nd Half Half

a. Liquid (Radwaste only)

1. Number of releases 167 168 Each

2. Total time period of releases 25,267 22,823 Minutes

3. Maximum time period of release 323 180 Minutes

4. Average time period of releases 151 136 Minutes

5. Minimum time period for release 67 74 Minutes

6. Average dilution stream flow during 64,287 37,792 CFS release periods cubic feet /second (CFS)

b. Gaseous (Batches only, containment purges, and waste decay tanks)

1. Number of releason 3 8 Each

2. Total time perlud of releases 563 12,259 Minutes

3. Maximum time period for release 340 10,470 Minutes

4. Average time period for releases 188 1,532 Minutes

5. Minimum time period for release 28 20 Minutes

! EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 191%

6. Abnormal P.eleases Value paita 1st 2nd Half Half

a. Liquid Number of Releases 0 0 i

Total Activity Released. 0.00E-01 0.00E-01 Ci

b. Gaseous Number of Releases 0 0 Total Activity Released 0.00E-01 0.00E-01 Ci

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1914 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1st _and_ 3rd 4th A. Fission and Activation Unit Otr Otr Otr Otr % Error Products

1. Total Released Curies 1.93E-01 5.02E-01 8.28E-01 4.80E-01 1.8E+01

2. Average Diluted Conc.

During Period of All Identified Isotopes pCi/ml 5.71E-07 9.59E-07 1.89E-06 1.46E-06

3. Percent of Applicable Limit (IECL11) % 1.11E+01 1.74E+01 2.60E+01 1.53E+01 NOTE: Percent of applicable limit is based on identified isotope concentration after dilution, related to their appropriate ECL concentration and sum of all the isotope fractions compared to 1.0.

B. Tritium

1. Total Released Curies 8.64E+01 2.40E+02 1.21E+02 1.54E+02 il.8E+01

2. Average Diluted pCi/ml 2.56E-04 4.59E-04 2.77E-04 4.69E-04 Conc. During Period

3. Percent of Applicable Limit (1.0E-03 pCi/ml) % 2.56E+01 4.59E+01 2.77E+01 4.69E+01 C. Dissolved and Entrained Cases

1. Total Released Curies 8.31E-03 2.58E-02 7.64E-02 7.38E-03 13.9E+01

2. Average Diluted pCi/ml 2.46E-08 4.95E-08 1.75E-07 2.25E-08 Conc. During Period

3. Percent of Applicable Limit (2.0E-04 pCi/ml) % 1.23E-02 2.47E-02 8.74E-02 1.13E-02 D. Gross Alpha Radioactivity

1. Total Released Curies 0.00E-01 0.00E-01 0.00E-01 0.00E-01 12.0E+01 E. Volume of Waste Released "iters 4.14E+06 5.29E+06 5.09E+06 4.14E+06 14.0E+00 F. Volume of Dilution Liters 3.34E+08 5.18E+08 4.32E+08 3.24E+08 il.lE+01 Water for Period EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 12.94 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G. Nuclide Summary (Note: Refer to Table A for ODCM nuclides reported as 0.00E-01)

Required by ODCM/Others Fission and Activation Products Continuous Mode Batch Mode Nuclide Unit Ouarter Quarter Ouarter Quarter 1st 2nd 1st 2nd

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 1.98E-04

3. Iron-55 Ci 0.00E-01 0.00E-01 6.17E-02 2.57E-01

4. Manganese-54 Ci 0.00E-01 0.00E-01 2.54E-03 8.86E-03

5. Cobalt-58 Ci 0.00E-01 0.00E-01 1.25E-02 3.29E-02

6. Iron-59 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

7. Cobalt-60 Ci 0.00E-01 0.00E-01 4.11E-02 1.04E-01

8. Zinc-65 Ci 0.00E-01 0.00E-01 8.15E-04 4.34E-03

9. Molybdenum-99 Ci 0.00E-01 0.00E-bl 0.00E-01 8.23E-05

10. Iodine-131 Ci 0.00E-01 0.00E-01 1.26E-05 6.54E-03

11. Cesium-134 Ci 0.00E-01 0.00E-01 6.41E-03 1.51E-02

12. Cesium-137 Ci 0.00E-01 7.98E-06 1,26E-02 2.51E-02 '

13. Cerium-141 Ci 0.00E-01 1.07E-05 0.00E-01 0.00E-01 I 1

14. Cerium-144 Ci 0.00E-01 0.00E-01 12 53E-03 7.85E-04

)

15. Antimony-125 Ci 0.00E-01 0.00E-01 4.72E-02 3.68E-02

16. Cobalt-57 Ci 0.00E-01 0.00E-01 4.48E-04 1.73E-03

17. Chromium-51 Ci 0.00E-01 0.00E-01 1.88E-03 1221E-03

18. Niobium-95 Ci 0.00E-01 0.00E-01 2.14E-03 6.90E-04 1

- -. . . . ~ . . . - - - . . .. - .__

EFFLUENT AND WALTE DISPOSAL ANNUAL REPORT 1224 '

LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE (CONTINUED)

Continuous Mode Batch Mode Nuclide Unit Ouarter Ouarter Quarter Quarter lee 2nd let 2nd

19. Iodine-133 Ci- 0.00E-gl 0.00E-01 0.00E-01 1.25E-03

20. Zirconium-95 Ci 0.00E-01 0.00E-01 8.77E-04 9.03E-05 l

21. Technetium-99m Ci 0.00E-01 0.00E-01 0.00E-01 8.23E-05

22. Strontium-92 Ci 0.00E-01 0.00E-01 2.11E-05 9.83E-05 ,

23. Tellurium-132 Ci 0.00E-01 0.00E-01 2.06E-06 3.46E-06

24. Antimony-124 Ci 9 00E-01 0.00E-01 1.47E-04 1.16E-05 ,

25. Lanthanum-140 Ci 0.00E-01 0.00E-Q1 0.00E-Ol' 7.56E-05 7 t

26. Cesium-136 Ci 0.00E-01 0.00E-01 0.00E-01 1.48E-04 l i'

27. Sodium-24 Ci 0.00E-01 0.00E-01 5.07E-06 1.94E-03

28. Cesium-138 Ci 0.00E-01 0.00E-01 0.00E-01 1.09E-05

29. Niobium-97 Ci 0.00E-01 0.00E-01 1.09E-04 2.65E-04 I l

30. Strontium-91 Ci 0.00E-01 0.00E-01 9.81E-06 1.20E-05 ?

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31. Bromine-82 Ci 0.00E-01 0.00E-01 0.00E-01 2.40E-04

32. Silver-110m Ci 0.00E-01 0.00E-01 1.20E-03 2.04E-03 l

33. Tellurium-129m Ci 0 00E-Q1 0.00E-01 0.00E-01 1.78E-04 I

34. Yttrium-91m Ci 0.00E-01 0.00E-01 5.95E-0k 0.00E-01 ,

1 Total for Period Ci 0.00E-01 1.87E-05 1.93E-01 5.02E-01 f

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1994 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE (CONTINUED)

G. Nuclide Summary (NOTE: Refer to Table A for ODCM nuclides reported as C.00E-01)

Required by ODCM/Others Dissolved and Entrained Noble Cases Continuous Mode Batch Mode ,

Nuclide Unit Ouarter Ouarter Quarter Ouarter i lst 2nd 1st 2nd

1. Krypton-87 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ,

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2. Krypton-88 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

3. Xenon-133 Ci 0.00E-01 0.00E-01 8.31E-03 2.26E-02

4. Xenon-133m Ci 0.00E-01 0.00E-01 0.00E-01 2.16E-04 ,

5. Xenon-135 Ci 0.00E-01 0.00E-01 0.00E-01 2.97E-03 ,

6. Xenon-138 Ci 0.00E:Q1 0.00E-01 0.00E-01 0.00E-01 !

7. Krypton-85m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

8. Xenon-131m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 j

9. Xenon-135m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l

10. Krypton-85 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

11. Argon-41 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Total fo. Period Ci 0.00E-01 0.00E-01 8.31E-03 2.58E-02 l

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1994 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G. Nuclide Summary (Note: . Refer to Table A for ODCM nuclides reported as 0.00E-01)

Required by ODCM/Others Fission and Activation Products Continuous Mode Batch Mode Nuclide Unit Ouarter Quarter Ouarter Quarter 3rd 4th. 3rd 4th

1. Strontium-89 Ci 0.00E-01 0.00E-01 -1.03E-03 0.00E-01

2. Strontium-90 Ci 0.00E-01 0.00E-01 2.55E-04 0.00E-01

3. Iron-55 Ci 0.00E-01 0.00E-01 1.47E-01 3.52E-02

4. Manganese-54 Ci 0.00E-01 0.00E-01 7.49E-Q3 5.76E-03

5. Cobalt-58 Ci 8.38E-07 4.90E-04 4.38E-01 2.82E-01

6. Iron-59 Ci 0.00E-01 0.00E-01 4.47E-03 9.94E-04

7. Cobalt-60 Ci 0.00E-01 3.65E-05 3.49E-02 4.30E-02

8. Zinc-65 Ci 0.00E-01 0.00E-01 5.61E-03 1.68E-03

9. Molybdenum-99 Ci 0.00E-01 0.00E-01 1.96E-03 4.2]E-04

10. Iodine-131 Ci 0.00E-01 0.00E-01 2 12E-02 2.58E-03

11. Cesium-134 Ci 0.00E-01 2.18E-06 2.02E-02 4.21E-03

12. Cesium-137 Ci 3.94E-06 1.79E-05 2.68E-02 9.69E-03

13. Cerium-141 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i

14. Cerium-144 Ci 0.00E-01 4.13E-05 6.35E-05 0.00E-01

15. Antimony-125 Ci 0.00E-01 0.00E-01 2142.E-02 3.42E-02

16. Cobalt-57 Ci 0.00E-01 0.00E-01 1.18E-03 1.35E-03

17. Chromium-51 Ci 0.00E-01 0.00E-01 4.26E-02 3.05E-02 l

18. Niobium-95 Ci 0.00E-01 0.00E-01 3.80E-03 6.67E-03 l l

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT- l au LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE (CONTINUED)

Continuous Mode Batch Mode Nuclide Unit Ouarter Quarter Quarter Ouarter 3rd 4th 3rd 4th

19. Iodine-133 Ci 0.00E-01 0.00E-01 5.96E-03 1.80E-03

20. Zirconium-95 Ci 0.00E-01 0.00E-01 1.96E-03 2.23E-03

21. Technetium-99m Ci 0.00E-01 0.00E-Q1 1.62E-03 3.94E-04

22. Ruthenium-103 Ci 0.00E-01 0.00E-01 8.48E-05 5.73E-06 l

23. Antimony-124 Ci 0.00E-01 0.00E-01 1.39E-02 3.85E-03

24. Lanthanum-140 Ci 0.00E-01 0.00E-01 3.08E-04 4.14E-05

25. Barium-140 Ci 0.00E-01 0.00E-01 2.14E-05 0.00E-01

26. Sodium-24 Ci 0.00E-01 0.00E-01 7.82E-04 1.02E-04 '

27. Cesium-138 Ci 0.00E-01 0.00E-01 1.35E-04 4.50E-05

28. Strontium-92 Ci 0.00E-01 0.00E-01 2.77E-05 2.43E-04 ,

29. Niobium-97 Ci 0.00E-01 0.00E-01 8.91E-05 -6.70E-04

30. Yttrium-91 Ci 0.00E-01 0.00E-01 2.40E-03 0.00E-01 !

31. Silver-110m Ci 0.00E-01 0.00E-01 1.62E-03 7.10E-03 ,

32. Nickel-65 Ci 0.00E-01 9 00E-01 0.00E-01 1.63E-05

33. Barium-139 Ci 0.00E-01 0.00E-01 4.78E-05 Q29pE-pl

34. Bromine-82 Ci 0.00E-01 0.00E-01 2.79E-05 0.00E-01 !

35. Be ry111um-7 Ci 0.00E-01 0.00E-01 1.10E-03 0.00E-01 ,

36. Bromine-84 Ci 0.00E-01 0.00E-01 7.53E-05 0.00E-01

37. Cesium-136 Ci 0.00E-01 0.00E-01 1.09E-03 0.00E-01

38. Iodine-132 Ci 0.00E-01 0.00E-01 3.03E-04 0.00E-01

39. Iodine-135 Ci 0.00E-01 0.00E-01 5.47E-04 1.59E-04

40. Manganese-56 Ci 2.00E-Q1 0.00E-01 4.10E-05 0.00E-01 t

41. Tin-ll3 Ci 0.00E-01 0.00E-01 5.47E-04 4.69E-04 l

42. Tellurium-129m Ci 0.00E-01 0.00E-01 3.68E-03 0.00E-01

43. Zinc-69m Ci 0.00E-01 0.00E-01 4.37E-06 0.00E-01 {

44. Yttrium-93 Ci 0.00E-01 0.00E-01 0.00E-01 7.64E-05 Total for Period C1 4.78E-06 5.88E-04 8.28E-01 4.80E-01 I

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1994 '

.I LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE (CONTINUED)

G. Nuclide Summary (NOTE: Refer to Table A for ODCM nuclides reported as 0.00E-01)

Required by ODCM/Others Dissolved and Entrained Noble Cases Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Ouarter Ouarter 3rd 4th 3rd 4th j 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 0.00E-01 2.32E-05

3. Xenon-133 Ci 0.00E-01 0.00E-01 7.29E-02 6.47E-03

4. Xenon-133m Ci 0.00E-01 0.00E-01 3.26E-04 0.00E-01

5. Xenon-135 Ci 0.00E-01 0.00E-01 2.56E-03 3.48E-04

6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

7. Krypton-85m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

8. Xenon-131m Ci 0.00E-01 5.46E-04 5.92E-04 0.00E-01

9. Xenon-135m Ci 0.00E-01 0.00E-01 2.19E-05 0.00E-01

10. Krypton-85 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

11. Argon-41 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Total for Period Ci 0.00E-01 5.46E-04 7.64E-02 6.84E-03

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EFFLUENT AND' WASTE DISPOSAL ANNUAL. REPORT [

1994 TABLE A LIQUID " TYPICAL LLD" EVALUATION (1) i At(2) l Nuclide ODCM LLD 15 min 30 min 1 hr _ 2 hr Manganese-54 5.0E-07 2,12E-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 {

t Cobalt-60 5.0E-07 1.08E-08 1.08E-08 1.08E-08 1.08E-08 i Zinc-65 5.0E-07 2.14E-08 2.14E-08 2.14E-08 2.14E-08 [

4 Molybdenum-99 5.0E-07 5.24E-08 5.25E-08 5.28E-08 5.34E-08 l Cesium-134 5.0E-07 9.82E-09 9.82E-09 9.82E-09 9.82E-09 Cesium-137 5.0E-07 9.31E-09 9.31E-09 9.31E-09 9.31E-09 l Cerium-141 5.0E-07 1.06E-08 1.06E-QR 1.07E-08 1.07E-08 Cerium-144 5.0E-06 4.03E-08 4.03E-08 4.03E-08 4.03E-08 :

Iodine-131 1.0E-06 7.28E-09 7.28E-09 7.30E-09 7.32E-09 f

Krypton-87 1.0E-05 1.62E-08 1.85E-08 2.43E-08 4.20E-11 ;

l Krypt on-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 f

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 l

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 122A F TABLE A f LIQUID " TYPICAL LLD" EVALUATION (1) f (Continued) ;

Nuclide ODCM LLD Tvolcal LLD :

l Tritium 1.0E-05 1.0E-06 i

Gross Alpha 1.0E-07 120E-08 ;

Strontium-89 5 0E-08 2.0E-08 Strontium-90 5.0E-08 1.0E-08 ,

Iron-55 1.0E-06 ldE, _QZ i

NOTES: (1) LLD values are in pCi/ml. Sample analyses are performed to ensure that ODCM LLD limits are met. These are typical LLD values.

(2) at is the time between sample collection and counting time.

4 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1 19_4 GASE0US EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES) let 2nd 3rd 4th Summation of All Releases Unit Otr Otr Otr Otr % Error A. Noble Gases

1. Total Released Ci 2.55E+00 1.01E+01 8.72E+01 1.36E+01 il.1E+01

2. Average Release Rate of Period pCi/sec 3.28E-01 1.27E+00 1.10E+01 1.71E+00

3. Percent of Applicable Limit % 9.25E-05 8.46E-04 3.66E-03 8.85E-04 B. Iodines

1. Total Iodine-131 Ci 0.00E-01 0.00E-01 8.47E-06 0.00E-01 il.3E+01

2. Average Release Rate for Period pCi/sec 0.00E-01 0.00E-01 1.08E-06 0.00E-01

3. Percent of Applicable Limit (1.60E-01 pCi/sec) % 0.00E-01 0.00E-01 6.73E-04 0.00E.01 C. Particulates

1. Particulates with Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 il.6E+01 half-lives >8 days

2. Average Release Rate for Period pCi/sec 0.00E-01 0.00E-01 0.00E-01 0.00E-01

3. Percent of Applicable Limit % 0.00E-01 0.00E-01 0.00E-01 0.00E-01

4. Gross Alpha Radio- Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 12.lE+01 activity D. Tritium

1. Total Release Ci 2.11E+00 1.78E+00 5.36E+00 5.57E+00 il.5E+01

2. Average Release Rate for Period pCi/sec 2.71E-01 2.26E-01 6.74E-01 7.01E-01

3. Percent of Applicable Limit (8.47E+04 pCi/sec) 3.20E-04 2.67E-04 7.96E-04 8.27E-04 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1994 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)

Continuous Mode Batch Mode Unit Quarter Ouarter Quarter Ouarter 1st 2nd 1st 2nd

1. Noble Gases Required by ODCM/Others

1. Krypton-87 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

2. Krypton-88 Ci 0.00E-01 3.45E-03 9 00E-01 1.95E-02

3. Xenon-133 Ci 2.23E-02 2.18E-02 2.31E+00 9.04E+00

4. Xenon-133m Ci 0.00E-01 0.00E-01 3.93E-03 1.11E-01

5. Xenon-135 Ci 3 65E-03 1.21E-02 4.49E-02 6.56E-01

6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

7. Krypton-85 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ,

1

8. Argon-41 Ci 0.00E-01 1.44E-04 1.60E-01 2.47E-01 l

9. Krypton-85m Ci 0.00E-01 2.93E-04 0.00E-01 3.39E-02 l

10. Xenon-131m Ci 0.00E-01 0.00E-01 7.92E-04 2.51E-03

11. Xenon-135m Ci 0.00E-01 7.48E-03 0.00E-01 0.00E-01 Total for Period Ci 3.10E-02 4.53E-02 2.52E+00 1.01E+01 l

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2. Iodines

1. Iodine-131 Ci 0.00E-01 0.00E-01

2. Iodine-133 Ci 0.00E-01 Q100E-01

3. Iodine-135 Ci 0.00E-01 0.00E-01 Total for Period Ci 0.00E-01 0.00E-01 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l 1994 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES , ,

(GROUND LEVEL RELEASES) )

3. Particulates l

Required by ODCM/Others l 1

1 Continuous Mode !

Nuclide Unit Ouarter Ouarter 1st 2nd

1. Strontium-89 Ci 0.00E-01 0.00E-01

2. Strontium-90 Ci 0.00E-01 0.00E-01

3. Iron-59 Ci 0.00E-01 0.00E-01 ;

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4. Cobalt-60 Ci 0.00E-01 0.00E-01

5. Zinc-65 Ci 0.00E-01 0.00E-01 l

6. Manganese-54 Ci 0.00E-01 0.00E-01

7. Cobalt-58 Ci 0.00E-01 0.00E-01

8. Molybdenum-99 Ci 0.00E-01 9 00E-01 i

9. Cesium-134 Ci 0.00E-01 0. 00E-91

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 i Total for Period Ci 0.00E-01 0.00E-01 HOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1994 !

GASEOUS EFFLUENTS-SU!MATION OF ALL RELEASES ;

(GROUND LEVEL RELEASES) i Continuous Mode Batch Mode !

Unit Ouarter Ouarter Ouarter Ouarter 3rd 4th 3rd 4th i

1. Noble Cases Required by ODCM/Others

1. Krypton-87 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-00 ;

2. Krypton-88 Ci 1.33E-03 0.00E-01 9.17E-03 0.00E-01

3. Xenon-133 Ci 4.44E+00 1.18E-02 7.91E+01 1.21E+01 ;

t

4. Xenon-133m Ci 0.00E-01 0.00E-01 1.61E+00 3.67E-01

5. Xenon-135 Ci 8.51E-03 1.58E-02 1.42E+00 8.37E-01 '

6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

7. Krypton-85 Ci 0.00E-01 0.00E-01 4.18E-01 3.28E-02 ;

8. Argon-41 Ci 0.00E-01 1.30E-02 6.51E-02 1.67E-01 l 1

9. Krypton-85m Ci 1.85E-05 6.494-94 2.98E-02 5.58E-02 '

10. Xenon-131m Ci 0.00E-01 0.00E-01 7.25E-02 0.00E-01

11. Xenon-135m Ci 2.79E-03 Q.00E-01 0.00E-01 0.00E-01 i.

Total for Period Ci 4.45E+00 4.13E-02 8.27E+01 1.36E+01 j

2. Iodines

1. Iodine-131 Ci 8.47E-06 0.00E-01

2. Iodine-133 Ci 0.00E-01 0.00E-01

3. Iodine-135 Ci 0.00E-01 0.00E-01 Total for Period Ci 8.47E-06 Q,00E-01 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01. ,

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l 19.2.%

GASEOUS EFFLUENTS-SUI 91ATION OF ALL RELEASES (GROUND LEVEL RELEASES)

3. Particulates i

Required by ODCM/Others Continuous Mode Raclide Unit Ouarter Ouarter 3rd 4th

1. Strontium-89 Ci 0.00E-01 0.00E-01 l

2. Strontium-90 Ci 0.00E-01 0.00E-01

3. Iron-59 Ci 0.00E-01 0.00E-01

4. Cobalt-60 Ci 0.00E-01 0.00E-01 l i

5. Zinc-65 Ci 0.00E-01 0.00E-01 l

[

6. Manganese-54 Ci 0.00E-01 0.00E-01 i i

7. Cobalt-58 Ci 0.00E-01 0.00E-01 '

8. Molybdenum-99 Ci 0.00E-01 0.00E-01 l

9. Cesium-134 Ci 0.00E-01 0.00E-01 -

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

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

r

12. Cerium-144 Ci 0.00E-01 0.00E-01 0.00E-01 Total for Period Ci 9 00E-01 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01. j i

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

9 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT +

1994 TABLE B i GASEOUS " TYPICAL" LLD EVALUATION (1) -

Hoble Gas-At(2) !

Nuclide ODCM LLD 1 hr 1.5 hr !

Krypton-87 1.0E-04 1.19E-06 2.69E-06 Krypton-88 1.0E-04 1.22E-06 1.76E-06 Xenon-133 1.0E-04 5.51E-Ol 5.56E-07 Xenon-133m 1.0E-04 1.99E_06 2.02E-06 ,

Xenon-135 1,pE-Q4 2.59E-07 2.90E-07 Xenon-138 1.0E-04 5.38E-05 8.55E-05 i

Particulate Sample 2.02 da 2.79 da 5.79 da Manganese-54 1.0E-15 1.83E-12 7.65E-14 1.10E-14 i

Cobalt-58 1.0E-10 1.60E-12 4.79E-14 9.99E-15 Iron-59 1.0E-10 3.21E-12 1.36E-13 2.03E-14 Cabalt-60 1.0E-10 1.79E-12 7.46E-14 1.07E-14 Zinc-65 1.0E-10 4.08E-12 1.71E-13 2.46E-14 Molybdenum-99 1.0E-10 2.08E-12 1.05E-13 3.18E-14 Cesium-134 1.0E-10 2.03E-12 8.45E-14 1.21E-14 Cesium-137 1.0E-10 1.85E-12 7.71E-14 1.10E-14 Cerium-141 1.0E-10 2.32E-12 9.82E-14 1.50E-14 Cerium-144 1.0E-10 1.03E-12 4.28E-13 6.16E-14 Iodine-131 1.0E-10 1.85E-12 8.22E-14 1.52E-14 Charcoal Sample 2.0 da 2.5 da 5.5 da Iodine-131 1.0E-11 2.53E-12 1.10E-13 2.00E-14

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1994 TABLE:B GASEOUS " TYPICAL" LLD EVALUATION (1) l (continued)

Nuclide ODCM LLD Tvolcal LLD i Tritium 1.0E-06 1.0E-ll Gross Alpha 1.0E-ll 1.5E-14 Strontium-89 1.0E-ll 1.0E-14

' Strontium-90 1.0E-Il 1.0E-15 NOTES: (1) LLD values are in pCi/cc.

(2) At for noble gases is the time from sampling to analysis. j at for charcoal and particulate samples is the midpoint of ,

sampling to analysis.

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1994 SOLID WASTE (RADI0 ACTIVE SHIPMENTS)

A. Solid Waste Shipped Offsite for Burial or Disposal (not Irradiated Fuel) 12 Month Est. Tot.

1. Type of Waste Unit Period Error %

a. Spent resins, filter sludges, m3 1.18E+01 11.00E-1 evaporator bottoms, etc. Ci 2.93E+01 il.50E+1

b. Dry Active Waste, Compressible Waste m3 4.61E+01 il.00E-1 Contaminated Equipment, etc. Ci 5.76E+00 il.50E+1

c. Irradiated Components, m3 None N/A Control Rods, etc. Ci None N/A

d. Other: Mechanical Filters m3 3.50E+00 i .00E-1 l

Floor Drain Media Ci 6.20E+01 i .50E+1 l

2. Estimate of Maior Nuclide Composition (by tvoe of waste)

a. Spent resins, filter sludges, evaporator bottoms, etc.

(nuclides determined by measurement)

Curies Percent

1. Iron-55 1.54E+01 5.25E+01

2. Cobalt-58 4.11E-01 1.40E+00

3. Cobalt-60 5.22E+00 1.78E+01 ,

4. Nickel-63 7.49E+00 2.55E+01

5. Cesium-137 5.28E-01 1.80E+00

b. Dry active waste, compressible waste, contaminated equipment, etc.

(nuclides determined by estimate)

1. Chromium-51 2.27E-01 3.94E+00

2. Manganese-54 6.75E-02 1.17E+00

3. Iron-55 2.00E+00 3.47E+01

4. Cobalt-58 1.15E+00 2.00E+01

5. Cobalt-60 4.62E-01 8.02E+00

6. Nickel-63 3.15E-01 5.46E400

7. Niobium-95 9.90E-02 1.72E+00

8. Zirconium-95 6.32E-02 1.10E+00

9. Cesium-134 5.55E-01 9.63E+00

10. Cesium-137 7.21E-01 1.25E+01

c. Irradiated Components N/A N/A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1994 -

SOLID WASTE (RADI0 ACTIVE SHIPMENTS)

2. Estimate of Major Nuclide Composition (by type of waste) Continued

d. Other: Mechanical Filters, Floor Drain Media (nuclides determined by estimate)

Curies Percent >

f

1. Manganese-54 9.33E-01 1.51E+00

2. Iron-55 2.56E+01 4.12E+01

3. Cobalt-58 9.82E+00 1.58E+01

4. Cobalt-60 9.92E+00 1.60E+01 !

5. Nickel-63 7.14E+00 1.15E+01 ,

6. Chromium-51 3.96E+00 6.39E+00 l

7. Niobium-95 1.55E400 2.50E+00 ,

8. Zirconium-95 1.72E+00 2.77E+00

9. Ruthenium-106 9.74E-01 1.57E+00

3. Solid Waste Disposition Number of Shioments Type Ouantity Mode of Transportation Destination a) Spent resins, filter sludges, evaporator bottoms, etc.

1 B-LSA Motor Freight Barnwell, SC i 2 A-LSA Motor Freight Barnwell, SC Number of Shipments Type Ouantity Mode of Transportation Destination b) Dry active waste, compressible waste, contaminated equipment, etc.

110 A-LSA Motor Freight Barnwell, SC l

. Number of Shipments Type Ouantity Mode of Transportation Destination i c) Irradiated components, control rods, etc.

None Number of Shioments Type Ouantity Kode of Transportation pestination d) Other: Mechanical Filters, Floor Drain Media 1 B-LSA Motor Freight Barnwell, SC 1 A-LSA Motor Freight Barnwell, SC

4. Irradiated Fuel Shioments (Disposition)

Number of Shipments Tvoe Ouantity Mode of Transportation Destination None N/A N/A N/A

5. Solidification of Waste Was solidification performed? NO If yes, solidification media: N/A

Effluent and Waste Disposal Annual Report 1994 Attachment 1.0 INOPERABLE INSTRUMENTATION Pursuant to ODCM Section 1.1.2, the following information is provided concerning radioactive effluent monitoring instrumentation which was inoperable for greater than 30 consecutive days during the period of January 1, 1994, through December 31, 1994. ;

I Radiation Monitor System Date/ Time Date/ Time Total l Number Monitored Out of Service Returned to Service Days I i

1-RM-90-400 U-l Shield Bldg 3/4/94 1400 4/11/94 1052 38 The Unit 1 Shield Building radiation monitor was considered inoperable for the timeframe noted above due to problems identified during calibration. The _

primary sample flow element located in the annulus had to be cleaned and !

retested. The flow element associated with containment purge also had to be removed for calibration.

Effluent and Waste Disposal Annual Report 1994 - --

Attachment 2.0 Unmonitored Releases In accordance with Regulatory Guide 1.21 and the ODCM Section 1.2.1.1 and 1.2.2.1, any unmonitored effluents should be clearly identified in the annual effluent report and the methods utilized in evaluating any radioactive effluents and/or offsite dose. j i

Irrbine Building Sump The ODCM requires daily sampling and weekly analysis of the Turbine Building Sump. In an effort to ensure accurate and timely analysis, samples are collected and analyzed on a daily basis. Ilowever during the review of the weekly surveillance package, it was determined that on 5/20/94 a sample was ,

not collected and/or analyzed. As noted, samples are collected and analyzed daily and during 1994 no radioactivity was identified in the Turbine Building Sump; therefore, no radioactivity was calculated or reported for the 5/20/94 missed sample. Timers are now in place with alarm functions to remind analysts of required sampling.

Auxiliary Building Exhaust On 4/7/94, the inspection port for Auxiliary Building 2A General Exhaust Fan was found off the duct and lying on the auxiliary building roof. This configuration permitted the partial release of auxiliary building exhaust air flow without being monitored by the auxiliary building monitor 0-RM-90-101.

The probable cause of the inspection port falling out was years of use with no maintenance program in place to inspect or repair them; they have now been added to the existing program for inspection and maintenance. A sample of the l auxiliary building exhaust flow was collected and analyzed on 4/7/94, !

1 identifying only tritium at an organ dose rate of 1.12E-03 mrem /yr (particulate, iodine and tritium limit 1500 mrem /yr). During 1994 only 8.47E-06 Curies of I-131 was identified in all gaseous effluents from the auxiliary building exhaust; therefore, no additional release evaluations were performed. l I

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ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT RADIOLOGICAL IMPACT ASSESSMENT REPORT (S58 950414 801)

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Radiologicalimpact Assessment Sequoyah Nuclear Plant January - December 1994 Page 1 of 17 INTRODUCTION Potential doses to maximum individuals and the population around Sequoyah are calculated for each quarter as required in Section 5.2 of the Offsite Dose Calculation Manual (ODCM).

Measured plant releases for the reporting period are used to estimate these doses. Dispersion of radioactive effluents in the environment is estimated using meleorological data and riverflow data measured during the period. In this report, the doses resulting from releases are described and compared to limits established for Sequoyah.

DOSE LIMITS The ODCM specifies limits for the release of radioactive effluents, as well as limits for doses to the general public from the release of radioactive effluents. These limits are se: well below the Technical Specification limits which govern the concentrations of radioactivity and doses permissible in unrestricted areas. This ensures that radioactive effluent releases are As low As Reasonably Achievable.

The limits for doses in unrestricted areas from airborne noble gases releases are:

Less than or equal to 5 mrad per quarter and 10 mrod per year (per reactor unit) for gamma radiation,and Less than or equal to 10 mrod per quarter and 20 mrod per year (per reactor unit) for beta radiation.

The limit for the dose to a member of the general public in an unrestricted area from iodines and particulates released in airborne effluents is: I Less than or equal to 7.5 mrem per quarter and 15 mrem per year (per reactor unit) to any organ.

The limit for doses to a member of the general public from radioactive material in liquid effluents released to unrestricted areas,is:

Less than or equal to 1.5 mrem per quarter and 3 mrem per year (per reactor unit) to the total body,and Less than or equal to 5 mrem per quarter and 10 mrem per year (per reactor Unit) to any organ The EPA limits for total dose to the public in the vicinity of a nuclear power plant, established in the Environmental Dose Standard of 40 CFR 190, are: j i

Less than or equal to 25 mrem per year to the total body, l Less than or equal to 75 mrem per year to the thyroid,and I Less than or equal to 25 mrem per year to any other organ. j i

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l RadiologicalImpact Assessment l I

Sequoyah Nuclear Plant January - December 1994 Page 2 of 17 l

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DOSE CALCULATIONS Estimated doses to the public are determined using computer models (the Gaseous Effluent ,

Licensing Code, GELC, and the Quarterly Water Dose Assessment Code, QWATA). These j models are based on guidance provided by the NRC (in Regulatory Gnides 1.109,1.111 and i 1.113) for determining the potential dose to individuals and populations living in the vicinity of the plant. The area around the plant is analyzed to determine the pathways through which ,

the public may receive a dose. The doses calculated are a represent ition ' the dose to a :

" maximum exposed individual." Some of the factors used in these calcuiations (such as !

ingestion rates) are maximum values. Many of these factors are obtains.d from NUREG/CR-1004. The values chosen will tend to overestimate the dose to this "maximt.m" person. The 1 expected dose to actualindividuals is lower. The calculated doses are presented in Tables 1 through 9.

l DOSES FROM AIRBORNE EFFLUENTS For airborne effluents, the public can be exposed to radiation from several sources: direct radiation from the radioactivity in the air, direct radiation from radioactivity deposited on the i ground, inhalation of airborne radioactivity, ingestion of vegetation which contains j radioactivity deposited from the atmosphere, and ingestion of milk and beef which contains I radioactivity deposited from the atmosphere onto vegetation and subsequently eaten by milk and beef animals.

Airbome Discharae Points All releases from Sequoyah are considered ground-level releases. The ground-level Joint Frequency Distribution (JFD) is derived from windspeeds and directions measured 10 meters above ground and from the vertical temperature difference between 10 and 46 meters, and are presented for each quarterin Attachment 1.0 MeteoroloaicalData Meteorological variables at Sequoyah are measured continuously. Measurements collected include wind speed, wind direction, and temperature at heights of 10, 46, and 91 meters above the ground. Quarterly joint frequency distributions (JFDs) are calculated for each release point using the appropriate levels of meteorological data. A joint frequency distribution gives the percentage of the time in a quarter that the wind is blowing out of a particular upwind compass sector in a particular range of wind speeds for a given stability class A through G. The wind speeds are divided into nine wind speed ranges. Calms are distributed by direction in proportian to the distribution of noncalm wind directions less than 0.7 m/s (1.5 mph). Stability classes are determined from the vertical temperature difference between two measurement levels.

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RadiologicalImpact Assessment l Sequoyah Nuclear Plant l January- December 1994 j Page 3 of 17 EgfemalExoosure Dose l Dose estimates for maximum external air dose (gamma-air and beta-air doses) are r ade for points at and beyond the uruesiricted area boundary as described in the Sequoyah ODCM. !

The highest of these doses is then selected. l Svbmersion Dose ?

External doses to the skin and total body, due to submersion in a cloud of noble gases, are estimated for the nearest residence in each sector. The residence with the highest dose is ,

then selected from all sectors. !

l Oraan Dose Doses to organs due to releases of airborne effluents are estimated for the inhalation, ground .

contamination, and ingestion pathways. The ingestion pathway is further divided into four possible contributing pathways: ingestion of cow / goat milk, ingestion of beef, and ingestion of

vegetables. Doses from applicable pathwnys are calculated for each real receptor location identified in the most recent land use survey. To determine the maximum organ dose, the doses from the pathways are summed for each receptor. For the ingestion dose, however, only those pathways that exist for each receptor are considered in the sum, i.e., milk ingestion j doses are included only for locations where milk is consumed without commercial preparation and vegetable ingestion is included only for those locations where a garden is identified. To conservatively account for beef ingestion, a beef ingestion dose equal to that }

for the highest unrestricted area boundary location is added to each identified receptor. For j ground contamination, the dose added to the organ dose being calculated is the total body j dose calculated for that location, i.e., it is assumed that the dose to on individual organ is i equal to the total body dose. ;

Doses from airborne effluents are presented in Tables 1 through 4. l l

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RadiologicalImpact Assessment Sequoyah Nuclear Plant January - December 1994 Page 4 of 17 DOSES FROM LlOUID EFFLUENTS For liquid effluents, the public can be exposed to radiation from three sources: the ingestion of water from the Tennessee River, the ingestion of fish caught in the Tennessee River, and direct exposure from radioactive material deposited on the river shoreline sediment (recreation).

The concentrations of radioactivity in the Tennessee River are estimated by a computer model which uses measured hydraulic data downstream of Sequoyah. Parameters used to determine the doses are based on guidance given by the NRC (in Regulatory Guides 1.109) for maximum ingestion rates, exposure times, etc. Wherever ponible, parameters used in the dose calculation are site specific use factors determined by TVA. The models that are used to estimate doses, as well as the parameters input to the models, are described in detail in the Sequoyah Nuclear Plant ODCM.

Liavid Release Points and River Data Radioactivity concentrations in the Tennessee River are calculated assuming that releases in liquid effluents are continuous. All routine liquid releases from Sequoyah, located at Tennessee River Mile 484, are made through diffusers which extend into the Tennesseo River. It is assumed that releases to the river through these diffusers will initially be entrained in one-fifth of the water which flows past the plant. The QWATA code makes the assumption that this mixing condition holds true until the water is completely mixed at the first downstream dam, at Tennessee River Mile 471.0.

Doses are calculated for locations within a 50 mile radius downstream of the plant site. The maximum potential recreation dose is calculated for a location immediately downstream from the plant outfall. The maximum individual dose from ingestion of fish is assumed to be that calculated for the consumption of fish caught anywhere between the plant and the first downstream dam (Chickamauga Dam). The maximum individual dose from drinking water is assumeJ to be that calculated at the nearest downstream public water supply (E.1. DuPont).

This could be interpreted as indicating that the maximum individual, as assumed for liquid releases from Sequoyah, is an individual who obtains all of his drinking water at E. l. DuPont, consumes fish caught from the Tennessee River between Sequoyah and Chickamauga Dam, and spends 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months per year on the shoreline just below the outfall from Sequoyah. Dose estimates for the maximum individual due to liquid effluents for eacF quarter in the period are presented in Tables 5 through 8, along with the average river flows post the plant site for the periods.

POPULATION DOSES Population doses for highest exposed organ due to airborne effluents are calculated for an estimated 1,060,000 persons living within a 50-mile radius of the plant site. Doses from external pathways and inhalation are based on the 50-mile human population distribution. Ingestion population doses are calculated assuming that each individual consumes milk, vegetables, l

Radiologicalimpact Assessment Sequoyah Nuclear Plant January - December 1994 Page 5 of 17 and meat produced with the sector annulus in which he resides. Doses from external pathways and inhalation are based on the 50-mile human population distribution.

Population doses for total body and the maximum exposed organ due to liquid effluents are calculated for the entire downstream Tennessee River Population. Water ingestion population doses are calculated using actual population figures for downstream public water supplies.

Fish ingestion population doses are calculated assuming that all sport fish caught in the Tennessee River are consumed by the Tennessee River population. Recreation population doses are calculated using actual recreational data on the number of shoreline visits at downstream locations.

Population dose estimates for airborne and liquid effluents are presented in Tables 1 through 8.

i

l RadiologicalImpact Assessment l Sequoyah Nuclear Plant January - December 1994 Page 6 of 17 DIRECT RADIATION External gamma radiation levels were measured by thermoluminescent dosimeters (TLDs) deployed around Sequoyah. The quarterly gamma radiation levels determined from these l TLDs during this reporting period averaged approximately 14.7 mR/ quarter at onsite stations and approximately 13.2 mR/ quarter at offsite stations, or approximately 1.5 mR/ quarter higher onsite than at offsite stations. This is consistent with levels reported at TVA's non operating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6 mR/ quarter higher than the levels offsite. This may be attributable to natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the corstruction of the plants, or other undetermined influences. Fluctuations in natural background dose rates and in TLD readings tend to mask any small increments which may be due to plant operations. Thus, there was no identifiable increase in dose rate levels attributable to direct radiation from plant equipment and/or gaseous effluents.

DOSE TO A ME,MBER OF THE PUBLIC INSIDE THE UNRESTRICTED AREA BOUNDARY As stated in the Sequoyah Offsite Dose Calculation Manual, an evaluation of the dose to a member of the public inside the unrestricted area boundary is performed for a hypothetical l TVA employee who works just outside the restricted area fence for on entire workyear (2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months ). Results from onsite TLD measurements for the calendar year in question indicate that the highest onsite TLD reading was 85.3 mrem. Using this value, and subtracting an annual background value of 55 mrem / year, and multiplying by the ratio of the occupancy times, the highest external dose to a member of the public inside the unrestricted area boundary is 6.9 mrem. The doses due to radioactive effluents released to the atmosphere calculated in this report would not add a significant amount to this measured dose. This dose is well below the 10 CFR 20 annual limit of 100 mrem. .

1 1

TOTAL DOSE To determine compliance with 40 CFR 190, annual total dose contributions to the maxirnum individual from Sequoyah radioactive effluents and all other nearby uranium fuel cycle sources are considered.

The annual dose to any organ other than thyroid for the maximum individual is conservatively estimated by summing the following doses: the total body air submersion dose for each ;

quarter, the critical organ dose (for any organ other than the thyroid) from airborne effluents for each quarter from ground contamination, inhalation and ingestion, the total body dose from liquid effluents for each quarter, the maximum organ dose (for any organ other than the thyroid) from liquid effluents for each quarter, and any identifiable increase in direct radiation dose levels as measured by the environmental monitoring program. This dose is compared to the 40 CFR 190 limit for total body or any organ dose (other than thyroid) to determine compliance, l

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i RadiologicalImpact As;cssment !

Sequoyah Nuclear Plant January - December 1994 Page 7 of 17 ,

1 The annual thyroid dose to the maximum individual is conservatively estimated by summing l the following doses: the total body air submersion dose for each quarter, the thyroid dose from airborne effluents for each quarter, the total body dose from liquid effluents for each quarter, the thyroid dose from liquid effluents for each quarter, and any identifiable increase in direct radiation dose levels as measured by the environmental monitoring program. This dose is compared to the 40 CFR 190 limit for thyroid dose to determine compliance.

Cumulative annual total doses are presented in Table 9.

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Radiologicalimpact Assessment '

Sequoyah Nuclear Plant January - December 1994 Page 8 of 17 Table 1 ,

Doses from Airborne Effluents Frst Quarter Individual Doses t

Pathway Dose Quarterly Percent of . Location Limit Limit Sector / Distance Extemal i Gamma Air 4.40E-04 mrad 5 mrad 0.009 SSW/1840 Beta Air 6.86E-04 mrad 10 mrod 0.007 Submersion Total Body 3.12E-04 mrad 10 mrod 0.003 SSW/2134 Skin 5.91E-04 mrod 10 mrod 0.006 ;

Organ Doses Child / Thyroid 2.16E-03 mrem 7.5 mrem 0.29 SSW/2707 i Child / Total Body 2.16E-03 mrem 7.5 mrem 0.29 Population Doses Total Body Dose 1.54E-02 man-rem Maximum Organ Dose (organ) 1.54E-02 man-rem (thyroid)

Population doses can be compared to the naturalbackground dose for the entire 50-mile population of about 95,400 man-rem / year (based on 90 miem/yr for naturalbackground).

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RadiologicalImpact Assessm:nt !

Sequoyah Nuclear Plant January - December 1994 Page 9 of 17 1

Table 2 Doses from Nrborne Effluents Second Quarter '

individual Doses Pathway Dose Quarterly Percent of Location -

Limit Limit Sector / Distance Extemal -

Gamma Air 1.64E-03 mrad 5 mrad 0.003 N/950 Beta Air 2.94E-03 mrad 10 mrad 0.029 Submersion Total Body 1.02E-03 mrad 10 mrad 0.010 NNW/841 i Skin 2.07E-03 mrad 10 mrad 0.020 l

l Organ Doses l

Child / Thyroid 3.03E-03 mrem 7.5 mrem 0.040 NNW/841 Child / Total Body 3.03E-03 mrem 7.5 mrem 0.040 Populat on Doses Total Body Dose 1.12E-02 man-rem i Maximum Organ Dose (organ) 1.12E-02 man-rem (thyroid) l Population doses con be compared to the naturalbackground dose for the entire 50-mile population of about 95,400 man-rem / year (based on 90 miem/yr for naturalbackground).

RadiologicalImpact Assessment Sequoyah Nuclear Plant January- December 1994 Page 10 of 17 Table 3 Doses from Krborne Effluents Third Quarter Individual Doses Pathway Dose Quarterly Percent of Location Limit Limit Sector / Distance Extemal Gamma Air 9.24E-03 mrad 5 mrad 0.185 N/950 Beta Air 2.62E-02 mrad 10 mrad 0.262 Submersion Total Body 5.03E-03__mrod 10 mrad 0.050 NNW/841 Skin 1.21E-02 mrad 10 mrad 0.121 Organ Doses Child / Thyroid 1.15E-02 mrem 7.5 mrem 0.153 NNW/841 ;

Child / Total Body 1.14E-02 mrem 7.5 mrem 0.153 l Pooulation Doses Total Body Dose 4.74E-02 man-rem Maximum Organ Dose (organ) 4.78E-02 man-rem (thyroid)

Population doses can be compared to the naturalbackground dose for the entire 50-mile population of about 95.400 man-rem / year (based on 90 miem/yr for naturalbackground).

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RadiologicalImpact Assessment Sequoyah Nuclear Plant January - December 1994 ,

Page 11 of 17 Table 4 Doses from Airborne Effluents i Fourth Quarter l Individuol Doses l Pathway Dose Quarterly Percent of Location I Limit Limit Sector / Distance Extemal ;

Gamma Air 2.28E-03 mrad 5 mrad 0.046 SSW/1840 Beta Air 5.07E-03 mrad 10 mrad 0.051 Submersion Total Body 1.60E-03 mrad 10 mrad 0.016 SSW/2134 Skin 3.58E-03 mrod 10 mrod 0.036 i Organ Doses Child / Thyroid 8.07E-03 mrem . 7.5 mrem 0.108 SSW/2707 Child / Total Body 8.07E-03 mrem 7.5 mrem 0.108 Population Doses !

Total Body Dose 5.09E-02 man-rem Maximum Organ Dose (organ) 5.09E-02 man-rem (thyroid) ;

Population doses can be compared to the naturalbackground dose for the entire 50-mile population of about 95,400 man <em/ year (based on 90 miem/yr for naturalbackground).

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RadiologicalImpact Assessmant ;

Sequoyah Nuclear Plant January - December 1994 Page 12 of 17 i

Table 5 Doses from Liquid Effluents First Quarter Individual Doses Age Organ Dose Quarterly Percent of l ;

Group Limit Limit l Adult Total Body 2.5E-03 1.5 mrem <1%

Liver 3.2E-03 5 mrem <1%

Teen Total Body 1.7E-03 1.5 mrem <1%

Liver 3.2E-03 5 mrem <1%

Child Total Body 1.2E-03 1.5 mrem <1%

Liver 3.0E-03 5 mrem <1%

Average Riverflow past SQN (cubic feet per second): 74,840 Pooulation Doses Total' Body Dose 3.1E-02 man-rem Maximum Organ Dose (organ) 3.4E-02 man-rem (liver)

Population doses can be compared to the naturalbackground dose for the entire 50-mile population of about 95,400 man-rem / year (based on 90 miem/yr for naturalbackground).

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RadiologicalImpact Assessment Sequoyah Nuclear Plant January - Decernber 1994 -

Page 13 of 17 Table 6 ,

Doses from Uquid Effluents Second Quarter Individual Doses Age Organ Dose Quarterly Percent of Group Limit limit Adult Total Body 7.7E-03 1.5 mrem <1%

Liver 9.7E-03 5 mrem <1%

Teen Total Body 5.3E-03 1.5 mrem <1% )

Uver 9.8E-03 5 mrem <1% ;

Child Total Body 3.8E-03 1.5 mrem <1%

Liver 9.2E-03 5 mrem <1%

Average Riverflow past SQN (cubic feet per second): 52,340 Pooulation Doses Total Body Dose 2.0E-01 man-rem Maximum Organ Dose (organ) 2.1E41 man-rem (liver)

Population doses can be compared to the naturalbackground dose for the en/Ve 50-mile population of about 95,400 man-rem / year (based on 90 mrem /yr for naturalbackground).

RadiologicalImpact Assessment Sequoyah Nuclear Plant January- December 1994 Page 14 of 17 Table 7 Doses from Liquid Effluents Third Quarter Individual Doses Age Organ Dose Quarterly Percent of Group Limit Limit Adult Total Body 1.1 E-02 1.5 mrem <1%

Liver 1.4E-02 5 mrem <1%

Teen Total Body 6.8E-03 1.5 mrem <1%

Liver 1.4E-02 5 mrem <1%

Child Total Body 4.0E-03 1.5 mrem <1%

Liver 1.3E-02 5 mrem <1%

Average Riverflow past SQN (cubic feet per second): 38,313 Pooulation Doses Total Body Dose 1.9E-01 man-rem Maximum Organ Dose (organ) 2.7E-01 man-rem (thyroid)

Population doses con be compared to the naturalbackground dose for the entire 50-mile population of about 95,400 mantem/yeor (based on 90 mrem /yr fornaturalbackground).

RadiologicalImpact Assessm nt Sequoyah Nuclear Plant January - December 1994 Page 15 of 17 Table 8 Doses from Uquid Effluents Fourth Quader Individual Doses Age Organ Dose Quarterly Percent of Group Limit limit Adult Total Body 4.3E-03 1.5 mrem <1%

GIT 6.7E-03 5 mrem <1%

Teen Total Body 3.1 E-03 1.5 mrem <1% .

Liver 5.3E-03 5 mrem <1%

Child Total Body 2.5E-03 1.5 mrem <1% -

Liver 5.1 E-03 5 mrem <1%

Average Riverflow past SQN (cubic feet per second): 37,130 Pooulation Doses t

Total Body Dose 5.1E-02 man-rem Maximum Organ Dose (organ) 6.6E-02 man-rem (GIT)

Population doses can be compared to the naturalbackground dose fx the entire 50-mile population of about 95,400 man-rem / year (bosed on 90 miem/yr for naturalbackground).

1

RadiologicalImpact Assessment Sequoyah Nuclear Plant l January - December 1994 Page 16 of 17 !

Table 9 Total Dose from fuel Cycle First Second Third Fourth Dose Quarter Quarter Quarter Quarter Total Body or any Organ i (except thyroid)

Total body air submersion 3.12E-04 1.02E-03 5.03E-03 1.60E-03 ;

Critical oroon dose (air) 2.16E-03 3.03E-03 1.15E-02 8.07E-03 l Total body dose (liquid) 2.5E-03 7.7E-03 1.1 E-02 4.3E-03 :

Maximum organ dose 3.2E-03 9.8E-03 1.4 E-02 6.7E-03 i (liquid) l Direct Radiation Dose 0.0E-00 0.0E-00 0.0E-00 0.00E-00 i Total 8.2E-03 2.2E-02 4.2E-02 2.1 E-02 i Cumulative Total Dose (Total body or any other organ) mrem 9.3E-02 ,

AnnualDoselimit(mrem) 2.50E+01 i Percent of Limit <1% )

Thyroid Dose (mrem) !

Total body air submersion 3.12E-04 1.02E-03 5.03E-03 1.60E-03 I Thyroid dose (airborne) 2.16E-03 3.03E-03 1.15E-02 8.07E-03 )

Total body dose (liquid) 2.5E-03 7.7E-03 1.1 E-02 4.3E-03

]

Thyroid dose (liquid) 7.8E-04 3.2E-03 4.8E-03 2.2E-03 Direct Radiation Dose 0.0E-00 0.0E-00 0.0E-00 00603 Total 5.8E-03 1.5E-02 3.2E-02 1.6E-02 Cumulative Total Dose (Thyroid) mrem 6.9E-02 AnnualDoselimit(mrem) 7.50E4D1 Percent of Limit <1%

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RadiologicalImpact Assessment Sequoyah Nuclear Plant January - December 1994 Page 17 of 17

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JOINT PERCECTAGE FREQUENCIES OF WIND SPEED BY OIND D3RECTION FOR STABILITY CLASS A (DELTA T(=-1.9 C/100 M)

SEQUOYAH NUCLEAR PLANT JAN 1, 94 - MAR 31, 94 WINO WIND SPEED (MPH)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL DIRECTION 0.000 0.000 0.000 0.000 0.000 0.445 0.000 0.000 0.000 0.445 N

0.000 0.000 0.000 0.000 0.593 0.791 0.000 0.000 0.000 1.384 NNE NE 0.000 0.000 0.000 0.049 0.099 0.099 0.000 0.000 0.000 0.247 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 E

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 ESE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 SE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 SSE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 S

0.000 0.000 0.000 0.049 0.099 0.247 0.000 0.000 0.000 0.395 SSW 0.000 0.000 0.000 0.000 0.148 0.148 0.000 0.000 0.000 0.297 SW 0.000 0.000 0.000 0.000 0.049 0.049 0.000 0.000 0.000 0.099 WSW W 0.000 0.000 0.000 0.000 0.049 0.049 0.000 0.000 0.000 0.099 WNW 0.000 0.000 0.000 0.000 0.000 0.099 0.000 0.000 0.000 0.099 0.000 0.000 0.000 0.000 0.049 0.247 0.000 0.000 0.000 0.297 NW 0.000 0.000 0.000 0.000 0.049 0.395 0.000 0.000 0.000 0.445 NRW 0.000 0.000 0.000 0.099 1.137 2.570 0.000 0.000 0.000 3.806 SUBTOTAL TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2143 TOTAL HOURS OF STABILITY CLASS A 19 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS A 77 TOTAL NOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2023 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY: SEQUOYAH NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.25 AND 45.99 METERS WIND SPEED AND DIRECTION MEASURED AT 9.73 METER LEVEL DATE PRINTED: 25-APR-94 MEAN WIND SPEED = 8.34 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBCRS l

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JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTIOC FOR STABILITY CLASS C (-1.7< DELTA T(=-1.5 C/100 M)

SEQUOTAH NUCLEAR PLANT JAN 1, 94 - MAR 31, 94 WIND WIND SPEED (MPN)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL N 0.000 0.000 0.049 0.049 0.297 0.247 0.000 0.000 0.000 0.643 NME 0.000 0.000 0.049 0.247 0.544 0.099 0.000 0.000 0.000 0.939 NE 0.000 0.000 0.099 0.049 0.148 0.049 0.000 0.000 0.000 0.346 ENE 0.000 0.000 0.049 0.000 0.000 0.000 0.000 0.000 0.000 0.049 E 0.000 0.000 0.049 0.000 0.000 0.000 0.000 0.000 0.000 0.049 ESE 0.000 0.000 0.049 0.000 0.000 0.000 0.000 0.000 0.000 0.049 SE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 SSE 0.000 0.000 0.000 0.000 0.049 0.049 0.000 0.000 0.000 0.099 s 0.000 0.000 0.000 0.000 0.049 0.G99 0.000 0.000 0.000 0.148 SSW 0.000 0.000 0.000 0.099 0.049 0.049 0.000 0.000 0.000 0.198 SW 0.000 0.000 0.000 0.148 0.000 0.049 0.000 0.000 0.000 0.198 WSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 W 0.000 0.000 0.049 0.049 0.099 0.049 0.000 0.000 0.000 0.247 WNW 0.000 0.000 0.000 0.099 0.000 0.148 0.000 0.000 0.000 0.247 NW 0.000 0.000 0.000 0.049 0.198 0.148 0.000 0.000 0.000 0.395 NNW 0.000 0.000 0.000 0.000 0.247 0.148 0.000 0.000 0.000 0.395 SUBTOTAL 0.000 0.000 0.395 0.791 1.681 1.137 0.000 0.000 0.000 4.004 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2143 TOTAL HOURS OF STABILITY CLASS C 82 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS C 81 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2023 TOTAL NOURS CALM 0 METEOROLOGICAL FACILITY: SEQUOYAH NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.25 AND 45.99 METERS WIND SPEED AND DIRECTION MEASURED AT 9.73 METER LEVEL DATE PRINTED: 25-APR-94 MEAN WIND SPEED = 6.50 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

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l JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BT W2ND DIRECTION FOR l

STABILITY CLASS D (-1.5< DELTA T(=-0.5 C/100 M)

SEQUOYAH NUCLEAR PLANT JAN 1, 94 - MAR 31, 94 WIND WIND SPEED (MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL N 0.017 0.148 0.890 1.384 1.780 1.038 0.000 0.000 0.000 5.256 NNE 0.027 0.198 1.483 2.274 2.224 1.186 0.000 0.000 0.000 7.392 NE 0.017 0.000 1.087 0.692 0.000 0.049 0.000 0.000 0.000 1.846 ENE 0.009 0.148 0.395 0.049 0.000 0.000 0.000 0.000 0.000 0.602 E 0.004 0.049 0.198 0.000 0.000 0.000 0.000 0.000 0.000 0.251 ESE 0.006 0.049 0.346 0.000 0.049 0.000 0.000 0.000 0.000 0.451 SE 0.002 0.000 0.099 0.049 0.000 0.000 0.000 0.000 0.000 0.150 SSE 0.002 0.099 0.049 0.049 0.148 0.000 0.000 0.000 0.000 0.348 s 0.015 0.049 0.890 0.445 0.593 0.593 0.000 0.000 0.000 2.586 SSW 0.010 0.049 0.544 1.631 1.236 0.741 0.000 0.000 0.000 4.211 SW 0.013 0.049 0.791 1.137 0.939 0.445 0.000 0.000 0.000 3.375 WSW 0.008 0.049 0.445 0.049 0.198 0.000 0.000 0.000 0.000 0.749 W 0.002 0.000 0.099 0.198 0.247 0.099 0.000 0.000 0.000 0.644 WNW 0.002 0.000 0.148 0.395 0.297 0.346 0.049 0.000 0.000 1.238 NW 0.004 0.049 0.198 1.434 1.038 0.395 0.000 0.000 0.000 3.118 NNW 0.010 0.000 0.643 1.236 1.137 1.285 0.000 0.000 0.000 4.311 SUBTOTAL 0.148 0.939 8.304 11.023 9.886 6.179 0.049 0.000 0.000 36.530 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2143 TOTAL HOURS OF STABILITY CLASS D 818 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS D 739 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2023 TOTAL HOURS CALM 3 METEOROLOGICAL FACILITY: SEQUOYAH NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.25 AND 45.99 METERS WIND SPEED AND DIRECTION MEASURED AT 9.73 METER LEVEL DATE PRINTED: 25-APR-94 MEAN WIND SPEED = 5.23 NOTEt TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

' L A P t

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS E (-0.5< DELTA Tc= 1.5 C/100 M)

)

SEQUOYAN NUCLEAR PLANT JAN 1, 94 - MAR 31, 94 I

! WIND WIND SPEED (MPN)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL 1

DIRECTION 0.544 0.099 0.000 0.000 0.000 5,502 N 0.164 0.494 2.867 1.335 0.494 4.152 1.483 0.247 0.049 0.000 0.000 0.000 6.652 NNE 0.226 0.346 0.346 0.049 0.000 0.000 0.000 0.000 0.000 0.775 NE 0.034 0.000 0.148 0.000 0.000 0.000 0.000 0.000 0.000 0.156 ENE 0.007 0.000 0.049 0.000 0.000 0.000 0.000 0.000 0.000 0.052 E 0.002 0.049 0.049 0.000 0.000 0.000 0.000 0.000 0.000 0.104 ESE 0.005 0.049 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.052 SE 0.002 0.010 0.000 0.198 0.099 0.099 0.049 0.000 0.000 0.000 0.455 SSE 0.043 0.148 0.741 0.544 0.395 0.395 0.049 0.000 0.000 2.317 S

0.643 2.323 1.384 0.939 1.087 0.000 0.000 0.000 6.521

! SSW 0.144 0.089 0.445 1.384 0.989 0.346 0.247 0.000 0.000 0.000 3.500 SW 0.029 0.148 0.445 0.346 0.099 0.000 0.000 -0.000 0.000 1.067 WSW 0.148 0.297 0.049 0.099 0.049 0.000 0.000 0.000 3.664 W 0.022 0.598 WNW 0.005 0.000 0.099 0.297 0.148 0.049 0.000 0.000 0.000 0.297 0.692 0.544 0.148 0.198 0.000 0.000 0.000 1.926 i NW 0.048 0.060 0.297 0.939 0.989 0.445 0.198 0.000 0.000 0.000 2.927 NNW 0.890 3.559 14.731 8.107 3.510 2.422 0.049 0.000 0.000 33.267 SUBTOTAL TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2143 TOTAL HOURS OF STABILITY CLASS E 692 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS E 673 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2023 TOTAL HOURS CALM 18 METEOROLOGICAL FACILITY: SEQUOYAN NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.25 AND 45.99 METERS WIND SPEED AND DIRECTION MEASURED AT 9.73 METER LEVEL

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DATE PRINTED: 25-APR-94 MEAN WIND SPEED = 3.61 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS 7

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JOINT PERCENTAGE FCEOUENCIES OF WIND SPEED BY WIND DIRECTIOO FOR STABILITY CLASS F ( 1.5< DELTA T(= 4.0 C/100 M)

SEQUOYAH NUCLEAR PLANT JAN 1, 94 - MAR 31, 94 WIND WIND SPEED (MPH)

DIRECTION CA LM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL 1

l N 0.089 0.198 1.137 0.049 0.000 0.000 0.000 0.000 0.000 1.473 NNE 0.211 0.741 2.422 0.099 0.049 0.000 0.000 0.000 0.000 3.523 NE 0.066 0.445 0.544 0.000 0.000 0.000 0.000 0.000 0.000 1.055 ENE 0.007 0.099 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.105 E 0.003 0.000 0.049 0.000 0.000 0.000 0.000 0.000 0.000 0.053 ESE 0.003 0.049 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.053 SE 0.007 0.000 0.099 0.000 0.000 0.000 0.000 0.000 0.000 0.105 SSE 0.013 0.148 0.049 0.000 0.000 0.000 0.000 0.000 0.000 0.211 S 0.059 0.148 0.741 0.148 0.000 0.000 0.000 0.000 0.000 1.097 SSW 0.072 0.247 0.840 0.247 0.494 0.049 0.000 0.000 0.000 1.951 SW 0.069 0.247 0.791 0.247 0.000 0.000 0.000 0.000 0.000 1.354 WSW 0.010 0.000 0.148 0.000 0.000 0.000 0.000 0.000 0.000 0.158 W 0.000 0.000 0.000 0.049 0.000 0.000 0.000 0.000 0.000 0.049 WNW 0.003 0.000 0.049 0.049 0.000 0.000 0.000 0.000 0.000 0.102 NW 0.010 0.049 0.099 0.099 0.000 0.000 0.000 0.000 0.000 0.257 NNW 0.020 0.049 0.247 0.198 0.000 0.000 0.000 0.000 0.000 0.514 SUBTOTAL 0.643 2.422 7.217 1.186 0.544 9.049 0.000 0.000 0.000 12.061 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2143 TOTAL HOURS OF STABILITY CLASS P 252 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS F 244 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2023 TOTAL HOURS CA LM 13 METEOROLOGICAL FACILITY: SEQUOYAH NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.25 AND 45.99 METERS l WIND SPEED AND DIRECTION MEASURED AT 9.73 METER LEVEL DATE PRINTED: 25-APR-94 MEAN WIND SPEED = 2.39 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS t 1

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JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS A (DELTA T(=-1.9 C/100 M)

SEQUOYAH NUCLEAR PLANT APR 1, 94 - JUN 30, 94 WIND WIND SPEED (MPH) TOTAL 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=2e.5 DIRECTION CALM 0.6-1.4 1.5-3.4 0.093 0.000 0.000 0.000 0.000 0.093 N 0.000 0.000 0.000 0.000 4

0.606 1.258 0.652 0.000 0.000 0.000 2.563 NME 0.000 0.000 0.047 0.000 1.398 0.000 0.466 0.652 0.280 0.000 0.000 NE 0.000 0.000 0.000 0.047 0.000 0.047 0.000 0.000 0.000 0.000 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 E 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 ESE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 SE 0.000 0.000 0.000 0.047 0.000 0.000 0.047 0.000 0.000 0.000 SSE 0.000 0.000 0.000 0.140 0.000 0.000 0.093 0.047 0.000 0.000 5 0.000 0.000 0.000 0.000 0.233 0.000 0.000 0.047 0.186 0.000 0.000 SSW 0.000 0.000 0.000 0.513 0.000 0.000 0.093 0.233 0.186 0.000 SW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 WSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 W 0.000 0.000 0.000 0.000 0.000 WNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 NW 0.000 0.000 0.000 0.326 0.000 0.000 0.093 0.233 0.000 0.000 0.000 NNW 0.000 0.000 2.656 1.398 0.000 0.000 0.000 5.359 SUBTOTAL 0.000 0.000 0.047 1.258 2159 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 116 TOT AL HOURS OF STABILITY CLASS A 115 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS A 2146 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 0 TOTAL HOURS CALM t METEOROLOGICAL FACILITY: SEQUOYAH HUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.25 AND 45.99 METERS WIND SPEED AND DIRECTION MEASURED AT 9.73 METER LEVEL DATE PRINTED: 20-JUL-94 MEAN WIND SPEED = 6.65 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

q JOINT PERCENTAGE FREOUENCIES OF WIND SPEED BT WIND DIRECTION FOR STABILITY CLASS B (-1.9< DELTA T 1.7 C/100 M)

SEQUOYAH NUCLEAR PLANT APR 1, 94 - JUN 30, 94 WIND WIND SPEED (MPH)

CALM C.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL DIRECTION N 0.000 0.000 0.000 0.047 0.280 0.047 0.000 0.000 0.000 0.373 NNE 0.000 0.000 0.093 0.466 0.373 0.140 0.000 0.000 0.000 1.072 NE 0.000 0.000 0.233 0.606 0.140 0.000 0.000 0.000 0.000 0.979 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 E 0.000 0.000 0.0Al 0.000 0.000 0.000 0.000 0.000 0.000 0.000 ESE 0.000 0.000 0 400 0.000 0.000 0.000 0.000 0.000 0.000 0.000 SE 0.000 0.0JO C.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 SSE 0.000 0.000 0.000 0.000 0.186 0.000 0.000 0.000 0.000 0.186 S 0.000 0.000 0.000 0.047 0.047 0.000 0.000 0.000 0.000 0.093 SSW 0.000 0.000 0.000 0.186 0.513 0.000 0.000 0.000 0.000 0.699 SW 0.000 0.000 0.000 0.093 0.186 0.093 0.000 0.000 0.000 0.373 WSW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 WNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 NW 0.000 0.000 0.000 0.000 0.000 0.140 0.000 0.000 0.000 0.140 NNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 SUBTOTAL 0.000 0.000 0.326 1.445 1.724 0.419 0.000 0.000 0.000 3.914 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2159 TOTAL HOURS OF STABILITY CLASS B 84 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS B S4 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2146 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY: SEQUOYAH HUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.25 AND 45.99 METERS WIND SPEED AND DIRECTION MEASURED AT 9.73 METER LEVEL DATE PRINTED: 2 0 -Jt'L- 9 4 MEAN WIND SPEED = 5.64 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

m JOINT PERCENTAGE PREQUENCIES OF WIND SPEED BY WIND DIRECT 20N FOR STABILITY CLASS C (-1.7< DELTA T(=-1.5 C/100 M)

SEQUOYAH NUCLEAR PLANT APR 1 94 - JUN 30, 94 WIND WIND SPEED (MPH) 1.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL DIRECT' ION CALM 0.6-1.4 1.5-3.*

0.140 0.186 0.093 0.093 0.000 0.000 0.000 0.513 N 0.000 0.000 1.305 0.000 0.373 0.513 0.186 0.233 0.000 0.000 0.000 NNE 0.000 0.000 0.000 0.792 NE 0.000 0.000 0.419 0.326 0.047 0.000 0.000 0.186 0.093 0.000 0.000 0.000 0.000 0.000 0.280 ENE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 E 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 ESE 0.000 0.000 0.186 0.000 0.000 0.000 0.140 0.J47 0.000 0.000 0.000 SE 0.000 0.000 0.140 0.000 0.000 0.047 0.000 0.093 0.000 0.000 SSE 0.000 0.000 G.326 0.000 0.000 0.000 0.186 0.140 0.000 0.000 5 0.000 1.258 0.000 0.000 0.000 0.326 0.885 0.047 0.000 0.000 SSW 0.000 0.792 0.000 0.000 0.466 0.280 0.047 0.000 0.000 SW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 WSW 0.000 0.000 0.000 W 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 WNW 0.000 0.000 0.047 0.000 0.000 0.000 0.047 0.000 0.000 0.000 NW 0.000 0.000 0.093 0.000 0.047 0.000 0.000 0.047 0.000 0.000 0.000 NNW 0.000 2.237 1.77.5 0.513 0.000 0.000 0.000 5.732 SUBTOTAL 0.000 0.000 1.212 2159 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 125 TOTAL HOURS OF STABILIT* si'SS C 123 TOTAL HOURS OF VALID WIND DIhECTION-WIND SPEED-STABILITY CLASS C TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2146 0

TOTAL MOURS CALM METEC ROLOG ICAL FACILITY: SEQUOTAH NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.25 AND 45.99 METERS WIND SPEED AND DIRECTION MEASURED AT 9.73 METER LEVEL DATE PRINTED: 20-JUL-94 MEA 4 WIND SPEED = 5.05 NO'?E : TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

- .s

l JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BT WIND DIRECTION FOR STABILITY CLASS D (-1.5( DELTA Tt=-0.5 C/100 M) l SEQUOTAR NUCLEAR PLANT APR 1, 94 - JUN 30, 94 1

l WIND WIND SPEED (MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL N 0.000 0.093 0.652 1.165 0.606 0.280 0.900 0.000 0.000 2.796 NME 0.000 0.140 1.817 1.724 1.212 0.559 0.000 0.000 0.000 5.452 NE 0.000 0.047 1.351 0.652 0.326 0.047 0.000 0.000 0.000 2.423 0.000 0.000 0.326 0.000 0.000 0.000 0.000 0.000 0.000 0.326 ENE E 0.000 0.000 0.186 0.093 0.000 0.000 0.000 0.000 0.000 0.280 0.000 0.093 0.233 0.140 0.047 0.000 0.000 0.000 0.000 0.513 ESE ,

SE 0.000 0.000 0.373 0.140 0.093 0.000 0.000 0.000 0.000 0.606 l 0.000 0.000 0.559 0.326 0.140 0.093 0.001 0.000 0.000 1.118 l SSE 0.000 0.000 1.118 1.724 0.652 0.606 0.000 0.000 0.000 4.101 1 5

SSW 0.000 0.140 2.516 4.054 1.631 0.559 0.000 0.000 0.000 8.900 SW 0.000 0.047 0.652 2.004 0.559 0.466 0.000 0.000 0.000 3.728 WSW 0.000 0.000 0.326 0.047 0.047 0.047 0.000 0.000 0.000 0.466 W 0.000 0.047 0.047 0.047 0.000 0.000 0.000 0.000 0.000 0.140 WNW 0.000 0.047 0.186 0.140 0.047 0.000 0.000 0.000 0.000 0.419 0.000 0.047 0.093 0.186 0.186 0.000 0.000 0.000 0.000 0.513 NW NNW 0.000 0.000 0.466 0.373 0.559 0.047 0.000 0.000 0.000 1.445 SUBTOTAL 0.000 0.699 10.904 12.815 6.104 2.703 0.000 0.000 0.000 33.225 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2159 TOTAL HOURS OF STABILITY CLASS D 718 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS O 713 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2146 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITT: SEQUOYAH NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.25 AND 45.99 METERS WIND SPEED AND DIRECTION MEASURED AT 9.73 METER LEVEL DATE PRINTED: 20-JUL-94 MEAN WIND SPEED = 4.43 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UN Rot *N D E D NUMBERS

JOINT PERCENTAGE FREQUENCIES OF GIND SPEED OT CIND DIRECTION FOR STABILITY CLASS E (-9.5< DELTA T(= 1.5 C/100 M)

SEQUOYAH NUCLEAR PLANT APR 1, 94 - JUN 30, 94 CIND WIND SPEED (MPH) 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 1.212 0.280 0.140 0.000 0.000 0.000 5.023 N 0.037 0.606 2.749 4.928 2.703 0.885 0.746 0.093 0.000 0.000 0.000 NME 0.035 0.466 0.000 0.894 0.233 0.513 0.140 0.000 0.000 0.000 0.000 NE 0.008 0.000 0.000 0.141 0.002 0.093 0.047 0.000 0.000 0.000 0.000 ENE 0.000 0.000 0.000 0.141 0.002 0.093 0.047 0.000 0.000 0.000 E 0.000 0.330 0.140 0.186 0.000 0.000 0.000 0.000 0.000 ESE 0.004 0.000 0.000 0.188 0.002 0.000 0.186 0.000 0.000 0.000 0.000 SC 0.000 0.000 0.000 1.407 SSE 0.009 0.326 0.466 0.233 0.186 0.186 0.559 0.419 0.419 0.000 0.000 0.000 3.707 5 0.025 0.746 1.538 6.654 3.075 2.190 0.979 0.140 0.000 0.000 0.000 SSW 0.037 0.233 0.000 4.505 0.280 2.563 0.792 0.466 0.373 0.000 0.000 SW 0.032 0.000 0.000 1.316 0.011 0.280 0.746 0.233 0.047 0.000 0.000 Df S W 0.704 0.280 0.093 0.186 0.000 0.000 0.000 0.000 W 0.005 0.140 0.000 0.659 0.233 0.373 0.047 0.000 0.000 0.000 0.000 WNW 0.007 0.000 0.000 0.939 0.007 0.140 0.513 0.140 0.093 0.047 0.000 NW 0.000 1.408 t 0.140 0.746 0.419 0.093 0.000 0.000 0.000 NNW 0.010 6.943 3.495 1.398 0.000 0.000 0.000 32.945 SUBTOTAL 0.233 4.147 16.729 2159 '

TOTAL HOURS OF VALID STABILITY OBSERVATIONS 709 TOTAL HOURS OF STABILITY CLASS E 707 TOTAL HOURS 9F VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS E 2146 TOTAL NOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 5 TOTAL HOURS CALM METEOROLOGICAL FACILITY: SEQUOYAH NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.25 AND 45.99 METERS WIND SPEED AND DIRECTION MEASURED AT 9.73 METER LEVEL DATE PRINTED: 20-JUL-94 MEAN WIND SPEED = 3.30 NOTE: TOTALS AND SUBTOTALS ARC OBTAINED FROM UNROUNDED NUMBERS

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SEQUOTAH NUCLEAR PLANT JUL 1, 94 - SEP 30, 94 WIND WIND SPEED (MPH) 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL DIRECTION CALM 0.6-1.4 0.000 0.137 0.091 0.000 0.000 0.000 0.000 0.228 N 0.000 0.000 1.095 0.000 0.274 0.639 0.137 0.046 0.000 0.000 0.000 NNE 0.000 0.000 0.958 0.000 0.000 0.730 0.137 0.091 0.000 0.000 0.000 NE 0.000 0.137 0.000 0.000 0.137 0.000 0.000 0.000 0.000 0.000 ENE 0.000 0.228 0.000 0.000 0.137 0.091 0.000 0.000 0.000 0.000 E 0.137 0.000 0.000 0.091 0.000 0.046 0.000 0.000 0.000 0.000 ESE 0.000 0.228 0.000 0.000 0.046 0.091 0.091 0.000 0.000 0.000 SE 0.000 0.228 0.000 0.000 0.137 0.091 0.000 0.000 0.000 0.000 SSE 0.000 0.000 0.684 5 0.000 0.000 0.091 0.502 0.046 0.046 0.000 0.228 0.867 0.456 0.000 0.000 0.000 0.000 1.551 SSW 0.000 0.000 1.505 0.000 0.228 1.095 0.137 0.046 0.000 0.000 0.000 SW 0.000 0.000 0.046 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 WSW 0.091 0.046 0.046 0.000 0.000 0.000 0.000 0.000 W 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 WNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 NNW 3.695 1.095 0.137 0.000 0.000 0.000 7.117 SUBTOTAL 0.000 0.000 2.190 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2197 TOTAL HOURS OF STABILITY CLASS C 157 TOTAL HOURS OF VALID WIND DIRECTION-WIRD SPEED-STABILITY CLASS C 156 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2192 0

TOTAL HOURS CALM NETEOROLOGICAL FACILITY: SEQUOTAH NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.25 AND 45.99 METERS WIND SPEED AND DIRECTION MEASURED AT 9.73 METER LEVEL DATE PRINTED: 3-NOV-94 MEAN WIND SPEED = 4.28 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BT WIND DIRECTIO2 FOR STABILITT CLASS D (-1.5< DELTA T(=-0.5 C/100 M)

SEQUOTAR NUCLEAR PLANT JUL 1, 94 - SEP 30, 94 WIND WIND SPEED (MPR) 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL DIRECTION CALM 0.091 1.688 0.776 0.274 0.046 0.000 0.000 0.000 2.890 N 0.016 5.447 0.019 0.137 1.962 1.916 1.004 0.411 0.000 0.000 0.000 NNE 1.608 0.182 1.049 0.319 0.046 0.000 0.000 0.000 0.000 NE 0.011 0.597 0.004 0.000 0.411 0.182 0.000 0.000 0.000 0.000 0.000 ENE 0.735 0.091 0.502 0.137 0.000 0.000 0.000 0.000 J.000 E 0.005 0.734 0.004 0.060 0.502 0.182 0.046 0.000 0.000 0.000 0.000 ESE 0.000 1.149 0.008 0.137 0.821 0.182 0.000 0.000 0.000 0.000 SE 2.799 0.456 1.369 0.593 0.137 0.228 0.000 0.000 0.000 SSE 0.016 0.000 7.202 0.040 0.137 4.334 2.327 0.365 0.000 0.000 0.000 5 0.000 8.516 0.031 0.182 3.285 4.471 0.547 0.000 0.000 0.000 SSW 0.000 2.981 SW 0.015 0.091 1.642 1.004 0.228 0.000 0.000 0 000 0.411 0.182 0.046 0.000 0.000 0.000 0.000 0.688 WSW 0.004 0.046 0.137 0.046 0.046 0.000 0.000 0.000 0.000 0.275 W 0.002 0.046 0.413 0.046 0.274 0.046 0.046 0.000 0.000 0.000 0.000 WNW 0.003 0.321 0.000 0.228 0.046 0.046 0.000 0.000 0.000 0.000 NW O.002 0.368 0.003 0.000 0.319 0.046 0.000 0.000 0.000 0.000 0.000 NNW 1.642 18.932 12.454 2.828 0.684 0.000 0.000 0.000 36.724 SUBTOTAL 0.182 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2197 TOTAL HOURS OF STABILITT CLASS D 807 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS D 805 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2192 4

TOTAL HOURS CALM METEOROLOGICAL FACILITY: SEQUOTAH NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.25 AND 45.99 M3TERS WIND SPEED AND DIRECTION MEASURED AT 9.73 METER LEVEL DATE PRINTED: 3-NOV-94 MEAN WIND SPEED = 3.49 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

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JOINT PERCENTAGE FREQUERCIES OF WIED SPEED BT WIND DIDECTIO3 F02 STABILITY CLASS E (-0.5< DELTA Tt= 1.5 C/100 M) l SEQUOYAH NUCLEAR PLANT JUL 1, 94 - SEP 30, 94 l

WIND WIND SPEED (MPH) 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL DIRECTION Cyrt 0.414 1.688 5.429 0.958 0.137 0.000 0.000 0.000 0.000 8.625

, N 1.323 2.646 0.639 0.000 0.000 0.000 0.000 0.000 4.838 NNE 0.231 0.228 0.182 0.046 0.000 0.000 0.000 0.000 0.000 0.480 NE 0.024 0.386 0.021 0.228 0.137 0.000 0.000 0.000 0.000 0.000 0.000 ENE 0.091 0.228 0.000 0.000 0.000 0.000 0.000 0.000 0.338 E 0.019 0.290 0.016 0.228 0.046 0.000 0.000 0.000 0.000 0.000 0.000 ESE 1.298 0.066 0.867 0.274 0.091 0.000 0.000 0.000 0.000 0.000 SE 0.095 0.684 0.958 0.228 0.046 0.000 0.000 0.000 0.000 2.012 SSE 0.191 1.049 2.235 0.411 0.091 0.000 0.000 0.000 0.000 3.977 S

0.593 2.372 0.319 0.091 0.000 0.000 0.000 0.000 3.548 SSW 0.172 3.532 0.156 0.502 2.190 0.547 0.091 0.046 0.000 0.000 0.000 SW 0.074 0.274 1.004 0.091 0.091 0.000 0.000 0.000 0.000 1.534 WSW 0.072 0.593 0.639 0.091 0.046 0.000 0.000 0.000 0.000 1.440 W 0.622 0.029 0.274 0.228 0.091 0.000 0.000 0.000 0.000 0.000 WNW MW 0.045 0.319 0.456 0.000 0.000 0.000 0.000 0.000 0.000 0.821 1.186 1.460 0.137 0.091 0.000 0.000 0.000 0.000 3.028 NdW 0.154 10.128 20.464 3.650 0.684 0.046 0.000 0.000 0.000 36.770 SUBTOTAL 1.779 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2197 TOTAL HOURS OF STABILITY CLASS E 807 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS E 806 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2192 TOTAL HOURS CALM 39 AETEOROLOGICAL FACILITY SEQUOYAH NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.25 AND 45.99 METERS WIND SPEED AND DIRECTION MEASURED AT 9.73 METER LEVEL DATE PRINTED: 3-NOV-94 MEAN WIND SPEED = 2.09 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

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ENCLOSURE 3 SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL (REVISIONS 32, 33, 34, AND 35) l I

\

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8 58 941028' 8'60 l

SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCUI.ATION MANUAL Revision 35 l

Prepared By: -

o hks/'4 Date 80/ Zs/9<l x w , vt Sponsor: Date /o c /

PORC Approval: Date

) I Effective Date: If/zi,/9d

SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL REVISION LOG (Page 1 of 1)

Revision Approval Date Revision Approval Date Effective Date Original 2/29/80' Revision 19 3/30/88' ODCM Revision 1 4/15/80' Revision 20 7/19/88 3 i Revision 2 10/7/80' Revision 20A 12/14/88 3 3

Revision 3 11/3/80,2/10/81, Revision 21 2/15/89 4/8/81, 6/4/81 2 Revision 4 10/22/81,11/28/81, Revision 22 6/1/89' 4/29/82,11/22/82 2 3

Revision 5 10/21/82 Revision 23 6/28/89,9/15/89* j 3

Revision 6 1/20/83 Revision 25 11/2/90,4/24/91 3 l Revision 7 3/23/83' Revision 26 1/17/92* 3/17/92 !

Revision 8 12/18/83' Revision 27 4/15/92' )

Revision 9 3/7/84 3 Revision 28 9/22/92' 12/1/92 3

Revision 10 4/24/84 Revision 29 3/30/93' Revision 11 8/21/84 Revision 30 9/30/93 3 Revision 12 2/19/85 3 Revision 31 10/13/93 3 Revision 13 12/02/85 3 Revision 32 11/29/93 3 1/1/94 Revision 14 4/14/86' Revision 33 2/25/94^

3 Revision 15 11/5/86' Revision 34 4/29/94 5/15/94 Revision 16 1/16/87 3 Revision 35 10/26/94' 11/21/94 Revision 17 10/28/87 3 Revision 18 1/5/88 3 l

' Low power license for Sequoyah Unit 1.

RARC Meeting Date.

Date approved by RARC Chairman.

Revision 23 implements the Nuclear Data Effluent Management Software. This ODCM ,

revision and the software will be implemented concurrently on October 9,1989. Releases made during the month of October prior to the software implementation will be backfitted to comply with this revision.

Revision 26 was recommended for approval by the SON RARC at the October 2,1991 meeting. The revision date is January 17,1992. The final implementation date for Revision 26 will be March 17,1992.

PORC Meeting Date.

i l

SON ODCM Revision 35 Page 1 of 163 I

INTRODUCTION . . . . - _6 ;

1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS.. . .8 1/2.0 APPLICABILITY.. .

. .8 1/2.1 INSTRUMENTATION.. . .. .10 1/2.1.1 RADIOACTIVE LIQUID EFFLUE?U MONITORING INSTRUMEPHATION.. .10 TABE I.1 1 RADIOACTIVE LIQUID EFTLUErfr MONITORING INSTRUMENTATION.. .I1 TABa 2.1 1 - RADIOACTIVE LIQUID EFFLUENT MONTTORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS. . .13 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION. .15 TABa 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMEl(TATION.. .16 TABU 2.12 RADIOACTIVE GASEOUS EFFLUENT MONTTOPJNG INSTRUMENTATION SURVEILLANCE REQUIREhENTS. .18 1/2.2 RADIOACTIVE EFFLUEPUS.. . 20 1/2.2.1 LIQUID EFFLUENTS.. . . . 20 1/2.2.1.1 CONCENTRATION.. . 20 TABa 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM. . 21 1/2.2.1.2 DOSE.. . . . . . . 24 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM.. . . . . 25 1/2.2.2 GASEOUS EFFLUENTS... . 26 1/2.2.2.1 DOSE RATE., . . .. . 26 TABU 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM. . . 27 1/2.2.2.2 DOSE - NOBLE GASES . . 30 1/2.2.2.3 DOSE -I.131.1-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH i HALF-LIVES GREA'IT.R THAN EIGHT DAYS.. . . 31 1/2.2.2.4 GASEOUS RADWASTE TREATME?TT.. . . 32 1/2.2.3 TOTAL DOSE.. . .. . 33 1/2.3 RADIOLOGICAL ENVIRONME?UAL MONITORING . . 34 1/2.3.1 MONITORING PROGRAM.. . 34 i

TABa 2.3 1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING l PROGRAM . . . 36 i TABE 2.3 2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN l ENVIRONMEffTAL SAMPLES.. . 38 TABU 2.3-3 MAXIMUM VALUES FOR ' LEE LOWER LIMITS OF DETECTION ~ . . 39 4 1/2.3.2 LAND USE CENSUS.. , . 41 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM ... . . 43 BASES -. - -.-- ~~ -. .~ - 45 INSTRUMEtTTATION . . 45 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.. . . 45 I

l l

SQN ODCM Revision 35 Page 2 of 163

( .

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! 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.. . . . . . 45 l

1/2.2 RADIOACTIVE EFFLUENTS.. . .. 45 1/2.2.1.1 CONCENTRATION.. . .

... . . 45 1/2.2.1.2 DOSE.... . . .. 45 1/2.2.1.3 LIQUID RADWASTE 'IREATMENT SYSTEM.. . .. . - 46 1/2.2.2.1 DOSE RATE... . . .. .. . . .. . 46 1/2.2.2.2 DOSE - NOBLE GASES . .. . . . . . . . 47 I 1/2.2.2.3 DOSE -IODINE-131, IODINE-133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM WITH HALF. LIFE GREATER THAN EIGHT DAYS. . .. . 47 1/2.3.2.4 GASEOUS RADWASTE TREATMENT SYSTEM.. . . . . 48 )

1/2.2.3 TOTAL DOSE.. . . . . . . . . . . 48 I

1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING . .. .. . . . . . 49 1/2.3.1 MONITORING PROGRAM... . . . . . . =49 1/2.3.2 LAND USE CENSUS., . . . . . . . .. . 4 9 1/2.3.3 D(IERLABORATORY COMPARISON . .... 4 9 3.0 DEFINITIONS -. _._ 51 3.1 CHANNEL CAUBRAT]ON.. .. . . .. 51 3.2 CHANNEL CHECK. . .. . 31 3.3 CHANNEL FUNCT10NAL TEST.. .. . .. . . 51 l 3.4 CONTROLLED AREA . .. . .. . . .51 3.5 DOSEEQUIVALENTl-131.,. l

. . . . . . . . 31 3.6 GASEOUSRADWASTE TREA TAfENTSYSTEki.. . S1 3.7MEAfBER(S) OF THE PUBUC.. . . . . .. . 52 3.8 OPERABLE - OPERAB1UTY... . .. .. . . . 32 3.9 Af0DE . .. 32 3.10 PURGE- PURGING.. . .. . _$2 3.11 RATED THERAfAL POWER.. . -; 32 3.12 RESTRICTED AREA _ .. . .. 32 3.13 S/TEBOUNDARY . 52 3.I4 SOURCDSENSOR CHECK.. . . .. . . 32 3.15 UNRESTRICTEDARE4/ BOUNDARY.. . . . 53 3.16 VENTILA TION EXHA UST TREA TAfENTSYSTEM.. . 33 3.17 VENTING.. .. . . .. 53 .

1 TABI E 3.I FREQUENCY NOTATION.. . . . . 54 FIGURE 3.1 UNRESTRICTED AREA BOUNDARY... . 55 5.0 ADMINISTRATIVE CONTROIJ!i _ 58 5.1 ANNUAL RADIOLOGICAL ENVIRONMEl(TAL OPERATING REPORT . 58 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT;_ . ... .. 58 1 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES = .. . _60 l 5.4 SPECIAL REPORTS. . 60 SECTION 6.0 LIQUID EFFLUENTS .- 62 RELEASE POthTS., . 62 i

6.1 LIQUID RELEASES.. . . .. _ _63 6.1.1 Pre-Release Analysts.. . .63 6.1.2 Epluent Concentration Limits (ECL)-Sum ofthe Ratios.. ;63 6.1.3 Post-Release Analysis.. . ... . ;64 ;

6.2 INSTRUMEl(T SETPOINTS -- _ 65 i

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SQN ODCM Revision 35 Page 3 of 163, 6.2.1 Process Discharge PointMonitor Setpoints (0-RE-90-133,134,140,141).. . . . 63 6.2.2 Release Point Monitor Setpoints (0-RM-90-122; 0-RM-90-223; 0-RM-90-212,-

1,2-RM-90-20,121)... . .. ;63 6.2.3 Batch Release Point Monitor Setpoint . . . . . . . . . 63 6.3 CUMULATIVE LIQUID EFTLUENT DOSE CALCULATIONS . .. . . . . 67 6.3.1 Monthly Dose Calculations.. .. .. . . . . .68 l 6.3.2 Cumulative Doses.... . . . . .

. 68 6.3.3 Comparison to Limits. . . . . .. . . 68 6.4 LIQUID RADWASTE TREATMENT SYSTEM . . . . . . . . . . 69 6.5 DOSE PROJECTIONS. . . . . . . . _70 6.6 QUARTERLY DOSE CALCULATIONS . . .. . . . . 71 6.6.1 WA TER INGESTION.. . . . . . 71 6.6.2 FISHINGESTION.... . . .. . .. . . . . . . .. . .. 72 6.6.3 SHOREUNERECREATION.. . . . . . . . . . . 72 6.6.4 TOTAL MAXIMUMINDD1 DUAL DOSE.. . . ..... . . . 73 6.6.5 POPULA TION DOSES : . _ 73 6.7 LIQUID DOSE FACTOR EQUATIONS . . =76 6.7.1 WA TER INGESTION... . .. .. .. . .76 6.7.2 FISHINGESTION. . .. . . .. . 76 6.7.3 SHOREUNE RECRE4 TION... .

. 76 TABU 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS =77 TABU 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA.. . 78 TABU 6.3 DOSE CALCULATION FACTORS.. . .. .... 81 TABU 6.4 INGESTION DOSE FACTORS . 83 TABU 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH : . .. 91 TABU 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND .92 FIGURE 6.1 LIQUID EFFLUENT RELEASE POINTS . . _94 FIGURE 6.2 LIQUID RADWASTE SYSTEM: . . . . . . . . . .95 <

SECTION 7.0 GASEOUS EFFLUENTS - ._ _ _ 97 RELEASE POINTS DESCRIPTION... . . . . . . _97 7.1 INSTRUMENT SETPOINTS . . . 98 7.1.1 Release Point Monitor Setpoints (1,2-RM-90-130,-131, 0-RM-90-118) .. ... 98 7.1.1.1 Containment Purge EfuentMonitors (1,2-Rhi-90-130,-131).. . .. :98 7.1.1.2 Waste Gas Decay Tank EfuentMonitor (0-RM-90-118)- . . 98 7.1.2 Discharge Point Monitor Setpoints (1,2-RE-90-400, 0-RM-90-101, 0-RM-90-132, 1,2-RM-90-119) . ,99 7.1.3 Discharge Point Epuent Monitor Default Setpoints : . 100 7.1.3.1 Shield Building Vents (1,2-RE-90-400), Auxiliary Building Vent (0-RM-90-101), and Service Building Vent (0-RM-90-132). . . .. . 100 7.1.3.2 Condenser Vacuum Exhaust Vent (1,2-RM-90-119) . .100 7.2 GASEOUS EFFLUENTS - DOSE RATES. . 101 7.2.1 (Deleted).- . . . -101 7.2.2 RELEASE S4MPUNG.. ... .101 7.2.3 NOBLE GASDOSERA TFL .... . .. 101 7.2.3.1 TotalBody Dose Rate _ .101 7.2.3.2 Skin Dose Rate . . . 102 7.2.4 1-131,1-133 TRITIUM AND ALL RADIONUCUDESIN PARTICUIA TE FORM M7TH HALF-UVES OF GRE4 TER THAN 8 DA YS - ORGAN DOSE RA TE - .. 103 7.3 DOSE - NOBLE GASES - .104 7.3.1 Gamma dose to air.. .- . . -104

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SON ODCM Revision 35 Page 4 of 163 7.3.2 Beta dose to air... . . . . .. . . . . . . . . . . . . . . . . .. . . 104 7.3.3 Cumulative Dose - Noble Gas.. . .. . . . 103 7.3.4 Comparison to Limits... . . . . . . . . . .. . ... .. 103 7.4 DOSE DUE TO I-131,1-133 TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WIni HALF-LIVES OF GREATER THAN 8 DAYS , . . . . . .. 106 7.4.1 Organ dose Calculation.. . . . . . . . . . 106 7.4.2 Cumulative Doses.. . . .107 7.4.3 Comparison to Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .107 7.5 DOSE PROJECTIONS. .. . . . .. . . . . . . . . .108 7.3.1 GASEOUSRADWASTE TREATMENTSYSTEMDESCRIPTION.... .. . . . . . . .. 108 7.6 QUARTERLY DOSE CALCULATIONS . . . . . . . . . . . . . . . ;109 7.6.1 NOBLE GAS- GAhotA AIR DOSE.. .. . . . . .. . . . .109 7.6.2 NOBLE GAS- BETA AIR DOSE.... , . .. . . . . . . . . .109 7.6.3 MD10 LODINE. PARTICULATEAND TRITIUM-MAXIMUMORGANDOSE.. .. . ...I10 7.6.4 POPULATIONDOSES.. . ...... ... . . . . . . . ..Ii1 7.6.5 REPORTING OFDOSES... . ... . . .. ... . ,1J2 7.6.6 DOSE TO A MEMBER OF THE PUBl2CINSIDE THE UNRESTRICTED AREA BOUNDARY.. IJ2 7.7 GASEOUS RELEASES - Dose FAcTosts . . . . .113

7. 7.1 PASTURE GMSS-CO WMOA T MILK INGESTION DOSE FA CTORS... . -113

7. 7.2 SmRED FEED-COW /GOA T-M/LK JNGESTION DOSE FA CmRS... . . . . ,.I14 7.7.3 PASTURE GMSS-BEEFJNGESTIONDOSEFACTORS... . .. . . ... ..I13

7. 7.4 STORED FEED-BEEFINGESTION DOSE FA CTORS . .. . . .I16 7.7.3 FRESHLEAFY VEGETABLE 1NGESTIONDOSEFACMRS.. .. .I17

7. 7.6 STORED VEGETABLEINGESTIONDOSEFACTORS-- . . . . . . ... .. I18 7.7.7 TRITIUM-PASTURE GMSS-COWMOAT-MILKDOSEFAC70R., .. ... .. -119

7. 7.8 TRIT 1UM. STORED FEED-COWMOA T-MILK DOSE FA CTOR.. .. . . . 119 7.7.9 TRITIUM-PASTURE GMSS-BEEFDOSE FAC70R... . . . . . . .. . 120 7.7.10 TRIT 1UM. STORED FEED-BEEFDOSE FA CTOR .. ... .. 120 7.7.11 TRITIUM-FRESH LE4FT VEGETABLESDOSEFACTOR.. . .. . . . .. ..I21 7.7.12 TRITIUM-STORED VEGETABLESDOSEFAC70R.. . .122 7.7.13 INHALATION DOSE FAC70RS.... . . . . . . . . . . . . . . ..122 7.714 GROUND PLANEDOSEFACTORS . .. .. .. .I22 7.8 DISPERSIONMETHODOLOGY.. .... . .. . . . ... I23 7 8.I AIR CONCENTRATION = .123 7.8.2 RELATIVE CONCEN7 RAT 10N= . .. . . . ...... ....I24 7.8.3 RELATIVEDEPOSITION .. .I24 TABLE 7.1 SQN OFFSITE RECEITOR LOCATION DATA.. . . .. ..I15 TABLE 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES * - -126 TABa 7.3 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES.; 133 ,

TABLE 7.4 SECTOR EEMENTS CONSIDERED FOR POPULATION DOSES ..... .. 134 l TABLE 7.5 POPULATION WITHIN EACH SECTOR ELEMENT = . ... 135 TABU 7.6 INHALATION DOSE FACIDRS . .. .136 FIOUltE7.1 GASEOUS EFFLUENT RELEASE POINTS-- . 144 FIGUltE7.2 AUXILIARY AND SHIELD BUILDING VENTS (DETAIL).. .. . . . . .145 ;

FIGUltE 7.3 GASEOUS RADWAS7E TREATMENT SYS7EM . . .146 j FIOUltE 7.4 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES .. . . . _147 ;

FIGUltE 7.5 VERTICs J STANDARD DEVIATION OF MA7ERIAL IN A PLUME.. . 148 FIGUltE 7.6 RELATI\ E DEPOSITION FOR GROUND LEVEL RELEASES __ 149 SECTION 3.0 TOTAL DOSE . 151

SQN ODCM Revision 35 Page 5 of 163 8.1 ANNUAL MAXIMUM INDIVIDUAL DOSES -TOTAL REPORTED DOSE.. . .. 151 SECTION 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM _ 153 9.1 MONITORING PROGRAM == . . . . . . . . . . . .153 9.2 DETECTION CAPABILITIES.. . . . . . . . . . . . . .. 153 9.3 LAND USE CENSUS.. . . . . . . . . .153 l

9.4 INTERLABORATORY COMPARISON PROGRAM = . . . . . . . . .153 TABLE 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.. . . 154 TABLE 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS . . . . . . .158 TABLE 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS.. . . . 159 FIGURE 9.1 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THE PLANT.. .. . . . . .161 l FIGURE 9.2 ENVIRONMENTAL MONITORING LOCATIONS FROM ONE TO FIVE MILES l FROM THE PLANT.. ... . . 162 FIGURE 9.3 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN FIVE l MILES FROM THE PLANT.. . . . ;163 I

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SQN ODCM Revision 35 Page 6 of 163 INTRODUCTION The Sequoyah Nuclear Plant (SON) Offsite Dose Calculation Manual (ODCM) is a supporting document of the SON Technical Specifications. The ODCM is divided into two major parts. The first part of the ODCM contains: 1) Radioactive Effluent Controls required by Section 6.8.4.f of the SON Technical Specifications; 2) Radiological 35 Envircamental Monitoring Controls required in Section 6.8.4.g of the SON Technical 35 Specifications; 3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by SON Technical Specifications 6.9.1.6 and 6.9.1.8; and,4) Administrative Controls for the ODCM requirements.

The second part of the ODCM contains the methodologies used to: 1) calculate offsite j doses resulting from radioactive gaseous and liquid effluents; 2) calculate gaseous and !

liquid effluent monitor Alarm / Trip setpoints; and,3) conduct the Environmental Radiological Monitoring Program.

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The SON ODCM will be maintained for use as a reference guide on accepted methodologies and calculations. Changes in the calculation methods or parameters will i be incorporated into the ODCM in order to assure that the ODCM represents the present l I

methodology in all applicable areas. Any licensee initiated ODCM changes will be l l

implemented in accordance with SON Technical Specification 6.14 and ODCM l

Administrative Control 5.3. I l

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SECTIONS 1.0 AND 2.0 CONTROLS AND SURVEILLANCE REQUIREMENTS l

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SQN ODCM Revision 35 Page 8 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.0 APPLICABILITY CONTROLS l

1.0.1 Compliance with the Controls contained in the succeeding controls is required during the j OPERATIONAL MODES or other conditions specified therein; except that upon failure to i meet the Control, the associated ACTION requirements shall be met. !

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

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

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

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

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

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

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SQN ODCM ,

Revision 35 Page 9 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS ,

l 1/2.0 APPLICABILITY SURVEILLANCE REQUIREMENTS 2.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other f

conditions specified for individual Controls unless otherwise stated in the individual Surveillance Requirement.

2.0.2 Each Surveillance Requirement shall be performed within the specified time interval with f a maximum allowable extension not to exceed 25% of the specified surveillance interval. 1 l

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

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

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SON ODCM Revision 35 Page 10 of 163 1/2 CONTROLS AND SURVElLLANCE REQUIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.1 RADIOACTIVE L.lQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.1 in accordance with SON Technical Specification 6.8.4.f.1, the radioactive liquid effluent 35 monitoring instrumentation channels shown in Table 1.1 1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of ODCM Control 1.2.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the methodology and parameters in ODCM Section 6.2.

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

ACTION:

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

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

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

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l SQN ODCM Revision 35 Page 11 of 163 r

Table 1.1-1 RADIOACTIVE UQUID EFFLUENT MONITORING INSTRUMENTATION (Page 1 of 2)

Minimum instrument Channels Action .

OPERABLE I

1. Gross Radioactivity Monitors Providing Automatic Termination of Release

a. Liquid Radwaste Effluent Line (0-RM-90-122A) 1 30

b. Steam Generator Blowdown Effluent Line 1 31 (1,2-RM-90-120A,121 A) i

c. Condensate Demineralizer Effluent Line 1 30 i (0-RM-90-225A) ]

2. Gross Radioactivity Monitors Providing Automatic Termination of Release

a. Essential Raw Cooling Water Effluent Header" 1 32 (0-RM-90-133A,-134A.-140A,-141 A)

b. Turbine Building Sump Effluent Line 1 32 (0-RM-90-212A (LOCAL))

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line 1 33 (0-F1-77-42)

b. Steam Generator Blowdown Effluent Line 1 33 (1,2-FI-15-44, 1,2-FR-15-25, 1,2-F-15-43)

c. Condensate Demineralizer Effluent Line 1 33 (0-FR-14-456, 0-F-14 185, 0-F-14-192)

d. Cooling Tower Blowdown Effluent Line 1 33 (0-FT-27-175 or 0-LS-27-225))

4. Tank LevelIndicating Devices

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

b. Steam Generator Layup Tank * (LOCAL FLOAT) 1 34

5. Continuous Composite Sampler and Sample Flow Monitor i

a. Condensate Demineralizer Regenerant Effluent Line 1 35 (MI-14-466)

Required when connected to the secondary system

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

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SQN ODCM Revision 35 Page 12 of 163 l I

l Table 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION l (Page 2 of 2) TABLE NOTATION j I

ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that t prior to initiating a release: j

a. At least two independent samples are analyzed in accordance with ODCM !

Control 2.2.1.1, and j l

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

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

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than or equal to 0.01 Ci/g DOSE EOUlVALENT l-131,

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 pCilg DOSE EQUIVALENT l-131.

ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for gross radioactivity gamma at a limit of detection of at least 10-7 Ci/ml.

ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves may be used to estimate flow.

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

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

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SON ODCM Revision 35 Page 13 of 163 a

Table 2.1 RADIOACTIVE LIQUID EtYLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 1 of 2)

SOURCE / CHANNEL CHANNEL CHANNEL SENSOR CALIBRA- FUNCTIONAL Instrument CHECK CHECK TION TEST

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

a. Liquid Radwaste Effluent Line D P R(3) Q(1)

(0-RM-90-122A) lN

b. Steam Generator Blowdown Effluent D M R(3) Q(5)

Line (1,2-RM-90-120A 121 A) l 54 C. Condensate Demineralizer Effluent D M R(3) O(5)

Line (0-RM-90-225A) l SV

2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIEN 1LARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Essential Raw Cooling Water Effluent D R(3) Q(2)

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

b. Turbine Building Sump Effluent Line D M R(3) Q(2)

(0-RM-90-212A (LOCAL)) l3Y

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line D(4) N.A. R Q (0-F1-77-42) l3Y

b. Steam Generator Blowdown Effluent D(4) N.A. R Q Line (1,2-FI-15-44,1.2-F R-15-25, 1,2-F- 5-43) l5/

C. Condensate Demineralizer Effluent _O(4) N.A. R Q Line ,

(0-FR 14-456.0-F 14-192,0-F-14-185) lN !

d. Cooling Tower Blowdown Effluent Line D(4) N.A. R Q (0-FT 27-175,0-L 27-225)

4. TANK LEVEL INDICATING DEVICES

a. Condensate Storage Tank D* N.A. R Q (0-LI-2-230, 0-L-2-233)

b. Steam Generator Layup Tank D* N.A. R N.A. ;

(LOCAL FLOAT) l

5. CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR

a. Condensate Demineralizer Regenerant P N.A. R N.A.

_ Effluent Line (0-FI-14-466) i

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Page 14 of 163 Table 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 2 of 2) TABLE NOTATION During liquid additions to the tank.

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

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

2. Circuit failure. ,

3. Downscale failure. l (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm ;

annunciation occurs if any of the following conditions exists; i

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Downscale failure.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference ,

standards certified by the National Bureau of Standards or using standards that have been .

obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration shall be used.

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(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release, i CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on dayr. on which continuous periodic, or batch releases are made.

(5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions

. occur:

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

2. Circuit failure.

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

1. Downscale failure.

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1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS !

1/2.1 INSTRUMENTATION <

1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.2 in accordance with SQN Technical Specification 6.8.4.f.1, the radioactive gaseous effluent l monitoring instrumentation channels shown in Table 1.1-2 shall be OPERABLE uth their l 35 alarm / trip setpoints set to ensure that the limits of ODCM Control 1.2.2.1 are not l exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the methodology and parameters in ODCM Section 7.1.

APPLICABILITY: As shown in Table 1.12.

ACTION

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required above, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, declare the channelinoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE take the action shown in Table 1.1-2. Exert best efforts to retum the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Report why the inoperability could not be corrected within 30 days.

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

SURVEILLANCE REQUIREMENTS 2.1.2 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK SOURCE CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2.12.

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SQN ODCM Revision 35 Page 16 of 163 Table 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Page 1 of 2)

Minimum Channels Instrument OPERABLE Applicability Action

1. WASTE GAS DISPOSAL SYSTEM

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

~

40

b. Effluent System Flow Rate Measuring ~ 35 1 41 Device (0-FI-77-230)

2. CONDENSER VACUUM EXHAUST SYSTEM

a. Noble Gas Activity Monitor (1,2-RM40-119) 1

~

42 35

b. Flow Rate Monitor (1,2-F 2 256,257) 1

~

41 (1,2-FI-2-101,148,191)

3. SHIELD BUILDING EXHAUST SYSTEM

a. Noble Gas Activity Monitor 1" ~

43 35 (1,2-RE-90-400A (Low Range))

b. lodine Sampler (1,2-RE-90-402) 1

~

44

c. Particulate Sampler (1,2-RE-90-402) 1

~

44

d. Flow Rate Monitor (1,2-F1-90-400) 1" ~

41,43

e. Sampler Flow Rate Monitor (1,2-RI-90-400 ~

l35 1 41 or 1,2-F1-90-400A) b

4. AUXILIARY BUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor (0-RM-90-1018) 1 42

b. lodine Sampler (0-RE-90-101) 1 44 N

c. Particulate Sampler (0-RE-90-101) 1 44

d. Flow Rate Monitor ( 0-F 30-5174A) 1 41

e. Sampler Flow Rate Monitor (0-FIS-90-101)

l35 1 41

5. SERV!CE BUILDING VENTILATION SYSTEM

a. Nob!e Gas Activity Monitor (0-RE-90-1328)

b. Feow Rate Monitor ( 0-F 90-5132A) 1 1

42 41 g

SON ODCM Revision 35 Page 17 of 163 ,

Table 1.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Page 2 of 2) TABLE NOTATION At all times.

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

- - During exhaust system operation.

ACTION 40 - With the number of channels OPERABLE less than required by the Minimum ,

Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release:

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

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

ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 42 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for noble gas gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 43 - Flow Rate Inocerable - With any inoperable flow element on a discharge pathway where a fan is operating (Purge A, Purge B, ABGTS, or EGTS), effluent release may continue provided: (a) " Low Rng" cn RI 90-400 is selected instead of "Eff"; and l (b) at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated instrument malfunction is verified not annunciated; and (c) a reading from " Low Rng" on RI-90-400 is obtained at least 35 ,

once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . 1 Radiation Monitor inooerable - With the low range channel inoperable, effluent releases may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for noble gas gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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

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SON ODCM Revision 35 Page 18 of 163 Table 2.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS '

(Page 1 of 2)

MODE in Which SOURCE / CHANNEL CHANNEL Surveil. f CHANNEL SENSOR Call 3RA- FUNCTIONAL lance instrument CHECK CHECK TION TEST Required

1. WASTE GAS DISPOSAL SYSTEM

a. Noble Gas Activity Monitor P P R(3) Q(1)

l (0-RM-90-118A) 3M l

b. Flow Rate Monitor D N.A. R Q ~*

l (0-F1-77-230) 1

2. CONDENSER VACUUM EXHAUST SYSTEM I

a. Noble Gas Activity Monitor D M(4) R(3) Q(2)

(1,2-RM-90-119)

b. Flow Rate Monitor D N.A. R Q *

(1,2-F-2-256,257, 1,2-F1-2-101,148,191)

3. SHIELD BUILDING EXHAUST SYSTEM

a. Noble Gas Activity Monitor D M R(3) . Q(2)

~

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

b. lodine Sampler W N.A. N.A. N.A. ~

(1,2-RE-90-402)

C. Particulate Sampler W N.A. N.A. N.A. ~

(1,2-RE-90-402)

d. Flow Rate Monitor D N.A. R Q ~

(1,2-F1-90-400, ) l3k

e. Sampler Flow Rate Monitor D N.A. R Q ~

l (1,2-RI-90-400 or 1,2-F1-90-400A) l3M

4. AUXILIARY BUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor D M R(3) Q(2)

(0-RM-90-1018)

b. lodine Sampler (0-RE-90-101) l35 W N.A. N.A. N.A.

C. Particulate Sampler W N.A. N.A. N.A. *

(0-RE-90-101) 3h

d. Flow Rate Monitor D N.A. R Q *

(0-F-30-5174A)

e. Sampler Flow Rate Monitor D N.A. R Q *

(0-FIS-90-101)

5. SERVICE BUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor D M R(3) Q(2)

(0-RE 90-1328) l37,j l

b. Flow Rate Monitor D N.A. R Q *

( 0-F-90-5132A) l34

P SON ODCM Revision 35 l Page 19 of 163 Table 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 2 of 2) TABLE NOTATION At all times.

During shield building exhaust system operation.

During waste gas releases.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions !

exists: !

1. Instrument indicates measured levels above the alam1/ trip setpoint.

2. Circuit failure.

3. Downscale failure.

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

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Downscale failure.

For the auxiliary building ventilation system, at least once every 18 months, the CHANNEL FUNCTIONAL TEST shall also demonstrate automatic isolation of this pathway if the following condition exists:

Instrument indicates measured levels above the alarm / 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 permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) The SOURCE / SENSOR CHECK for the Condenser Vacuum Exhaust Monitor will be accomplished using an LED sensor check source in lieu of a radioactive source.

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SQN ODCM Revision 35 Page 20 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.1 CONCENTRATION CONTROLS 1.2.1.1 In accordance with SON Technical Specifications 6.8.4.f.2 and 3, the concentration of l35 radioactive material released to UNRESTRICTED AREAS (see Figure 3.1) shall be limited

{

at all times to ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 32 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2X104 Ci/ml total activity.

& PLICABILITY: At all times.

ACTION:

a. With the concentration of radioactive material released to UNRESTRICTED AREAS exceeding the above limits, without delay, restore the concentration to within the above limits.

b. If samples or analyses required by Table 2.2-1 are not performed, report these in the next Annual Radioactive Effluent Release Report with an explanation why they were missed and what actions were taken to prevent reoccurrence,

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

SURVEILLANCE REQUIREMENTS 2.2.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 2.21.

2.2.1.1.2The results of the radioactivity analysis shall be used in accordance with the methods in !

ODCM Section 6.1 to assure that the concentration at the point of release is maintained within the limits stated above. l l

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SQN ODCM Revision 35 Page 21 of 163 Table 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 1 of 3) ,

Minimum Lower Limt of Sampling Analysis Type of Activity Detection (LLD)

Liquid Release Type Frequency Frequency Analysis ( cumn a A. Batch Waste Release Tankso P P Principal Gamma 5x10-

1. Waste Condensate Tanks Each Batch Each Batch Emitters l (3) l

2. Cask Decontamination 1-131 1x10* '

Tank 3

3. Laundry Tanks (2) P M Dissolved / 1x10-

4. Chemical Drain Tank One Batch /M Entrained Gases

5. Monitor Tank (Gamma Emitters)

6. Distillate Tanks (2) 3

7. Condensate Demineralizer P M H-3 1x10' Waste Evaporator Tank Each Batch Composite b Gross Alpha 1x10-P Q Sr-89. Sr-90 5x10-Each Batch Composite b Fe-55 1x10*

B, Continuous Releasese D W Principal Gamma 5x10-

1. Steam Generator Grab Sample Compositec Emitters '

Blowdownh

2. Turbine Building Sumph M M l-131 1x10j Grab Sample Dissolved / 1x10-Entrained Gases (Gamma Emitters) 3 D M 1x10 7 Grab Sample Composite c H-3 1x10-

- Gross Alpha ,

D Q 5x10-Grab Sample Compositec Sr-89, Sr-90 1x10' Fe-55 C. Periodic Continuous Continuous' W Principal Garpma 5x10-'

Releasese,h Compositec Emitters

1. Non-Reclaimable Waste Tank M' M l131 1x10*

2. High Crud Tanks (2) Grab Sample Dissolved / 1x10'

3. Neutralizer Tank Entrained Gases (Gamma Emitters)

Continuous 8 M 1x10' Compositec H-3 1x10-Gross Alpha ,

Continuous 8 Q 5x10*

Compositec Sr-89, Sr 90 1x10-Fe-55

i SQN ODCM Revision 35 Page 22 of 163 Table 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM.

(Page 2 of 3) TABLE NOTATION

,, a The LLD is defined for the purpose of these specifications as the smallest concentration of l radioactive material in a sample that will yield a net count above system background that will be I detected with 95% probability with only a 5% probability of falsely concluding that a blank i observation represents a "real" signal.

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

l l 4.66s, j LLD =

E V 2.22x10e Y exp(-AAt)

Where:

l LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume, seis 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 fractional radiochemical yield (when applicable),

A is the radicactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between midpoint of sample collection and time of counting (midpoint).

l It should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of a measurement system and not an a postenori (after the fact) limit for a particular measurement. !3b b A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

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

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SQN ODCM i Revision 35 Page 23 of 163 Table 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 3 of 3) TABLE NOTATION d A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by the method described in ODCM Section 6.1.1, to assure representative sampling.

e A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the continuous release. ,

i f The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141.

Ce-144 shall also be measured with an LLD of 5x10-8. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. ,

g Release" from these tanks are continuously composited during releases. With the composite sampler or the sampler flow monitor inoperable, the sampling frequency shall be changed to require representative batch samples from each tank to be released to tw taken prior to release and manually composite for these analyses, h Applicable only during periods of primary to secondary leakage or the release of radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of

<1x104 pCi/ml and allowing for background radiation during periods when primary to secondary leakage is not occurring.

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SON ODCM Revision 35 Page 24 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS I 1/2.2.1.2 DOSE CONTROLS I

1.2.1.2 In accordance with SQN Technical Specification 6.8.4.f.4 and 5, the dose or r.ase l35 commitment to a MEMBER OF THE PUBLIC from radioactive materials in liqud effluents released to UNRESTRICTED AREAS shall be limited from each reactor unit:

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

to less than or equal to 5 mrem to any organ, and i

b. During any calendar year to less than or equal to 3 mrem to the total body and to 1 less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding ,

any of the above limits, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a 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 sssure that subsequent releases will be in compliance with the above limits. This Special Report si.a:I also include (1) the results of radiological analyses of the drinking water source and (2) the stdiologicalimpact on finished drinking water supplies with regard to the requirements of 40 CFR 141 (applicable only if drinking water supply is taken from the receiving water body within three miles downstream of the plant discharge).

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

SURVEILLANCE REQUIREMENTS 2.2.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in ODCM Section 6.3 at least once per 31 days.

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SQN ODCM Revision 35 Page 25 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM CONTROLS 1.2.1.3 In accordance with SQN Technical Specification 6.8.4.f.6, the liquid radwaste treatment l35 system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent to UNRESTRICTED AREAS (see Figure 3.1) would exceed 0.06 mrem per reactor unit to the total body or 0.2 mrem per reactor unit to any organ in a 31 day period.

APPLICABfLITY: At alltimes.

ACTION:

a. With radioactive liquid waste being aischarged without treatment and in excess of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days pursuant to ODCM Administrative Control 5.4, a Special Report which includes the following information:

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

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

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

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

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

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l SQN ODCM l Revision 35 Page 26 of 163 1/2 CONTROLS AND SURVElLLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 112.2,2,1 DOSE RATE CONTROLS i 1.2.2.1 In accordance with SQN Technical Specification 6.8.4.f.7, the dose rate at any time due to l 31 l 35 radioactive materials released in gaseous effluents to areas at or beyond the UNRESTRICTED AREA BOUNDARY (see Figure 3.1) shall be limited to the followir.g: l 33 l

a. For noble gases: Less than or equal to a dose rate of 500 mrem /yr to the total tody '

and less than or equal to a dose rate of 3000 mrem /yr to the skin, and y

b. For lodine-131, lodine 133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem /yr to JA I any organ. ;

1 APPLICABILITY: At alltimes.

ACTION:

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

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

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

SURVEILLANCE REQUIREMENTS 2.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in ODCM Section 7.2.3, and i 2.2.2.1.2The dose rate due to lodine-131, lodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be i determined to be within the above limits in accordance with the methodology and I parameters in ODCM Section 7.2.4 and by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in ;

Table 2.2-2. 1 i

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SON ODCM !

Revision 35 i Page 27 of 163 ;

l Tabie 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM (Page 1 of 3)

Lower Limit of Sampling Minimum Analysis Detection (LLD) l Gaseous Release Type Frequency Frequency Type of ActMty Analysis (pC64ni)a j A. Waste Gas Storage P P Principal Gamma 1x104 ,

Tank Each Tank Each Tank Emitters 9 l Grab l B. Containment P' D' Principal Gamma 1x104 I

1. PURGE Each PURGE Each PURGE Emitters 9 Grab Sample H-3 1x104 l

2. Vent W W Principal Gamma 1x104 )

Grab Sample Emitters 9 !

H-3 1x104 )

C. Noble Gases and M M Principal Gamma 1x104 l Tritium Grab Sample Emitters 9 l

1. Condenser Vacuum Exhausth H-3 1x104

2. Auxiliary Building Exhaustb,e

3. Service Bldg.

Exhaust

4. Shield Bldg.

Exhaustb,c,h D. lodine and Particulates Continuous WO l-131 1x10-12

1. Auxiliary Building Samplerf Charcoal Sample Exhaust

2. Shield Building Exhaust Continuous Wd Principle Gamma 1x10*"

Sampler I Particulate Emitters 9 Sample (1-131. Others)

Continuous Gross Alpha 1x10-"

Samplerf M Composite Particulate Continuous Sample Sr-89, Sr 90 1x10 "

Samplerf Q

Composite Particulate Sample E. Noble Gases Continuous Noble Gas Monito Noble Gases 1x104 All Release types Monitorf Gross Beta or Gamma as listed in C

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SON ODCM Revision 35 Page 28 of 163 Table 2.2-2 (Page 2 of 3)

RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION a The LLD is defined, for the purpose of these Controls, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will '

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

observation represents a "real" signal.

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

I 4.66se l LLD = l E V 2.22x106 Y exp (4 At) l Where:

LLD is the "a priori" tower limit of detection as defined above in microcurie per unit mass or Volume, seis the standarti 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, 2.22x106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (midpoint),

i 11 should be noted that the LLD is defined as an a orlori (before the fact) limit representing the capability of a measurement system and not an a costeriori(after the fact) limit for a particular measurement.

b Sampling and analysis shall also be performed following shutdown, startup, or a thermal power change exceeding 15% of RATED THERMAL POWER within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months unless (1) analysis shows I that the DOSE EQUIVALENT l-131 concentration in the primary coolant has not increased more than a factor of 3 and (2) the containment noble gas activity monitor (RE-90-106 or RE-90-112) shows that the radioactivity has not increased by more than a factor of 3.

c Tritium grab samples shall be taken periodically when the refueling canal is flooded. 3'$

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SQN ODCM Revision 35 Page 29 of 163 Table 2.2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (Page 3 of 3) d Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 2 days following each shutdown from 115% RATED THERMAL POWER, startup of 115% RATED THERMAL POWER or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in one hour and analyses shall be -

completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for <24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10.

e Tritium grab samples shall be taken periodically from the ventilation exhaust from the spent 33 fuel pool area, whenever spent fuel is in the spent fuel pool.

f The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with ODCM Sections 7.2,7.3, and 7.4.

g The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gases and Mn-54, Fe-59,1-131, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate principal gamma emitters. This list does not mean that only these nuclides are to be detected and reported. Other gamma peaks which are measurable and identifiable, together with the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to ODCM Administrative Control 5.2.

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 compartmeats 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 PURGE or at the peak of 33 the discharge based on the radiation monitor response.

J VENTING - Applicable in MODES 1,2,3, and 4; the containment will be VENTED to the containment annulus and then to the auxiliary building via containment annulus fans. The lower containment compartment shall be sampled weekly and the lower containment radiation monitor response will be recorded daily when VENTING is to occur to account for the radioactivity being discharged from the VENTING process. The lower containment will also be N sampled when the reading on the lower containment radiation monitor increases by 50% during any sampling period.

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SQN ODCM Revision 35 ;

Page 30 of 163 !

l 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS f i

1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.2 DOSE - NOBLE GASES '

CONTROLS ,

1.2.2.2 In accordance with SQN Technical Specification 6.8.4.f.8, the air dose due to noble gases l35 .

released in gaseous effluents from each reactor unit to areas at or beyond the +

UNRESTRICTED AREA BOUNDARY (see Figure 3.1) shall be limited to the following:

l33 :

a. During any calendar quarter Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less i than or equal to 20 mrad for beta radiation. !

APPLICABILITY: At alltimes.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any ,i of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days, l pursuant to ODCM Administrative Control 5.4, a Special Report which identifies the cause(s) -

for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective adions to be taken to assure that subsequent releases will be in compliance with the above limits.

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

SURVEILLANCE REQUIREMENTS 2.2.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in ODCM Section 7.3 at least once per 31 days.

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I SQN ODCM Revision 35 Page 31 of 163 1 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS i

1/2.2 RADIOACTIVE EFFLUENTS )

i 1/2.2.2 GASEOUS EFFLUENTS '

1/3,2.2.3 DOSE -I-131. I-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM w!TH HALF-LIVES GREATER THAN EIGHT DAYS

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CONTROLS 1.2.2.3 in accordance with SON Technical Specification 6.8.4.f.9, the dose to a MEMBER OF l35 THE PUBLIC from I-131,1-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at or beyond the UNRESTRICTED AREA BOUNDARY (see Figure 3.1) shall be limited to the following 33 from each reactor unit:

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

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

APPLICABILITY: At alltimes.

ACTION:

a. With the calculated dose from the release of I-131,1-133, tritium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the ,

above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days, i pursuant to ODCM Administrative Control 5.4, a Special Report which identifies the cause(s) {

for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. i

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. I SURVEILLANCE REQUIREMENTS j l

2.2.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for 1-131,1 133, tritium and all radionuclides in particulate form with half lives greater than 8 days shall be determined in accordance wdh the methodology and parameters in ODCM Section 7.4 at least once per 31 days.

SQN ODCM Revision 35 Page 32 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.4 GASEOUS RADWASTE TREATMENT CONTROLS 1.2.2.4 in accordance with SQN Technical Specification 6.8.4.f.5 and 6 the GASEOUS !

RADWASTE TREATMENT SYSTEM snd the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent doses due to gaseous effluent releases to areas at or beyond the SITE BOUNDARY (see Figure 3.1), when averaged over 31 days, would exceed 0.2 mrad per unit for gamrna radiation, and 0.4 mrad p6r unit for beta radiation. The appropriate portions of t'se VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses Jue to gaseous effluents to areas at or beyond the UNRESTRICTED AREA BOUNDARY (See Figure 3.1) when averaged over 31 days l33 would exceed 0.3 mrem per unit to any organ.

e.GLTGN:

a. With the radioactive gaseous waste being discharged without treatment for more than 31 days and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report which includes the following information:

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

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

3. Summary description of actior'(s) taken to prevent a recerrence.

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

SURVEILLANCE REQUIREMENTS 2.2.2.4 Doses due to ghseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in ODCM Section 7.5.

SQN ODCM Revision 35 Page 33 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.3 TOTAL DOSE CONTROLS 1.2.3 in accordance with SQN Technical Specification 6.8.4.f.10, the annual (calendar year) l35 dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem).

APPLICABILITY: At alltimes.

ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the liruits of ODCM Control 1.2.1.2,1.2.2.2, or 1.2.2.3, calculations should be made to determine whether the above limits have been violated. If such is the case, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits above. This Specia! Report, as defined in 10 CFR Part 20.2203, shall include an analysis 32.

which estimates the radiation dose to a MEMBER OF THE PUBLIC from uranium fuel cycle i sources (including all effluent pathways and direct radiation) for a calendar year that includes the release (s) covered by this report. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190 and include the specified information of Section 190.11(b). Submittal of the '

report is considered a timely request, and a variance is granted until the staff action on the request is complete,

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

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

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SQN ODCM Revision 35 Page 34 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM CONTROLS 1.3.1 in accordance with SON Technical Specification 6.8.4.g.1, the radiological environmental 35 monitoring program shall be conducted as specified in Table 2.3-1.

APPLICABILITY: At all times.

ACTION:

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

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b. With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 2.3-2 wt'en averaged over any calendar quarter, prepare and submit to the ;

Commission within 30 days from the end of the affected quarter, pursuant to ODCM '

Administrative Control S.4, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of ODCM Controls 1.2.1.2,1.2.2.2 and 1.2.2.3. When one or more of the radionuclides in Table 2.3-2 is de'tected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2)

+

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

When radionuclides other than those in Table 2.3-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of ODCM Controls 1.2.1.2,1.2.2.2, and 1.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report

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Page 35 of 163 l

1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS l

1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM ACTION (CONTINUED): )

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 2.31, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specified locmions from which samples were unavailable may then be deleted from the monitoring program. Pursuant to ODCM Administrative Control 5.1, identify the new locations for {

obtaining replacement samples in the Annual Radiological Environmental Operating Report. A l revised figure (s) and table (s) for the ODCM reflecting the new location (s) shall be included in the next Annual Effluent Release Report pursuant to ODCM Administrative Control 5.2.

d. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. j l

SURVEILLANCE REQuiREMEnlTS I 2.3.1 The radiological environmental monitoring samples shall be collected pursuant to Table 2.3-1 from the locations given in the tables and figures given in ODCM Section 9.0 and shall be analyzed pursuant to the requirements of Table 2.31 and the detection capabilities requimd by Table 2.3-3.

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SQN ODCM Revision 35 i Page 36 of 163 Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 1 of 2)

Exposure Number and Sampling and Pathway Location of Collection Type and Frequency of ,

and/or Samples

Frequency Analysis !

Sample AIRBORNE Radioiodine Minimum of 5 W Radiolodine canister and locations Continuous sampler" Weekly 1-131 Particulates Particulate sampler: Analyze for gross beta activity > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change.

Perform gamma isotopic analysis on each sample when gross beta activity is >

10 times the yeariy mean of control samples Q: Perform gamma isotopic analysis on composite ( by location) sample. l DIRECT RADIATION 35 to 40 locations Q Q: Gamma Dose-with > 2 dosimeters for continuously l measuling and recording dose rate at each location.

WATERBORNE Surface 3 locations M Gamma isotopic Composite" sample Each compcsite sample Tritium analysis l Ground 2 locations Q Gamma isotopic and tritium I analyses of each sample.

Gross beta and gamma ,

isotopic analysis !

Drinking Minimum of 1 M Q l location Composite ~ sample Tritium analysis M

2 locations Grab sample Gross beta and gamma isotopic analysis Shoreline Minimum of 2 S Gamma isotopic analysis Sediment locations from each sample.

locations

Sample locations are given in Table 9.1.

" Continuous sampling with sample collection as required by dust loading, but at least once per 7 days.

" Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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l SON ODCM Revision 35 Page 37 of 163 I

Table 2.31 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i (Page 2 of 2) l f

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

Frequency l Sample INGESTION Milk Milk from 3 B" I Gamma isotopic and 1-131 locations. analysis of each sample.

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

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

Once per 184 days if not seasonal.

One sample of each of the following species:

Channel Catfish Crappie Smallmouth Buffalo Food Products Minimum of 2 At time of harvest. Gamma isotopic analysis on locations One sample of each edible portions.

of the following or similar classes of food products, as available i

1. Lettuce and/or cabbage 2.Com

, 3. Beans l 4. Tomatoes i

- When animals are on pasture, at least once per 31 days at other times. l l

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SQN ODCM Revision 35 Page 38 of 163 Table 2.3-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water Airbome Fish Milk Food (pCi/L) Particulate (pCi/kg, wet) (pCi/L) Products or gases (pCi/kg, wet)

(pCi/m3)

H-3 2 x 104(a) N.A N.A N.A. N.A.

Mn-54 1 x 103 N.A. 3 x 104 N.A. N.A.

Fe-59 4 x 102 N.A. 1 x 104 N.A. N.A.

Co-58 1 x 103 N.A. 3 x 10d N.A. N.A.

Co-60 3 x 102 N.A. 1 x 104 N.A. N.A.

Zn-65 3 x 102 N.A. 2 x 104 N.A. N.A.

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

1-131 2(D) 0.9 N.A. 3 1x102 Cs-134 30 10 1x103 60 1x103 Cs-137 50 20 2x103 70 2x103 Ba-La-140 2 x 102 N.A. N.A. 3 x 102 N.A.

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

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

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SQN ODCM Revision 35 Page 39 of 163 Table 2.3-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b (Page 1 of 2) e i

Airbome Particulate Fish Food i Water or Gases (pCi/kg, Milk Products Sediment Analysis (pCi/L) (pCi/m3) wet) (pCi/L) (pCi/kg, wet) (pCl/kg. dry) gross beta 4 1x10-2 N.A. N.A N.A. N.A. ,

H-3 2000* N.A N.A N.A N.A. N.A.

Mn-54 15 N.A. 130 N.A. N.A. N.A.

Fe-59 30 N.A. 260 N.A. N.A. N.A.

Co-58,60 15 N.A. 130 N.A. N.A. N.A.

Zn-65 30 N.A. 260 N.A. N.A. N.A.

Zr 95 30 N.A. N.A. N.A. N.A. N.A. :

Nb-95 15 N.A. N A. N.A. N.A. N.A.

1-131 1" 7x10-2 N.A. 1 60 N.A.

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

La-140 15 N.A. N.A. 15 N.A. N.A.

If no drinking water pathway exists, a value of 3000 pCi/L may be used. l "If no drinking water pathway exists, a value of 15 pCl/L may be used. !

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SON ODCM Revision 35 Page 40 of 163 I Table 2.3-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b (Page 2 of 2) TABLE NOTATION a The LLD is defined, for the purpose of these Controls, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will l be detected with g5% probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

4.66sb LLD =

E V 2.22 Y exp(4.A1) ,

where:

LLD is the "a priori" lower limit of detection as defined above in picocurie per unit mass or volume, sbis 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 picocurie, i 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.

It should be recognized that the LLD is defined as an a orlori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement. Analysis will be performed in such a manner that the stated LLDs will be achieved under routine conditions.

b Other peaks which are measurable and identifiable, together with the radionuclides above, shall be identified and reported.

SQN ODCM i Revision 35 Page 41 of 163 1/2 CONTROLS AND SURVElLLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2,3.2 LAND USE CENSUS CONTROLS 1.3.2 in accordance with SQN Technical Spec 1 cation 6.8.4.g.2, a Land Use Census shall be 35 conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the a

nearest garden of greater than 50 m2 (500 ft 2) producing fresh leafy vegetables.

Broad beef vegetation semp6ng of et least three d6erent kinds of vegetation may be performed at the sRe boundary h each of two d6erent drection sectors with the highest pro 6cted DGs M beu of the garden connus. Spec 6catens for broadleaf vegetaten sempMg in Tab 6e 2.3-1 shotbe IbCowed, hcludog eneysts of control semples.

APPLICABILITY: At all times.

i ACTION.

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

b. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same pathway) 20% greater than at a location from which samples ate currently being obtained in accordance with the requirements of ODCM Control 1.3.1, add the t'ew location (s) within 30 days to the radiological environmental monitoring program l

given in ODCM Section 9.0, if samples are available. The sampling locat6on(s), excluding l the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitosing program after October 31 of the year in which this Land Use Census was conducted. Pursuant to ODCM Administrative Controls 5.2 and 5.3, submit in the next Annual Effluent Release Report i documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new kx:stion(s) with the information supporting the change in sampling locations.

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

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SQN ODCM Revision 35 Page 42 of 163 1/2 CONTROLS AND SURVElLLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS SURVEILLANCE REQUIREMENTS 2.3.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, mail survey, telephone survey, aerial survey, or by consulting local agricultural authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM Administrative Control 5.1.

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SON ODCM Revision 35 Page 43 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 1.3.3 in accordance with SON Technical Specification 6.8.4.g.3, analyses shall be performed on l36 radioactive materials supplied as part of an Intertaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At alltimes.

ACTION:

a. With analyses not being performed as required above, report the corrective actions being taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to ODCM Administrative Control 5.1.

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

SURVEILLANCE REQUIREMENTS 2.3.3 A summary of the results obtained as a part of the above required intertaboratory _

Comparison Program and in accordance with the guidance below shall be included in the Annual Radiological Environmental Operating Report pursuant to CDCM Administrative Control 5.1.

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SON ODCM l Revision 35 ;

Page 44 of 163 EAEfSFOR SECTIO'as t.0 AND 2.0 UCffTh0LS AND SURVEILLANCE REQUIREMENTS liQlE The BASES contained in succeeding pages summanite the reasons for the Controls in Sections 1.0 and 2.0, but are not part of these Controls. -

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SQN ODCM Revision 35 Page 45 of 163 BASES INSTRUMENTATION 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable.

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

procedures in ODCM Section 6.2 to ensure that the alarm / trip will occur prior to exceeding ten 3R l times the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A to 10 l CFR Part 50. I 1/2.1.2 RADIOAgr/E GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance to exceeding ten timeswith thethe limitsprocedures inThe of 10 CFR Part 20. ODCM Section OPERABILITY and use7.1of to this ensure that the alarm, instrumentation is consistent with the requirements of General Design Criteria 60,63, and S4 of Appendix A to 10 CFR Part 50.

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1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1.1 CONCENTRATION This Control is provided to ensure that the concentration of radioactive materials released at any y time in liquid waste effluents to UNRESTRICTED AREAS will be less than ten times the concentration levels specified in 10 CFR Part 20. Appendix B, Table 2, 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 ll.A design objectives of Appendix 1,10 CFR 50, and (2) the limits of 10 CFR 20.1301(a)(1) to a MEMBER OF THE y PUBLIC. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in Intemational Commission of Radiological Protection (ICRP) Publication 2.

1/2.2.1.2 DOSE This Control is provided to implement the requirements of Sections ll.A, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The requirement implements the guide set forth in Section ll.A of Appendix 1. The action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive materials in liquid effluents will be kept "as low as reasonable achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculations in ODCM Section 6.3 implement the requirements in Section Ill.A of Appendix i that conformance with the guides of Appendix ! be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriately modeled pathways is unlikely to substantially underestimated. The equations specified in Section 6.3 for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology

SON ODCM Revision 35 Page 46 of 163 BASES 1/2,21.2 DOSE (continued) provided in Regulatory Guide 1.109," Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1 October 1977 and Regulatory Guide 1.113," Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," April 1977.

This Control applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing that system.

Compliance with this Control will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301(a)(1) per 56 FR 23374. 31 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM The Control that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonable achievable." This requirement implements the requirements of 10 CFR Part 50.36a, General Design Criteria 60 of 10 CFR Part 50 Appendix A, and the design objective given in 10 CFR Part 50 Appendix i, Section ll.D. The specified limits goveming the use of appropriate portions of the liquid radwaste system were specified as a suitable fraction of the dose design objectives set forth in 10 CFR Part 50 Appendix 1, Section ll.A, for liquid effluents.

1/2.2.2.1 DOSE RATE This Control is provided to ensure that the extemal dose rate at any time at the UNRESTRICTED AREA BOUNDARY from gaseous effluents from all units on the site will be within the limits of 10 CFR Part 20.1301(a)(1) for UNRESTRICTED AREAS. The 500 mrem / year dose rate will ensure 32 that the instantaneous dose rate is well below 2 mrem /hcur. The limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, to annual average concentrations exceeding the limits specified in of 10 CFR Part 20, Appendix B. Table 2. For MEMBERS OF THE PUBLIC who may at times be within the CONTROLLED AREA, the occupancy of the individual will be sufficiently low to N compensate for any increase in the atmospheric diffusion factor above that for the UNRESTRICTED AREA BOUNDARY. The specified reh,ase rate limits restrict, at all times, the l33 corresponding gamma and beta dose rates above background to an individual at or beyond the UNRESTRICTED AREA BOUNDARY to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all g

times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to less than or equal to 1500 mrem / year for the nearest cow to the plant. This requirement applies to the release of gaseous effluents from all reactors at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared systems are proportioned among the units sharing that system.

I SQN ODCM Revision 35 Page 47 of 163 l BASES I

1/2 2 RADIOACTIVE EFFLUENTS 1/2.2.2.2 DOSE - NOBLE G ASES l This requirement is provided to implement the requirements of 10 CFR Part 50 Appendix 1, Sections !!.B,lll.A and IV.A. The requirement implements the guides set forth in Appendix I Section ll.B Compliance with this Control will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301(a)(1) per 56 FR 23374. The action to be taken provides the required 32 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 ' % l low as reasonably achievable." The surveillance implements the requirements in Section Ill.A c.

Appendix 1 that conformance with the guides of Appendix l be shown by calculational procedures i based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through l appropriately modeled pathways is unlikely to be substantially underestimated. The dose calculations established in ODCM Section 7.3 for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109,' Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision

1. July 1977. The ODCM equations provided for determining the air doses at the UNRESTRICTED g j AREA BOUNDARY are based upon the historical average atmospheric conditions.

1/2.2.2.3 DOSE -IODINE-131. LODINE-133. TRITIUM. AND RADIOACTIVE MATERIAL IN PARTICULATE FORM WITH HALF-LIFE GREATER THAN EIGHT DAYS This Control is provided to implement the requirements 10 CFR Part 50 Appendix i Sections a '

lli.A and IV.A. The requirement implements the guides set forth in Appendix I Section ll.C. The action to be taken provides the required operating flexibility and at the same time implements the guides set forth in Appendix 1 Section IV.A to assure that the releases of radioactive material in l gaseous effluents will be kept "as low as reasonably achievable." Section 7.4 calculational methods implement the requirements in Appendix I Section Ill.A that conformance with the guides l of Appendix 1 be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriately modeled pathways is unlikely to be substantially underestimated. Section 7.4 calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-1004,"A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Intemal Dose of Radionuclides," October 1979 and Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix 1,"

Revision 1, October 1977 and Regulatory Guide 1.111,' Methods for Estimating 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 soecifications for lodine-131, lodine -133, tritium and all radionuclides in particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man, beyond the UNRESTRICTED 33 AREA BOUNDARY. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airbome radionuclides,2) deposition of radionuclides .

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

man, and 4) deposition on the ground with subsequent exposure of man.

SON ODCM Revision 35 Page 48 of 163 BASES 1/2 3 RADIOACTIVE EFFLUENTS 1/2.3.2.4 GASEOUS RADWASTE TREATMENT SYSTEM This Control that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This Controlimplements the requirements of 10 CFR Part 50.36a, General Design Criteria 60 of 10 CFR Part 50 Appendix A, and the design objectives given in 10 CFR Part 50 Appendix i Section ll.D. The specified limits goveming the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in 10 CFR Part 50 Appendix 1 Section ll.B and ll.C, for gaseous effluents.

1/2.2.3 TOTAL DOSE This Control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. Compliance with this Control will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301(a)(1) per 56 N FR 23374. The ACTION requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrem to the total body or any other organ except thyroid, which shall be limited to less than or equal to 75 mrem. 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 Part 190 if the individual reactors remain within twice the dose design objectives of Appendix l and if direct radiation doses from the units and from outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered.

If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provide the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance M

only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in ODCM Controls 1.2.1.1 and 1.2.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is a part of the nuclear fuel cycle.

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SON ODCM Revision 35 Page 49 of 163 BASES

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1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING I 1/2.3.1 MONITORING PROGRAM The radiological environmental monitoring program required by this Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix l to 10 CFR Part 50 and thereby supplements the i radiological effluent monitoring program by verifying that the measurable concentration of I radioactive materials and levels of radiation are not higher than expected on the basis of the !

effluent measurements and modeling of the environmental exposure pathways. Guidance for this l monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.

l The required detection capabilities for environmental sample analyses are tabulated in terms of I the lower limits of detection (LLDs). The LLDs required by Table 2.3-3 are considered optimum for l routine environmental measurements in industriallaboratories. It should be recognized that the i

LLD is defined as an a pl_Q_rl (before the fact) limit representing the capability of a measurement I system and not as a posteriori (after the fact) limit for a particular measurement. l Detailed description of the LLD, and other detection limits can be found in HASL Procedures !

Manual, HASL-300 (revised annually), Curie, L. A., " Limits for Qualitative Detection and '

Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

1/2.3.2 LAND USE CENSUS This Control is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of that census.

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

authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix l to 10 CFR Part 50. Restricting the census to gardens of greater than 500 ft2provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to provide the quantity (26 kglyr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used,1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m2, 1/2.3.3 INTERLABORATORY COMPARISON The requirement for participation in an Intertaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

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SON ODCM Revision 35 Page 50 of 163 SECTION 3.0 DEFINITIONS l

i SQN ODCM Revision 35 '

Page 51 of 163 3.0 DEFINITIONS The defined terms in this section appear in capitalized type in the text and are applicable throughout this ODCM.

3.1 CHANNEL CALIBRATION A CHANNEL CAllBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CAllBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

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

3.3 CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:

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

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

3.4 CONTROLLED AREA 32 A CONTROLLED AREA is the area outside the RESTRICTED AREA but inside the UNRESTRICTED AREA BOUNDARY (See Figure 3.1). !N 3.5 DOSE EQUIVALENT l-131 DOSE EQUIVALENT l-131 shall be that concentration of I-131 (pCl/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132,1 133, I-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table lit of TID-14844, ' Calculation of Distance Factors for Power and Test Reactor Sites."

3.6 GASEOUS RADWASTE TREATMENT SYSTEM A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

SQN ODCM Revision 35 Page 52 of 163 3 0 DEFINITIONS (continued) 3.7 MEMBER (S) OF THE PUBLIC l MEMBER (S) OF THE PUBLIC as defined in 10 CFR 20, shall include all individuals in CONTROLLED OR UNRESTRICTED AREAS.

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

3.9 MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1 of the SON Technical Specifications.

3.10 PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinemaat.

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

3.12 RESTRICTED AREA The RESTRICTED AREA, as defined in 10 CFR Part 20, is that area, access to which is l limited by the licensee for the purposes of protecting individuals against undue risks from 32 33 l '

exposure to radiation and radioactive materials. The permament RESTRICTED AREA is shown on Figure 3.1, but temporary restricted areas outside the permanent RESTRICTED AREA may be defined by SON.

3.13 SITE BOUNDARY NOT USED 33 3.14 SOURCE / SENSOR CHECK A SOURCE / SENSOR CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or other channel sensor intemal test circuit.

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l SON ODCM Revision 35 Page 53 of 163 1

3.0 DEFINITIONS (continued) 1 3.15 UNRESTRICTED AREA / BOUNDARY i

An UNRESTRICTED AREA / BOUNDARY, as used for calculations performed pursuant to 10 CFR Part 50.36a, shall be an area at or beyond the site boundary which is utilized in the ODCM Controls to keep levels of radioactive materials in liquid and gaseous effluents 33 l as low as !s reasonably achievable. The UNRESTRICTED AREA does not include areas I overwater bodies (See Figure 3.1).

3.16 VENTILATION EXHAUST TREATMENT SYSTEM l A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to I reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing l ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing lodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

4 3.17 VENTING VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

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Page 54 of 163 l i

Table 3.1 FREQUENCY NOTATION l ,

P = Completed prior to each release f D = At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l

B = At least once per 15 days 4 i

l l M = At least once per 31 days

! Q = At least once per 92 days R = At least once per 18 months N.A. = Not Applicable l

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SQN ODCM Revision 35 Page 55 of 163 l

Figure 3.1 UNRESTRICTED AREA BOUNDARY I) %hs N DETAll OF N .

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u ss Area between the RESTRICTED AREA and the UNRESTRICTED AREA BOUNDARIES is the CONTROLLED AREA. Area outside the UNRESTRICTED AREA BOUNDARY is the UNRESTRICTED AREA.

SQN ODCM Revision 35 Page 56 of 163 SECTION 4.0 (NOT USED)

SQN ODCM Revision 35 Page 57 of 163 SECTION 5 0 ADMINISTRATIVE CONTROLS I

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SQN ODCM Revision 35 Page 58 of 163 5.0 ADMINISTRATIVE CONTROLS 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT As required by SON Technical Specification 6.9.1.6, Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The annual radiological enviror' mental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by ODCM Control 1.3.2 and a listing of the new locations for dose calculations and/or environmental monitoring identified by the land use census. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, 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 be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Intertaboratory Comparison Program required by ODCM Control 1.3.3.

5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT As required by SON Technical Spec;fication 6.9.1.8, an Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted prior to May 1 of each year.

Annual radioactive release reports shall include a summary of the quantities 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 from Light-Water-Cooled Nuclear Power Plants,"

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

The annual radioactive release report shall include unplanned releases from the site to unrestricted areas on a quarterly basis and shall also include any changes made to the ODCM pursuant to ODCM Administrative Control 5.3.

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SON ODCM Revision 35 Page 59 of 163 5.0 ADMINISTRATIVE CONTROLS 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (continued)

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

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

The annual radioactive effluent release report (Radiological impact) shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability, in lieu of submission with l the annual radioactive effluent release report, this summary of required meteorological data may l be retained on site in a file that shall be provided to NRC upon request). This same report shall include an assessment of the radiation doses due to radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the UNRESTRICTED AREA 33 BOUNDARY (Figure 3.1) during the report period. All assumptions used in making these -

assessments (i.e., specific activity, exposure time, and location) shall be included in these reports.

The meteorological conditions concurrent with the time of release of radioactive materials in l gaseous effluents (as determined by sampling fregt.ency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with Sections 6.6 and 7.6.

The annual radioactive effluent release report to be submitted after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBERS OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation, in accordance with ODCM Section 8.0. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1.

SON ODCM Revision 35 Page 60 of 163 5.0 ADMINISTRATIVE CONTROLS 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES As required by SON Technical Specification 6.14, changes to the ODCM:

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

a. Sufficient information to t,upport the change together with the appropriate analyses or evaluations justifying the change (s) and

b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR Part 20.1302,40 CFR Part 190,10 CFR Part 50.36a, and Appendix i to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

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

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

5.4 SPECIAL REPORTS Special Reports shall be submitted within the time period specified for each report, in accordance with 10 CFR Part 50.4.

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SON ODCM Revision 35 Page 61 of 163 SECTION 6.0 LIQUID EFFLUENTS

SON ODCM Revision 35 Page 62 of 163 SECTION 6.0 LIQUID EFFLUENTS RELEASE POINTS There are four systems from which liquid effluents are released to the environment. These are the Liquid Radwaste System, the Condensate Demineralizer System, the Turbine Building Sump, and the Units 1 and 2 Steam Generator Blowdown. Figure 6.1 provides an outline of the liquid release paths and discharge points with associated flow rates and radiation monitors.

i All liquid effluents are ultimately discharged to the Diffuser Pond which releases to the Tennessee River. The Essential Raw Cooling Water (ERCW) routinely provides dilution for liquid effluents at a minimum flow rate of 15,000 gpm. ERCW flow is monitored by radiation monitors 0-RM-133,-

134,-140,-141.

Liauid Radwaste System 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 6.2 provides a schematic of the Liquid Radwaste System, showing the liquid pathways, flow rate and radiation monitors. The normal release points for liquid radwaste are the Monitor Tank and the Cask Decontamination Collector Tank (CDCT). The Monitor Tank has a capacity of 22,000 gal and is released routinely at a flow rate of 125 gpm. The CDCT has a capacity of 15,000 gal and is also released routinely at a flow rate of 125 gpm. The Monitor Tank and CDCT discharge to the Cooling Tower Blowdown (CTBD) line as a batch release and are monitored y radiation monitor 0-RM-90-122.

Condensate Demineralizer System The Condensate Demineralizer System processes liquid wastes coming from the High Crud Tanks (HCT 1 and 2), the Neutralization Tank, and the Non-Reclaimable Waste Tank (NRWT). The HCTs have a capacity of 20,000 gal and a maximum discharge flow rate of 245 gpm. The Neutralization Tank has a capacity of 19,000 gal and a maximum discharge flow rate of 245 gpm.

The NRWT has a capacity of 11,000 gal and a maximum discharge flow rate of 245 gpm. The Condensate Demineralizer System is routinely released to the CTBD line and is monitored by radiation monitor 0-RM-90-225.

Turbine Buildino Sumo The Turbine Building Sump (TBS) normally releases to the Low Volume Waste Treatment Pond (LVWTP) but can be released to the Yard Pond. The TBS has a capacity of 30.000 gal and a design discharge release mte of 1,750 gpm per pump. TBS releases are monitored by radiation monitor 0-RM-90-212.

Steam Generator Blowdown The Steam Generator Blowdown (SGBD) is processed in the Steam Generator Draindown Flash Tanks or SGBD Heat Exchangers. The SGBD discharge has a maximum flow rate of 80 gpm per steam generator. SGBD discharges to the CTBD line are continuous and am monitored by radiation monitors (1) (2)-RM-90-120, -121.

SQN ODCM Revision 35 Page 63 of 163 0 6,1 LIQUID RELEASES 6.1.1 Pre-Release Analysis To ensure representative sampling, radwaste tanks will be recirculated for a procedurally 3S established length of time, or through two volumes. Periodically, checks will be made to ensure a 33 representative mixing of tank contents. All radwaste tanks will be released as " batch" releases.

Releases from condensate demineralizer tanks are routinely continuous releasesa and utilize a composite sampler to obtain a representative sample while being discharged. In the event of an inoperable composite sampler, the releases will be made as a batch release, and will be 33 recirculated for a procedurally established length of time or through two volumes to ensure 35 representative sampling.

Steam generator blowdown and turbine building sumpa are considered continuous and grab sampled daily during releases. l33 Prior to any batch release, a grab sample will be taken and analyzed to determine the l33 concentration, Ci/ml, of each gamma-emitting nuclide. For continuous releases, daily grab or composite samples will be taken on days when releases are being made and analyzed to determine the concentration, pCi/ml, of each gamma-emitting nuclide. Composite samples are l33 maintained during periods of radioactive discharge from all pathways (as required by Table 2.2-1) l 33 to determine the concentration of certain nuclides (H-3, Fe-55, Sr-89, Sr 90, and alpha emitters).

For those nuclides whose activities are determined from composite samples, the concentrations for the previous composite period can be assumed as the concentration for the next period to perform the calculations in Sections 6.3 and 6.5. The actual measured concentrations will be used for the dose calculations described in Section 6.6.

a Sampling requirements for these release points are applicable only during periods of significant primary tol 3 3 secondary leakage or the release of radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of 51E-06 pCi/mi and allowing for background radiation during periods when primary to secondary leakage is occurring. Sampling and analysis is routinely performed versus utilizing the radiation monitor at this LLD. 33 6.1.2 Effluent Concentration Limits (ECL)-Sum of the Ratios l32 The sum of the ratios (Rj) for each release point will be calculated by the following relationship.

Ci R=I 3 (6.1) i ECL, where:

R3 = the sum of the ratios for release point J.

ECLi = the ECL of radionuclide i, pCi/mi, from 10 CFR Part 20, Appendix B Table 2, Column 2. l 32, C, = concentration of radionuclide i, CL/ml.

The sum of the ECL ratios must be 510 following dilution at the Cooling Tower Blowdown due to the releases from any or all of the release points described above. The ECL ratios for releases 32 from the Turt>ine Building Sump will be s 10 at the sump.

SQN ODCM Revision 35 !

Page 64 of 163 i

The follow:ng relationship is used to ensure that this criterion is met:

fR+fR+IR+fR g 3 22 33 4 4 (6.2)

Ras T + 5. 10.0 F ,

where R Tes = sum of the ECL ratios of the turbine building sump as determined by equation 6.1. l32, '

f,,f I ,f2s4 = effluent flow rate for radwaste, condensate demineralizer system and each of the steam generator blowdowns, respectively, gpm. l 33 R3,R2,R3,R4= sum of ECL ratios for radwaste, condensate demineralizer system and each of the l32. ,

steam generator blowdowns, respectively, as determined by equation 6.1.

F = dilutic:, Cow rate for CTBD, routinely 15,000 gpm. l 33 6.1.3 Post-Release Analysis l A post-release evaluation will be done using actual release data to ensure that the limits specified in ODCM Control 1.2.1.1 were not exceeded. This analysis willinclude an evaluation of the noble 33 gas concentration with regard to ODCM Control 1.2.1.1.

A composite list of concentrations (C), by isotope, will be used with the actual waste (f) and dilution (F) flow rates (or volumes) during the release. The data will be evaluated to demonstrate compliance with the limits in ODCM Control 1.2.1.1. l 33 I

SQN ODCM Revision 35 Page 65 of 163 6.2 INSTRUMENT SETPOINTS Liquid effluent monitor setpoints are determined to ensure that the concentration of radioactive material released at any time from the site to UNRESTRICTED AREAS does not exceed ten times the ECL limits referenced in ODCM Control 1.2.1.1 and to identify any unexpected releases.

6.2.1 Process Discharge Point Monitor Setpoints (0-RE-90-133,134,140,141)

The setpoints for the ERCW monitors (RE 90-133,134,140,141) are set to ensure that the concentration of radioactive materials released at any time from the site do not exceed the limits given in ODCM Control 1.2.1.1. The setpoints for these monitors will be set at a small value above background to ensure that any radioactivity is identified. Site procedures will document and control this value.

6.2.2 Release Point Monitor Setpoints (0-RM-90-122; 0-RM-90-225; 0-RM-90-212; 1,2-RM-90 20,121)

There are five liquid release point effluent monitors: the Liquid Radwaste System radiation monitor 0-RM-90-122; the Condensate Demineralizer System radiation monitor 0-RM-90-225; the Turbine Building Sump radiation monitor 0-RM-90-212; and the Steam Generator Blowdown (SGBD) radiation monitors 1,2-RM-90-120,121.

The batch release points, the Liquid Radwaste System and the Condensate Demineralizer System !

(if being released in a batch mode), are looking at an untiluted waste stream as it comes out of a tank. The purpose of the monitor setpoints for these batch releases is to id*ntify any release that i is larga than expected and would have the potential to exceed the limits after dilution. Setpoints are calculated as described in Section 6.2.3.

The continuous release points, the Condensate Demineralizer System, the Steam Generator Blowdowns, and the Turbine Building Sump, will not be releasing radioactivity unless there is or has been a primary to secondary leak. When there is no identified primary to secondary leakage, these release points we monitored to indicate the presence of elevated activity levels in these systems. The setpoints for these monitors will be set to alarm if the activity in the stream exceeds a routine nominal background. These setpoints are controlled by site instructions.

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

6.2.3 Batch Release Point Monitor Setpoint For each release from a release point, two setpoints are calculated; one based on the monitor response to the contents of the effluent stream; and another based on the predicted response of the monitor to the activity in the release stream if it were large enough to exceed ten times the 10 CFR Part 20 limits after dilution. The expected monitor response, R in cpm, is calculated using equation 6.3 below. The maximum calculated setpoint, m S ,,is calculated using Equation 6.4 below. A comparison is made between these two calculated setpoints to determine which is used.

SQN ODCM Revision 35 l Page 66 of 163 '

The actual monitor setpoint for the release is set equal to X times the expected radioactivity response plus background, or to the maximum calculated setpoint, whichever is less. X is an administrative factor designed to account for expected variations in monitor response (it will be defined in approved plant instructions). The X times expected response setpoint allows for the identification of any release of radioactivity above the expected amount. The maximum calculated setpoint ensures that the release will be stopped if it exceeds ten times the 10 CFR Part 20 concentration limits after dilution.

Exoected resoonse R=B+ I Eff,

C, (6.3)

I where B = monitor background, cpm.

Eff, = monitor efficiency for nuclide i, cpm per Cl/ml.

C, = tank concentration of nuclide i, Ci/ml.

Calculated Maximum Monitor Setooint s

SF (F, + (A

Fd d)

S. = (R - B) + B (6.4)

F, Rj where -

SF = safety factor for the monitor.

F, = flow of waste stream, gpm.

F= flow of the dilution strram gpm.

A = fraction of dilution ficw v6:.cated to this release point. For the TBS, this fraction is zero.

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

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

Rg = sum of the ECL ratios for release point J as calculated in Section 6.1.2.

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

B = background, cpm.

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SON ODCM Revision 35 Page 67 of 163 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATIONS Doses due to liquid effluents are calculated for each release for all age groups (adult, teen, child and infant) and organs (bone, liver, total body, thyroid, skin, kidney, lung and GI tract). Pathways considered are ingestion of drinking water, fish consumption and recreation-shoreline. The maximum individual dose from drinking water is assumed to be that calculated at the location immediately downstream from the diffuser. The maximum individual dose from fish ingestion is assumed to be that calculated for the consumption of fish caught anywhere between the plant and ,

the first downstream dam (Chickamauga Dam). The maximum potential recreation dose is calculated for a location immediately downstream of the plant outfall. Dose factors for these age groups and pathways are calculated as described in Section 6.7. For pathways with no age or organ specific dose factors (i.e. shoreline recreation), the total body dose will be added to the intemal organ doses for all age groups. ]

The general equation for the dose calculations is: ;

Dose = I AnT C, D (6.5) !

I i where: l A g= the total dose factor to the total body or any organ t for nuclide i, mrem /hr per Ci/ml. The i total dose factor is the sum of the dose factors for water ingestion, fish ingestion, and l shoreline recreation, as defined in Section 6.7. I T = the length of time period over which the concentrations and the fbws are averaged for the I liquid release, hours.

C, = the average concentration of radionuclide i, in undiluted liquid effluent during the time period T from any liquid release, pCi/ml.

D = the near field average dilution factor for C iduring any effluent release. D is calculated by the following equation:

FLOW, D=

0.60 RF where:

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

0.60 = mixing factor of effluent in river, defined as the percentage of the riverflow which is available for dilution of the release.

RF = default riverflow, cfs. For each release, this value is set to 7900 cfs (the lowest average quarterly riverflow recorded from the period 1978-1988).

From the four age groups com.idered, 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 d0se described in Section 6.3.1.

SON ODCM Revision 35 Page 68 of 163 6.3.1 Monthly Dose Calculations At the end of each month, the actual average riverflow for the month is used to recalculate the liquid doses. The monthly cumulative dose is defined as the sum of the doses for the critical age l group for each release during the month. Thus, the monthly cumulative dose will be a conservative value, consisting of doses belonging to various age groups depending on the mix of .j

! radionuclides. These 0'oses are multiplied by the ratio of the default riverflow (7900 cfs) to the i 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 quartetty and annual doses described in Section 6.3.2, and for the dose projections described in Section 6.5.

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

the limits given in ODCM Control 1.2.1.2. These quarterly and annual sums will be the sum of the l monthly cumulative doses described in Section 6.3.1 for the appropriate months in the quarter or l year. These doses will be used in the comparison to the limits.

6.3.3 Comparison to Limits The cumulative calendar quarter and calendar year doses are. compared to the limits in ODCM Control 1.2.1.2 once per 31 days to determine compliance.

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SQN ODCM i Revision 35 Page 69 of 163 2 6.4 LIQUID RADWASTE 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 6.2. 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 building: one sump tank and pumps, one tritiated drain collector tank with two pumps and one filter, one floor drain collector tank with two pumps ar'd one filter, a waste condensate tank filter, three waste condensate tanks and two pumps, a chemical drain tank and pump, two laundry end hot shower tanks and pump, a spent resin storage tank, a cask decontamination tank with two pumps and two filters, Auxiliary Building floor end equipment drain sump and pumps, and evaporator with two distillate tanks, a Mobile Waste Demineralizer System (if needed) and the associated piping, valves and instrumentation.

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SQN ODCM Revision 35 Page 70 of 163 6.5 DOSE PROJECTIONS in accordance with ODCM Surveillance Requirement 2.2.1.3, dose projections will be performed by averaging the two previous month's doses as determined in Section 6.3.1. To determine compliance with the limits, these averages are assigned as the dose projections for the upcoming month, t

The projected doses are compared to the limits of ODCM Control 1.2.1.3. If the projected doses I i

exceed either of these limits, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge to UNRESTRICTED AREAS.

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SQN ODCM Revision 35 Page 71 of 163 6.6 QUARTERLY DOSE CALCULATIONS A complete dose analysis utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control 5.2. Methodology for this analysis is that which is described in this section using the quarterly release values reported by the plant personnel. The releases are assumed, for this calculation, to be continuous over the 90 day period.

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

1 D= (for receptors upstream (6.6)

RF

0.60 of Chickamauga Dam) and 1

D= (for receptors downstream (6.7)

RF of Chickamauga Dam) where:

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

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

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

D y = 106 9.80E-09 Aw, Q, D exp(-8.64E+04 to) (6.8) where 108 = conversion factor, pCi/Cl. !

9.80E-09 = conversion factor, cfs per ml/h. l A,w a dose factor for water ingestion for nuclide i, age group t, mrem /h per Ci/ml, as calculated in Section 6.7.1.

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

D = dilution factor, as described above, cfs t A = radiological decay constant of nuclide i, sd (Table 6.2).

td = decay time for water ingestion, equal to the travel time from the plant to ue water supply plus one day to account for the time of processing at the water supply (per Regulatory Guide 1.109), d.

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

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SQN ODCM Revision 35 Page 72 of 163 6.6.2 FISH INGESTlON Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of SQN (Table 6.1). Individual fish ingestion doses are calculated for the total body and each intema! organ as described below:

8 D y = 10 9.80E-09 0.25 Ar, Q, D exp(-8.64E+04 y td) (6.9) where 106 = conversion factor, Cl/Cl.

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

O.25 = fraction of the yearly fish consumption eaten in one quarter, dimensionless.

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

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

D = dilution factor, as described above, cfs-1 y = radiological decay constant of nuclide i, s-1 (Table 6.2).

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), d.

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

6.6,3 SHORELINE RECREATION Recreation doses are calculated for each identified reach within a 50 mile radius downstream of SON (Table 6.1). It is assumed that the maximum exposed individual spends 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months per year on the shoreline at a location immediately downstream from the diffusers. Individual recreation shoreline doses are calculated for the total body and skin as described below-Dy = 1089.80E-09 ff A Ra Qi D exp(-8.64E+04 y to) (6.10) where 106 = conversion factor, Ci/Cl.

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

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

spent at a rt. creation site during each quarter. Recreation factors used are:

1st quarter - 0.1 2nd quarter - 0.3 31 quarter - 0.4 4th quarter- 0.2.

A pg = dose factor for shoreline recreation for nuclide i, age group t, mrem /h per Ci/mt, as calculated in Section 6.7.3.

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

D = dilution factor, as described above, cfs-1 A = radiological decay constant of nuclide i, s 1 (Table 6.2).

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

. reach, d.

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

i SQN ODCM Revision 35 Page 73 of 163 6.4.4 TOTAL MAXIMUM INDIVIDUAL DOSE The total maximum individual total body dose is obtained by summing the following for each age l

group: the highest total body water ingestion dose from among all the public water supplies; the i highest total body fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual organ dose is obtained by s aming the following for each organ and each age group: that organ's highest water ingestion dosu 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. !

6.6.5 POPULATION DOSES I

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

{

\

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

5 4 i POPWTR: = 10-3 I POPm I POP, ATMW, TWDOS w (6.11) m=1 a=1 where:

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

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

Adult = 0.665 Child = 0.168 infant = 0.015 Teen = 0.153 POP, = population at PWS m. The 4 PWSs and their populations are listed in Table 6.1.

ATMW, = ratio of average to maximum water ingestion rates for each age group a. Maximum water ingestion rates are given in Table 6.3. Average water ingestion rates, in 1/ year, (from R.G.1.10g Table E 4) are:

Adult = 370 Child = 260 Infant = 260 Teen = 260 TWDOS, = total individual water ingestion dose to organ t at PWS m, to the age group a, as described in Section 6.6.1, mrem.

10-3 = conversion factor for rem / mrem.

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SON ODCM Revision 35 Page 74 of 163 For population doses resulting from fish ingestion the calculation assumes that all fish caught within a 50-mile radius downstream of SQN are consumed by local population. An additional 7-day decay term is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in man-rem from fish ingestion of all fish caught within a 50-mile radius downstream is:

453.6 HVST APR 4 3 TFDOS g POP, POPF, = I I (6.12) 103 103 r=1 a=1 FISH, POP, where:

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

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

APR = size of reach, acres (Table 6.1).

TFDOSg = tota l'ish ingestion dose to organ t for reach r, for the age group a, as described in Section 6.6.2, mrem. ,

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

FISH, = amount of fish ingested by each age group a, kgly. Average fish ingestion rates (R.G.1.109 Table E-4) are:

Adult = 6.9 Child = 2.2 Teen = 5.2 453.6 = conversion factor, g/lb.

103 = conversion factor, mrem / rem.

103 = conversion factor, g/kg.

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SQN ODCM Revision 35 Page 75 of 163 For recreation shoreline, the general equation used for calculating the population doses, POPR, in man-rem is:

REQFRA 4 POPR, = E TSHDOSnSHVIS rHRSVIS r (6.13) 103 8760 r=1 where:

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

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

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

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

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

103 = conversion factor, mrem / rem.

8760 = conversion factor, hours per year.

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SON ODCM Revision 35 Page 76 of 163 6.7 LIQUID DOSE FACTOR EQUATIONS 6.7.1 WATER INGESTION Awg (mrem /h per Ci/ml)

DF w U 10s103

=

8760 where:

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

U =

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

10 conversion factor, pCi/ Cl.

103 = conversion factor, ml/l.

8760 = conversion factor, hours per year.

6.7.2 FISH INGESTION Ara (mrem /h per Ci/ml)

DF w SU B,10610 3 Apg =

8760 where:

DFu = ingestion dose conversion factor for nuclide i, age group a, organ t, mrem /pCl, (Table 6.4). l U m = fish consumption rate for age Group a, kgly, (Table 6.3). '

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

108 = conversion factor, pCi/ Cl.

103 = conversion factor, ml/L.

8760 = conversion factor, hours per year.

6.7.3 SHORELINE RECREATION ara (mrem /h per Ci/ml).

DFoa K eM W 10 310s U AR [1-exp( \ty)

~

8760 *3600 where:

l DFo,= dose conversion factor for standing on contaminated ground for nuclide i and organ t (total j body and skin), mrem /h per pCi/m2, (Table 6.6). l K, = transfer coefficient from water to shoreline sediment, Ukg-h, (Table 6.3).

M = mass density of sediment, kg/m2, (Table 6.3).

W = shoreline width factor, dimensionless, (Table 6.3).

103 = conversion factor, ml/L.

10e = conversion factor, pCi/ Ci.

3600 = conversion factor, s/h.

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

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

U = usage factor,500 h/y.

' 760 = conversion factor, hours per year.

4

SQN ODCM Revision 35 ;

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

)

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

Guntersville Lake 425.0 400.0 6766 104,000 Public Water Supplies Within 50 Mile Radius Downstream of SQN Name TRM Population E.1. DuPont 469.9 1,400 Chattanooga, TN 465.3 224,000 South Pittsburg, TN 418.0 4,898 l

Bridgeport, AL 413.6 4,650 l

G k!

-=

J SON ODCM Revision 35 Page 78 of 163 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Pa081 of 3)

Half Life A.

Sw Fw Fw Fn (minutes) (1/s) (cow) (ooat 1 (beef)

H-3 6.46E+06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1.20E-02 C-14 3.01 E+09 3.84E 12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 Na-24 9.00E+02 1.28E-05 5.20E-02 4.00E 02 4.00E 02 3.00E-02 P-32 2.06E+04 5.61 E-07 1.10E+00 2.50E-02 2.505-01 4.60E-02 Cr-51 3.99E+04 2.90E-07 2.50E-04 2.20E 03 2.20E-03 2.40E-03 Mn-54 4.50E+05 . 2.57E-08 2.90E-02 2.50E-04 2.50E-04 8.00E-04 i Mn-56 1.55E+02 7.45E-05 2.90E-02 2.50E-04 2.50E-04 8.00E 04 Fe-55 1.42E+06 8.13E-09 6.60E-04 1.20E-C3 1.30E-04 1.20E-02 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Co-57 3.90E+05 2.96E-08 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-58 1.02E+05 1.13E-07 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co40 2.77E+06 4.17E-09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Ni43 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni45 1.51 E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Cu44 7.62E+02 1.52E-05 1.20E-01 1.40E-02 1.30E 02 - 9.70E 04 Zn45 3.52E+05 3.28E-08 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn49m 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 Br82 2.12E+03 5.45E-06 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br 83 1.43E+02 8.08E-05 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-84 3.18E+01 3.63E-04 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br85

~

2.87E+00 4.02E-03 7.60E 01 5.00E-02 5.00E-02 2.60E-02 Rb-86 2.69E+04 4.29E-07 1.30E-01 3.00E-02 3.00E-02 3.10E-02 -

Rb-88 1.78E+01 6.49E 04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.00E-02 3.10E 02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr90 1.50E+07 7.70E-10 1.70E-02 1.40E 03 1.40E-02 6.00E-04 Sr 91 5.70E+02 2.03E-05 1.70E 02 1.40E-03 1.40E-02 6.00E-04 Sr92 1.63E+02 7.09E-05 1.70E 02 1.40E-03 1.40E 02 6.00E-04 Y-90 3.85E+03 3.00E 06 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y 91m 4.97E+01 2.32E-04 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y 92 2.12E+02 5.45E 05 2.60E 03 1.00E-05 1.00E-05 4.60E-03 Y-93 6.06E+02 1.91E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Zr 95 9.22E+04 1.25E-07 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Zr 97 1.01E+03 '

1.14E-05 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb 95 5.05E+04 2.29E-07 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Nb-97 7.21E+01 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E 01 Mo-99 3.96E+03 2.92E-00 1.20E-01 7.50E-03 7.50E-03 1.10E-03 Tc-99m 3.61 E+02 3.20E 05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 i Tc 101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Ru-103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E 01 l Ru-105 2.66E+02 4.34E-05 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru 106 5.30E+05 2.18E-08 5.00E 02 1.00E-06 1.00E-06 4.00E 01

SQN ODCM Revision 35 Page 79 of 163 1

Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA I (Pa9e 2 of 3) l Half-Life A. By Fw Fw Fg (minutes) _fj!/3)._ (cow) fgg.311 _fbeeD .

Ag-110m 3.60E+05 3.21 E-08 1.50E-01 5.00C42 5.00E-02 1.70E-02 -

Sb-124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 N/A Sb-125 1.46E+06 7.91E-09 N/A 1.50E-03 1.50E-03 N/A Sn-125 1.39E+04 8.32E 07 N/A N/A N/A N/A {

Te-125m 8.35E+04 1.38E 07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127m 1.57E+05 7.36E-08 1.30E+00 1.00E-03 1.00E 03 7.70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.00E-03 1.00D03 7.70E-02 Te-129m 4.84E+04 2.39E 07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129 6.96E+01 1.66E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 i 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 l

1.30E+00 1.00E 03 1.00E-03 7.70E-02 ]

Te-132 4.69E+03 2.46E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 '

l-130 7.42E+02 1.56E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 1131 1.16E+04 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 1132 1.38E+02 8.37E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 4 1-133 1.25E+03 9.24E-06 2.00E-02 1.20E-02 4.30E-01 2.90E-03 1-134 5.26E+01 2.20E-04 2.00E-02 1.20E-02 4.30E-01 2.90E-03 1-135 3.97E+02 2.91E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 !

Cs-134 1.08E+06 1.06E-08 1.00E-02 8.00E-03 3.00E-01 1.50E-02 '

Cs-136 1.90E+04 6.08E-07 1.00E-02 8.00E-03 3.00E 01 1.50E-02 Cs-137 1.59E+07 7.26E-10 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-138 3.22E+01 3.59E-04 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Ba-139 8.31E+01 1.39E 04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba 140 1.84E+04 6.28E-07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-141 1.83E+01 6.31E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-142 1.07E+01 1.08E-03 5.00E-03 4.00E-04 4.00E-04 3.20E-03 La-140 2.41E+03 4.79E-06 2.50E 03 5.00E-06 5.00E-06 2.00E-04 La 142 9.54E+01 1.21E-04 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ce-141 4.68E+04 2.47E-07 2.50E 03 1.00E-04 1.00E 04 1.20E-03 Ce-143 1.98E+03 5.83E-06 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Pr 143 1.95E+04 5.92E-07 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Pr 144 1.73E+01 6.68E-04 2.50E-03 5.00E-06 5.00E 4.70E-03 Nd-147 1.58E+04 7.31E-07 2.40E-03 5.00E-06 5.00E-06 3.30E-03 W 187 1.43E+03 8.08E-06 1.80E-02 5.00E-04 5.00E 04 1.30E-03 Np 239 3.39E+03 3.41E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ar-41 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A N/A Kr-85 5.64E+06 2.05E-09 N/A N/A N/A N/A

~

Kr 87 7.63E+01 1.51E-04 N/A N/A N/A N/A Kr-88 1.70E+02 6.79E-05 N/A N/A N/A N/A Kr-89 3.16E+00 3.66E-03 N/A N/A N/A N/A Kr-90 5.39E-01 2.14E-02 N/A N/A N/A N/A Xe-131m 1.70E+04 6.79E-07 N/A N/A N/A N/A

. - . . . . = . . _ . - .-=_ ._- ~- .- .- .. .- .- , . . _

SQN ODCM Revision 35 Page 80 of 163 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 3 of 3)

Half-Life A By Fw Fw Fn (minutes) (1/3)_ (cow) M (beef)

Xe-133m 3,15E+03 3.67E-06 N/A N/A N/A N/A Xe-133 7.55E+03 1.53E-06 N/A N/A N/A N/A 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 i

References:

l 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. ;

I Cow-milk transfer factors for lodine, Strontium, and Cesium nuclides are from NUREG/CR 1004, ;

Table 3.17.

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

]

I Beef transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides are from NUREG/CR. ;

1004, Table 3.18.

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

l f

I 5

f b

SQN ODCM Re ision 35 Pagt i of 163 Table 6.3 DOSE CALCULATION FACTORS (Page 1 of 2)

Factor Value Units Reference

, BR, (infant) 1400 m 3/ year ICRP 23 BR, (child) 5500 m3/ year ICRP 23 BR, (teen) 8000 m 3/ year ICRP 23 BR, (adult) 8100 m 3/ year ICRP 23 f, 1 TVA Assumption ft 1 R. G.1.109 (Table E 15) f, 1 TVA Assumption f, O TVA Assumption H 9 g/m 3 TVA Value Ke 0.072 Ukg-h R. G.1.109 (Section 2.C.)

M 40 kg/m2 R. G.1.109 (Section 2.C.)

P 240 kg/m2 R. G.1.109 (Table E-15)

Q,(cow) 64 kg/d NUREG/CR-1004 (Sect. 3.4)

Qr (goat) 08 kg/d NUREG/CR 1004 (Sect. 3.4) r 0.47 NUREG/CR-1004 (Sect. 3.2) to 4.73E+08 seconds R. G.1.109 (Table E 15)

(15 years) tn e 7.78E+06 seconds SON FSAR Section 11.3.9.1 (90 days) t, e 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)

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

(30 days) t,,, 7.78E+06 seconds R. G.1.109 (Table E-15)

(90 days) tg 8.64E+04 seconds SON FSAR Section 11.3.9.1 1 (1 day) , I tg 8.64E+04 seconds NUREG/CR 1004, Table 3.40 (1 day) t, 1.12E+06 seconds NUREG/CR-1004, Table 3.40 (13 days) t,, 2.38E+07 seconds SQN FSAR Section 11.3.9.1 (275 days)

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

U (child) 41 kg/ year R. G.1.109 (Table E-5)

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

U (adult) 110 k9/ year R. G.1.109 (Table E 5)

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

U, (child) 330 1/ year R. G.1.109 (Table E 5)

U,(teen) 400 l/ year R. G.1.109 (Table E 5)

(adult) 310 1/ year R. G.1.109 (Table E 5)

U, U(g infant) 0 kg/ year R. G.1.109 (Table E-5)

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

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

SQN ODCM Revision 35 Page 82 of 163 Table 6.3 DOSE CALCULATION FACTORS (Page 2 of 2)

Factor Value Units Reference Un(adult) 21 kg/ year R. G.1.109 (Table E 5)

Un (infant) 0 kg/ year R. G.1.109 (Table E 5)

U3 (child) 26 k0/ year R. G.1.109 Uable E-5)

Un (teen) 42 kg/ year R. G.1.109 (Table E-5)

Un (adult) 64 kg/ year R. G.1.109 (Table E 5)

U (infant) 0 kg/ year R. G.1.109 (Table E-5)

U (child) 520 kg/ year R. G.1.109 (Table E-5)

U (teen) 630 kg/ year R. G.1.109 (Table E 5)

U (adult) 520 kg';sar R. G.1.109 (Table E-5)

U (infant) 330 Uyear R. G.1.109 (Table E-5)

U.(child) 510 Uyear R. G.1.109 (Table E-5)

U.(teen) 510 Uyear R. G.1.109 (Table E 5)

U.(adult) 730 Uyear R. G.1.109 (Table E 5)

W 0.3 none R. G.1.109 (Table A-2)

Y, 1.85 kg/m2 NUREG/CR-1004 (Table 3.4) 1.18 kg/m2 NUREG/CR-1004 (Table 3.3)

Y',

Y, 0.64 kg/m2 NUREG/CR-1004 (Table 3.3)

Y, 0.57 kO/m2 NUREG/CR-1004 (Table 3.4)

(value selected is for non-leafy vegetables)

((iodines) 7.71 E-07 sec-8 NUREG/CR 1004 (Table 3.10)

(10.4 d half-life) !

((particulates) 5.21E-07 sec-1 NUREG/CR-1004 (Table 3.10)

(15.4 d half life) {

l I

)

L _ _ _ _ _ _

SQN ODCM l Revision 35 l Page 83 of 163 Table 6.4 INGESTION DOSE FACTORS (Page 1 of 8) j (mrem /pCl ingested) j i

ADULT i bone liver ibody thyroid kidney lung gi-lii l H-3 1.05E-07 1.05E-07 1.05E-07 1.0$E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 !

Na 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 I P-32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 2.17E-05 l Cr-51 0.00E+00 0.00E+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 l Mn 54 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 Mn-56 0.00E+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 i Fe-59 4.34E-06 1.02E-05 3.91 E-06 0.00E+00 0.00E+00 2.85E-06 3.40E-05 Co-57 0.00E+00 1.75E-07 2.91E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co-58 0.00E+00 7.45E 07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51 E-05 Co40 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 Ni43 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 Ni45 5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 Cu44 0.00E+00 8.33E-08 3.91 E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 l Zn45 4.84E-06 1.54E-05 6.96E 06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 l Zn49 1.03E-08 1.97E-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00 2.96E-09 Zn49m 1.70E-07 4.08E-07 3.73E-08 0.00E+00 2.47E-07 0.00E+00 2.49E-05

Br 82 0.00E+00 0.00E+00 2.26E 06 0.00E+00 0.00E+00 0.00E+00 2.59E-06 .

Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 !

Br-84 0.00E+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00 4.09E-13 i Br-85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Rb-86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 Rb-88 0.00E+00 6.05E-08 3.21E-08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 Rb-89 0.00E+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E 21 Sr 89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 Sr90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 '

Sr 91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 Sr-92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y 90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y-91m 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y 91 1.41E-07 0.00E+00 3.77E-09 0.00E+00 0.00E+00 0.00E+00 7.76E-05 Y 92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y 93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 Zr 95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 Zr 97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E-04 Nb 95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E 09 0.00E+00 2.10E-05 Nb-97 5.22E-11 1.32E 11 4.82E 12 0.00E+00 1.54E-11 0.00E+00 4.87E-08 Mo-99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E 09 0.00E+00 1.06E-08 3.42E 10 4.13E-07 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 Ru 106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+ 00 1.78E 04

I SQN ODCM Revision 35 Page 84 of 163 Table 6.4 INGESTION DOSE FACTORS (Page 2 of 8)

(mrem /pCiingested) i ADULT l bone liver ibody thyroid kidney lung gi-Ili 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 Sb 125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.00E-00 1.:18E-06 1.97E-05 Sn-125 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0.00E-00 0.00E-00 1.04E-04 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0.00E+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 Te-129 3.14E-08 1.% E-08 7.65E-09 2.41E-08 1.32E-07 0.00E+00 2.37E-08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.00E+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 l-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 l-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06 l-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00 1.02E-07 l-133 1.42E 06 2.47E-06 7.53E 07 3.63E-04 4.31E-06 0.00E+00 2.22E-06 l

l-134 1.06E-07 2.83E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51E-10 l-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06

! Cs-134 6.22E 05 1.48E-04 1.21 E-04 0.00E+00 4.79E-05 1.59E-05 2.59E 06 Cs-136 6.51 E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 i Cs-137 7.97E-05 1.09E-04 7.14E 05 0.00E+00 3.70E-05 1.23E-05 2.11E-06 l Cs-138 5.52E-08 1.09E-07 5.40E-08 0.00E+00 8.01E-08 7.91E-09 4.65E-13

! Ba-139 9.70E-08 6.91E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E 05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E 08 3.56E-11 1.59E-09 0.00E+00 3.31E-11 2.02E-11 2.22E 17 Ba-142 2.13E-08 2.19E-11 1.34E-09 0.00E+00 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 0.00E+00 0.00E+00 0.00E+00 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 0.00E+00 0.00E+00 0.00E+00 4.25E-07 Co-141 9.36E-09 6.33E-09 7.18E-10 0.00E+00 2.94E-09 0.00E+00 2.42E-05 Co-143 1.65E-09 1.22E-06 1.35E-10 0.00E+00 5.37E 10 0.00E+00 4.56E-05 l

Co-144 4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.13E-09 0.00E+00 4.03E-05 Pr-144 3.01E 11 1.25E-11 1.53E-12 0.00E+00 7.05E 12 0.00E+00 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E 10 0.00E+00 4.25E-09 0.00E+00 3.49E-05 W 187 1.03E-07 8.61E-08 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 Np 239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 0.00E+00 2.40E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

l

REFERENCES:

Regulatory Guide 1.109, Table E-11.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125. Sb-124 and Sb-125 are from NUREG-0172 Ace Soecific Radiation Dose Commitment Factors for a One Year Chronic intake..

November,1977, Table 4.

l l

l

SQN ODCM Revision 35 Page 85 of 163 Table 6.4 INGESTION DOSE FACTORS (Page 3 of 8) mrem /pCiingested)

TEEN t bone liver tbody thyroid kidney lung gi-Ili H-3 1.06E-07 1.06E-07 1.06E-07 1.06E 07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E 07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E 06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E 05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 Cr-51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21E-05 Mn-56 0.00E+00 1.58E-07 2.81 E-08 0.00E+00 2.00E-07 0.00E+00 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 0.00E+00 0.00E+00 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 ,

Co-57 0.00E+00 2.3BE-07 3.99E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co-58 0.00E+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 Co-60 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 0.WE+00 0.00E+00 0.00E+00 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 Cu-64 0.00E+00 1.15E-07 5.41E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 Zn-65 b.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 Zn-69m 2.40E-07 5.66E-07 5.19E-08 0.00E+00 3.44E-07 0.00E+00 3.11 E-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 0.00E+00 3.66E-05 Sr 92 3.05E-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E-05 Y-90 1.37E-08 0.00E+00 3.69E 10 0.00E+00 0.00E+00 0.00E+00 1.13E-04 Y-91m 1.29E-10 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09 Y-91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 Y-92 1.21E-09 0.00E+00 3.50E 11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y-93 3.83E-09 0.00E+00 1.05E-10 0.00E+00 0.00E+00 0.00E+00 1.17E-04 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 2.51 E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 Nb-97 7.37E-11 1.83E-11 6.68E-12 0.00E+00 2.14E-11 0.00E+00 4.37E-07 Mo-99 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.08E-05 Tc.99m 3.32E-10 9.26E 10 1.20E-08 0.00E+00 1.38E-08 5.14E .10 6.08E-07 Tc 101 3.60E-10 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E 10 8.75E 17 Ru-103 2.55E-07 0.00E+00 1.09E-07 0.00E+00 8.99E 07 0.00E+00 2.13E-05 Ru-105 2.18E-08 0.00E+00 8.46E-09 0.00E+00 2.75E-07 0.00E+00 1.76E-05 Ru-106 3.92E-06 0.00E+00 4.94E-07 0.00E+00 7.56E-06 0.00E+00 1.88E-04

l SQN ODCM Revision 35 Page 86 of 163 Table 6.4 INGESTION DOSE FACTORS (mrem /pCiingested)

(Page 4 of 8)

TEEN bone liver ibody thyroid kidney lung Gi-lli Ag-110m 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 Sb-124 3.87E-06 7.13E-08 1.51E-06 8.78E-09 0.00E-00 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0.00E+00 2.18E-06 1.93E-05 Sn-125 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0.00E+00 0.00E+00 1.12E-04 Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.00E+00 0.00E+00 1.13E-05 Te-127m 9.67E-06 3.43E 06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.22E-05 Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0.00E+00 2.45E-07 Te 131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0.00E+00 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0.00E+00 7.00E-05 l130 1.03E 06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.00E+00 2.29E-06 l-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.00E+00 1.62E-06 l-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 l133 2.01E-06 3.41E-06 1.04E 06 4.76E-04 5.98E-06 0.00E+00 2.58E-06 l-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 l135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 0.00E+00 1.74E-06 Cs-134 8.37E-05 1.97E 04 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E 05 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E 04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E 08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 Ba-139 1.39E 07 9.78E 11 4.05E-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 Ba 140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E 11 2.24E-09 0.00E+00 4.65E 11 3.43E 11 1.43E-13 Ba-142 2.99E 08 2.99E 11 1.84E-09 0.00E+00 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E 11 0.00E+00 0.00E+00 0.00E+00 2.42E-06 Co-141 1.33E-08 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E-05 Co-143 2.35E-09 1.71E-06 1.91E-10 0.00E+00 7.67E 10 0.00E+00 5.14E-05 Co-144 6.96E-07 2.88E-07 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 Pr 143 1.31E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-09 0.00E+00 4.31E-05 Pr 144 4.30E 11 1.76E 11 2.18E 12 0.00E+00 1.01E-11 0.00E+00 4.74E-14 Nd 147 9.38E 09 1.02E 08 6.11 E-10 0.00E+00 5.99E 09 0.00E+00 3.68E-05 W-187 1.46E-07 1.19E 07 4.17E-08 0.00E+00 0.00E+00 0.00E+00 3.22E-05 Np-239 1.76E-09 1.66E 10 9.22E-11 0.00E+00 5.21E-10 0.00E+00 2.67E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

REFERENCES:

Regulatory Guide 1.109, Table E-12.

Dose Factors for Co-57, Zn-69m, Br-82. Nb-97, Sn-125, Sb-124 and Sb.125 are from NUREG-0172 Ane Soecific Radiation Dose Commitment Factors for a One Year Chronic Intake..

November,1977. Table 4.

9 l - _ ______ _. _ _ _

I l

SQN ODCM Revision 35 Page 87 of 163 Table 6.4 INGESTION DOSE FACTORS (mrem /pCiingested)

(Page 5 of 8)

CHILD bone liver ibody thyroid kidney lung gi-Ili H-3 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.2SE-04 3.86E-05 3.18E-05 0.00E+00 0.00E+00 0.00E+00 2.28E-05 Cr-51 0.00E+00 0.00E+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 0.00E+00 1.07E-05 2.85E-06 0.00E+00 3.00E-06 0.00E+00 8.98E-06 Mn-56 0.00E+00 3.34E-07 7.54E-08 0.00E+00 4.04E-07 0.00E+00 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 0.00E+00 0.00E+00 3.45E-06 1.13E-06 ,

Fe-59 1.65E-05 2.67E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05 Co-57 0.00E+00 4.93E-07 9.98E-07 0.00E+00 0.00E+00 0.00E+00 4.04E-06 Co-58 0.00E+00 1.80E 06 5.51 E-06 0.00E+00 0.00E+00 0.00E+00 1.05E-05 Co40 0.00E+00 5.29E-06 1.56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 0.00E+00 0.00E+00 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 0.00E+00 0.00E+00 2.56E-05 Cu44 0.00E+00 2.45E-07 1.48E-07 0.00E+00 5.92E-07 0.00E+00 1.15E-05 Zn45 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 Zn49 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00 3.99E-06 Zn49m 7.10E-07 1.21E-06 1.43E-07 0.00E+00 7.03E-07 0.00E+00 3.94E-05 Br-82 0.00E+00 0.00E+00 7.55E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 !

Br-83 0.00E+00 0.00E+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Br-84 0.00E+00 0.00E+00 1.98E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Br-85 0.00E+00 0.00E+00 9.12E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 Rb-86 0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00 4.31 E-06 Rb-88 0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 0.00E+00 9.32E-09 j Rb 89 0.00E+00 1.17E-07 1.04E-07 0.00E+00 0.00E+00 0.00E+00 1.02E-09 ,

Sr-89 1.32E-03 0.00E+00 3.77E-05 0.00E+00 0.00E+00 0.00E+00 5.11E-05 Sr90 1.70E-02 0.00E+00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04 Sr-91 2.40E-05 0.00E+00 9.06E-07 0.00E+00 0.00E+00 0.00E+00 5.30E-05 Sr92 9.03E-06 0.00E+00 3.62E-07 0.00E+00 0.00E+00 0.00E+00 1.71E-04 I Y 90 4.11E-08 0.00E+00 1.10E-09 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Y 91m 3.82E-10 0.00E+00 1.39E 11 0.00E+00 0.00E+00 0.00E+00 7.48E-07 !

Y 91 6.02E-07 0.00E+00 1.61E-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 Zr 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-09 0.00E+00 1.62E-05 Nb 97 2.17E-10 3.92E-11 1.83E-11 0.00E+00 4.35E-11 0.00E+00 1.21E-05 Mo-99 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E 05 0.00E+00 1.10E-05 Tc-99m 9.23E 10 1.81E-09 3.00E-08 0.00E+00 2.63E 08 9.19E 10 1.03E-06 To-101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91 E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 0.00E+00 2.81E-07 0.00E+00 1.84E-06 0.00E+00 1.89E-05 Ru 105 6.45E-08 0.00E+00 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21E-05 Ru-106 1.17E-05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E+ 00 1.82E 04

i i

SQN ODCM '!

Revision 35 l Page 88 of163 :

Table 6.4 INGESTION DOSE FACTORS (mrem /pCiingested)

(Page 6 of 8)

CHILD bone liver ibody thyroid ' kidney lung gi-Ili Ag-110m 5.39E 07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 Sb-124 1.11E-05 1.44E 07 3.89E-06 2.45E-08 0.00E+00 6.16E-06 6.94E-05 Sb 125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0.00E+00 3.99E-06 1.71E-05 Sn-125 3.55E 05 5.35E-07 1.59E-06 5.55E-07 0.00E+00 0.00E+00 1.10E-05 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.00E+00 2.34E-05 Te-127 4.71E 07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 0.00E+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.00E+00 8.34E-06 Te-131m 7.20E-06 2.49E 06 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E 08 6.35E-08 2.51E-07 0.00E+00 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0.00E+00 4.50E-05 l-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 l-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 l132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.2SE-06 0.00E+00 1.73E-06 l-133 5.92E-06 7.32E 06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.95E-06 l-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16E-07 l-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 Cs-134 2.34E 04 3.84E 04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1.96E-06 i Cs 138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-08 0.00E+00 1.93E-10 1.30E 10 2.39E-05 l Ba-140 8.31 E-05 7.28E-08 4.85E 06 0.00E+00 2.37E 08 4.34E-08 4.21E-05 l Ba-141 2.00E-07 1.12E 10 6.51E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 l Ba 142 8.74E-08 6.29E-11 4.88E-09 0.00E+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E 09 1.19E-09 0.00E+00 0.00E+00 0.00E+00 9.84E-05 La-142 5.24E 10 1.67E-10 5.23E-11 0.00E+00 0.00E+00 0.00E+00 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 0.00E+00 8.68E-09 0.00E+00 2.47E-05 Co-143 6.99E-09 3.79E-06 5.49E-10 0.00E+00 1.59E-09 0.00E+00 5.55E-05 Ce 144 2.08E-06 6.52E-07 1.11E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-04 l Pr-143 3.93E-08 1.18E-08 1.95E-09 0.00E+00 6.39E-09 0.00E+00 4.24E-05 Pr 144 1.29E-10 3.99E-11 6.49E-12 0.00E+00 2.11E-11 0.00E+00 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 W 187 4.29E-07 2.54E-07 1.14E-07 0.00E+00 0.00E+00 0.00E+00 3.57E-05 Np-239 5.25E-09 3.77E 10 2.65E 10 0.00E+00 1.09E-09 0.00E+00 2.79E-05 NOTE: The tritium dose factor for bone is assumed to be eq El to the total body dose factor.

REFERENCES:

Regulatory Guide 1.109 Table E-13.

Dose Factors for Co-57, Zn-69m. Br 82, Nb 97, Sn-125, Sb-124 and Sb-125 are from NUREG-0172 Ace Specific Radiation Dose Commitment Factors for a One Year Chronic Intake..

November,1977. Table 4.

1 SQN ODCM Revision 35 Page 89 of 163 <

. l 1

Table 6.4 l lNGESTION DOSE FACTORS (mrem /pClingested)

(Page 7 of 8) ;

INFANT l bone liver ibody thyroid iddney lung gi-Ili l H-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 ' 3.08E-07 l C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01 E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01 E-05 P-32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00 0.00E+00 2.30E-05 Cr 51 0.00E+00 0.00E+00 1.41E 08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 0.00E+00 1.99E-05 4.51 E-06 0.00E+00 4.41E-06 0.00E+00 7.31E-06 Mn-56 0.00E+00 8.18E-07 1.41 E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E 05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05 Co-57 0.00E+00 1.15E-06 1.87E-06 0.00E+00 0.00E+00 0.00E+00 3.92E-06 Co-58 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 0.00E+00 8.97E-06 Co40 0.00E+00 1.08E-05 2.55E-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 Ni43 6.34E 04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 Ni45 4.70E 06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.05E 05 Cu44 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05 Zn45 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 Zn49 9 33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E-05 Zn49m 1.50E-06 3.06E-06 2.79E-07 0.00E+00 1.24E-06 0.00E+00 4.24E-05 Br-82 0.00E+00 0.00E+00 1.27E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br43 0.00E+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br44 0.00E+00 0.00E+00 3.82E-07 ' O.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.94E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.70E-04 8.40E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 Rb-88 0.00E+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 Rb-89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-08 Sr89 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 4.71 E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 Sr 91 5.00E-05 0.00E+00 1.81E-06 0.00E+00 0.00E+00 0.00E+00 5.92E-05 Sr-92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0.00E+00 2.07E-04 !

.Y-90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 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-00 0.00E+00 2.15E 10 0.00E+00 0.00E+00 0.00E+00 1.46E-04 Y-93 2.43E-08 0.00E+00 6.62E 10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 !

Zr-95 2.06E-07 5.02E-08 3.56E 08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 I Zr 97 1.48E-08 2.54E 09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 Nb 95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E 08 0.00E+00 1.46E-05 Nt>97 4.59E 10 9.79E-11 3.53E 11 0.00E+00 7.65E-11 0.00E+00 3.09E-05 Mo-99 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 To 99m 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 j To 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

l SQN ODCM Revision 35 Page 90 of 163 Table 6.4 INGESTION DOSE FACTORS (mrem /pCiingested)

(Page 8 of 8)

INFANT bone liver ibody thyroid kidney lung gi-Ili Ag-110m 9.96E-07 7.27E-07 4.81E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 Sb-124 2.14E-05 3.15E 07 6.63E-06 5.68E-08 0.00E+00 1.34E-05 6.60E 05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72E-06 1.64E-05 Sn-125 7.41E-05 1.38E-06 3.29E-06 1.36E-06 0.00E+00 0.00E+00 1.11E-04 Te 125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1.11 E-05 ~

Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.00E+00 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.00E+00 2.10E-05 i Te-129m 1.00E-04 3.43E 05 1.54E 3.84E-05 2.50E-04 0.00E+00 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0.00E+00 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.00E+00 7.11E-06 Te-132 2.08E-05 1.03E 05 9.61 E-06 1.52E-05 6.44E-05 0.00E+00 3.81E-05 l-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 l-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00 1.51E-06 l-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0.00E+00 2.73E-06 l-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.00E+00 3.08E-06 l-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.00E+00 1.84E-06 l-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81E-04 7.42E-05 1.91E 06 Cs-136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11 E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91E 06 i Cs-138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 l Ba-139 8.81 E-07 5.84E-10 2.55E-08 0.00E+00 3.51E-10 3.54E-10 5.58E-05 l Ba 140 1.71 E-04 1.71E-07 8.81E-06 0.00E+00 4.06E 08 1.05E-07 4.20E-05 l 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 2.11 E-08 8.32E-09 2.14E 09 0.00E+00 0.00E+00 0.00E+00 9.77E-05 l La 142 1.10E-09 4.04E-10 9.67E-11 0.00E+00 0.00E+00 0.00E+00 6.86E-05 l Ce-141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 I Co-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E 07 0.00E+00 4.93E-07 0.00E+00 1.71E-04 Pr 143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-06 0.00E+00 4.29E-05 ;

Pr 144 2.74E-10 1.06E-10 1.38E-11 0.00E+00 3.84E 11 0.00E+00 4.93E-06 Nd 147 5.53E-08 5.68E-08 3.48E-09 0.00E+00 2.19E-08 0.00E+00 3.60E-05 W 187 9.03E-07 6.28E-07 2.17E-07 0.00E+00 0.00E+00 0.00E+00 3.69E-05 Np 239 1.11 E-08 9.93E 10 5.61E 10 0.00E+00 1.98E-09 0.00E+ 00 2.87E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. .,

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REFERENCES:

Regulatory Guide 1.109. Table E-14. l Dose Factors for Co-57, Zn-69m, Br-82. Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG- l l

0172 Ace Soecific Radiation Dose Commitment Factors for a One Year Chronic intake..

November,1977, Table 4.

1

SQN ODCM Revision 35 Page 91 of 163 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH

( Ci/kg per Cl/ml)

H-3 9.0E-01 Y 91m 2.5E+01 1-134 4.0E+01 C-14 4.6E+03 Y 91 2.5E+01 1-135 4.0E+01 Na 24 1.0E+02 Y-92 2.5E+01 Cs-134 1.9E+03 P-32 1.0E+05 Y 93 2.5E+01 Cs-136 1.9E+03 Cr 51 2.0E+02 Zr-95 3.3E+00 Cs-137 1.9E+03 Mn-54 4.0E+02 Zr-97 3.3E+00 Cs-138 1.9E+03 Mn-56 4.0E+02 Nb-95 3.0E+04 Ba-139 4.0E+00 Fe-55 1.0E+02 Nb 97 3.0E+04 Ba-140 4.0E+00 Fe-59 1.0E+02 Mo-99 1.0E+01 Ba-141 4.0E+00 Co-57 5.0E+01 Tc-99m 1.5E+01 Ba-142 4.0E+00 Co-58 5.0E+01 Tc-101 1.5E+01 La-140 2.5E+01 Co-60 5.0E+01 Ru-103 - 1.0E+01 La-144 2.5E+01 Ni-63 1.0E+02 Ru-105 ' 1.0E+01 Ce-141 1.0E+00 Ni-65 1.0E+02 Ru-106 1.0E+01 Co-143 1.0E+00 Cu-64 5.0E+01 Ag-110m 2.31E+00 Ce-144 1.0E+00 Zn-65 2.0E+03 Sb-124 1.0E+00 Pr 144 2.5E+01 Zn-69 2.0E+03 Sb 125 1.0E+00 Pr-143 2.5E+01 Zn-69m 2.0E+03 Sn-125 3.0E+03 Nd-147 2.5E+01 Br-82 4.2E+02 Te-125m 4.0E+02 W-187 1.2E+03 Br-83 4.2E+02 Te 127m 4.0E+02 Np-239 1.0E+01 Br-84 4.2E+02 Te-127 4.0E+02 Br 85 4.2E+02 Te-129m 4.0E+02 Rb 86 2.0E+03 - Te-129 4.0E+02 Rb88 2.0E+03 Te-131m 4.0E+02 Rb-89 2.0E+03 Te-131 4.0E+02 Sr 89 5.6E+01 Te-132 4.0E+02 Sr 90 5.6E+01 1-130 4.0E+01 Sr-91 5.6E+01 1-131 4.0E+01 Sr 92 5.6E+01 1-132 4.0E+01 Y 90 2.5E+01 1-133 4.0E+01

REFERENCES:

Bioaccumulation factors for Ag 110m, Sb-124, Sb 125 and Sn-125 are from ORNL-4992,"A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment,"

March 1976, Table 4.12A.

Bioaccumulation factors for lodine, Cesium, and Strontium nuclides are from NUREG/CR-1004, Table 3.2.4.

All other nuclides' bioaccumulation factors are from Regulatory Guide 1.109, Table A-1, 4

1 SQN ODCM Revision 35 Page 92 of 163 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /h per pCi/m2)

(Page 1 of 2)

Nuclide ptal Body 3, tin H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P 32 0.0 0.0 Cr 51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-57 1.77E-09 2.21E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Zn-69m 5.50E-09 6.59E-09 Br-82 3.18E-08 3.90E-08 Br 83 6.40E-11 9.30E 11 Br84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-06 Sr-89 5.60E 13 6.50E 13 Sr 91 7.10E-09 8.30E-09 Sr92 9.00E-09 1.00E-08 Y 90 2.20E-12 2.60E-12 Y 91m 3.80E-09 4.40E-09 Y 91 2.40E-11 2.70E 11 Y-92 1.60E-09 1.90E-09 Y 93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr 97 5.50E-09 6.40E-09 Nb 95 5.10E-09 6.00E-09 Nb 97 8.11E-09 1.00E-08 Mo-99 1.90E-09 2.20E-09 l Tc-99m 9.60E-10 1.10E-09

) Tc 101 2.70E-09 3.00E-09 Ru 103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 l

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SQN ODCM j Revision 35 Pa9e 93 of 163 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND i (mrem /h per pCi/m2) !

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Nuclide Total Body Skin !

Ag-110m 1.80E 08 2.10E 08 Sb-124 2.17E-08 2.57E 08 ,

Sb-125 5.48E-09 6.80E-09 i Sn-125 3.58E-09 4.51E-09 l Te-125m 3.50E 11 4.80E-11 Te-127m 1.10E 12 1.30E-12 Te 127 1.00E 11 1.10E-11 l Te-129m 7.70E 10 9.00E-10 ;

Te-129 7.10E 10 8.40E-10 I Te-131m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-08 ,

Te-132 1.70E-09 2.00E-09 l l-130 1.40E-08 1.70E-08 l-131 2.80E 09 3.40E-09 l-132 1.70E-08 2.00E-08 l-133 3.70E-09 4.50E-09 l-134 1.60E-08 1.90E-08 l-135 1.20E-08 1.40E-08 i Cs 134 1.20E 08 1.40E-06 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E 08 1.80E-08 Ce-141 5.50E 10 6.20E 10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E 10 3.70E-10 Pr 143 0.0 0.0 Pr-144 2.00E 10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np 239 9.50E-10 1.10E-09 l

REFERENCES:

Regulatory Guide 1.109. Table E-6. i Dose Far: tors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, St>124 and Sb-125 are from Dose-Rate Conversion Factors for Extemal Exoosure to Photon and Electron Radiation from Radionuclides Occurrina in Routine Releases from Nuclear Fuel Cvele Facilities. D. C. Kocher, Health Physics l Volume 38, Apnl1980. '

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SQN ODCM Revision 35 Page 94 of 163 Figure 6.1 LIQUID EFFLUENT RELEASE POINTS l Steam Generenor ,

Turbine Buil6ng Condeneste Blowdown l Sump Demaneralizer ,,

System -m '

Turbine Buildng SG SG High Crud 8' SA* { S4 j' Sump (30000 gel)

Tank 1 teos png. t p 20000 gal !

O RM-90-212 l aogan, y p t}

High Crud i Tank 2 so mm ,

20000 gal 180 GPS. Finah Tann sosc j

{ I, k

Neutralization Tar

1JtuM120,121 Q $

180 gpg, (19000 gal)

Unit 2 l

so so se sc V f U Non-Reclaimable -AL .22. J L J L Waste Tank Low Volume (11000 gal) iso M U I, Yard Waste

' , Pond Treatment Pmd 80 gpm P sc Drondose f

Pimah Tank Composite Sampler 3 -

0 RM-90-225 0 !

__ ___ . 2au-80120.121 o -

p y Radweste r, System " D' h (see Figure j 0-RM40122 Pond l

6.21 l

ERCW Co@g pp p p Tower

~{ U Blowdown Tennessee River "A" Train 0 RE-90133,140

B* Trein 0 R E-90-134.141 l

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SQN ODCM Revision 35 Page 95 of 163 i

l Figure 6.2 LIQUID RADWASTE SYSTEM Reactor Building Auxiliary Building Drains Drains V V ,

l V

Tritiated Drain y l Collector Tank =

Floor Drain Collector Tank (occasional use)

Chemical 20 gpm

U "

Drain Tank (600 gal) Condensate Vendor Domineralizer Radwaste w,,,,

Sptam Evaporator Laundry and Hot Shower l y g y !

Tanks A & B %. T Pm Waste Distillate (600 gal)

" " Tanks Monitor Tank Cask Decon (8500 cal)

Collector Tank '

(22000 gal) (15000 gal) 8 y

125 gpm 125 gpm l

U (routine release path) V I (occasional release path) 0-RM-9012S y TO COOLING TOWER BLOWDOWN

SQN ODCM Revision 35 Page 96 of 163 l

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l SECTION 7.0 GASEOUS EFFLUENTS l

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SON ODCM Revision 35 Page 97 of 163 l 1

i SECTION 7.0 GASEOUS EFFLUENTS l l

}fEt. EASE POINTS DESCRIPTION l Thes cre six major exhaust pathways at Sequoyah Nuclear Plant that are monitored for airbome l33 effluents. These are: a Condenser Vacuum Exhaust for each unit, a Service Building Exhaust, an Auxiliary Building Exhaust and a Shield Building Exhaust for each unit. Figure 7.1 provides an outline of the airbome effluent release and discharge points with associated radiation monitor identifications. I Condenser Vacuum Exhaust The Condenser Vacuum Exhausts (CVEs) are located in the turbine building. They exhaust at a l maximum design flow rate of 45 cubic feet per minute. They are monitored for routine releases by l 33 rediation monitors 1,2-RM-90-119.

Service Buildino Vent Various low-level sources exhaust to the Service Bui! ding Vent. This exhausts at a total design flow of approximately 14,950 cfm. The portion of this total flow originating from the Titration Room, the Waste Baler Room, and the Chemistry Lab is monitored by radiation monitor 0-RM 1 132.

Auxiliary Buildina Exhaust (see Figure 7.2 for detail)

The annulus vacuum primino system exhausts through the containment vent to the Auxiliary ;

Building. The Auxiliary Builo,ag Exhaust consists of the Auxiliary Building General Exhaust System and the Fuel Handling Exhaust and they cumulatively exhaust at a maximum design flow of 228,000 cfm. The exhaust is monitored by radiation monitor 0-RM-90-101.

Shield Buildino Vent (see Figure 7.2 for detail)

The Auxiliary Building Gas Treatment System (ABGTS) draws from the Auxiliary Building and exhausts to the waste gas header. There are nine Waste Gas Decay Tanks (WGDTs) that also empty into this header. Either ABGTS or the Emergency Gas Treatment System (EGTS) is run to release a WGDT. Each WGDT has a design capacity of 600 cubic feet at STP and a design release rate of 22.5 cim. Both the Containment Purge and the incore Instrument Room Purge l33 from each unit tie into the waste gas header. The Containment Purge exhausts at a maximum of 28,000 cfm and is monitored by radiation monitors 1,2-RM-90-130,131. If the incore Instrument Room Purge is operating exclusively, it exhausts at 800 cfm. Under emergency conditions, and sometimes during normal operation, the EGTS is used to draw a vacuum in the annulus and j exhaust to the Shield Building Vent. Auxiliary Building isolation starts both the ABGTS and EGTS. !

The common header exhausts to the Shield Building Exhaust. There is one exhaust for each unit. l This exhausts at a maximum design flow of 28,000 cfm and is monitored by radiation monitors 1,2-RM-90-400.

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SON ODCM Revision 35 Page 98 of 163 7.1 INSTRUMENT SETPOINTS Airbome effluent monitor setpoints are determined to ensure that the dose rate at the UNRESTRICTED AREA BOUNDARY does not exceed the dose rate limits given in ODCM 3 ~3 Control 1.2.2.1 and to identify unexpected releases.

7.1.1 Release Point Monitor Setpoints (1,2-RM 90-130,-131,0-RM-90-118) 7.1.1.1 Containment Purge Effluent Monitors (1,2-RM-90-130,-131)

These monitors are set at a cpm value equal to a percentage of the Technical Specification Limit of 8.5x10-3 Ci/cc as Xe-133 (Technical Specification 3.3.2.1 Table 3.3-4).

7.1.1.2 Waste Gas Decay Tank Effluent Monitor (0-RM-90118)

For each release from a waste gas decay tank, two setpoints are calculated for the monitor: one based on the expected response of the monitor to the radioactivity in the effluent stream; and a calculated maximum setpoint which corresponds to the most restrictive dose rate limit given in ODCM Control 1.2.2.1. The expected monitor response is calculated as described below in Equation 7.1. The maximum calculated setpoint is calculated as described below in Equation 7.2.

A comparison is made between these two calculated setpoints to determine which is used. The actual monitor setpoint for the release is set equal to X times the expected monitor response, or to the maximum calculated setpoint, whichever is less. X is an administrative factor designed to account for expected variations in monitor response (it will be defined in approved plant instructions). The X times expected response setpoint allows for the identification of any release of radioactivity above the expected amount. The maximum calculated setpoint ensures that the release will be stopped if it exceeds the dose rate limits.

Expected Monitor Response R=B+ I eff Ca i (7.1)

I where B = monitor background, cpm.

eff, = efficiency factor for the monitor for nuclide i, cpm per Ci/cc.

C, = measured concentration of nuclide i, Ci/cc.

Calculated Maximum Setooint The calculated maximum setpoint, S. in cpm, corresponding to the dose rate limit is determined using the following equation:

DR n S. = ( A SF ( (R - B))) + B (7.2)

DR 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 procedures.

DR, = the dose rate limit, mrem / year.

= 500 mrem / year to the total body for noble gases,

= 3000 mrem / year to the skin for noble gases, and

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i SON ODCM Revision 35 Page 99 of 163 DR = the calculated dose rate for the release, mrem / year.

= DRTs for total body (as described in Section 7.2.3.1),

= DRsfor skin (as described in Section 7.2.3.2), and R = expected monitor response (as calculated in Equation 7.1), cpm.

B = the monitor background, cpm.

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7.1.2 Discharge Point Monitor Setpoints (1,2-RE-90-400,0-RM 90-101,0-RM-90-132,1,2-RM-90-119)

A normal default setpoint is determined for each discharge point monitor as described in Section 7.1.3. These setpoints on the discharge monitors will routinely be set equal to the default setpoints. When release permits are generated, the expected response and maximum calculated 1 setpoints are calculated for the appropriate discharge monitor as described in Section 7.1.1.2. A comparison is made between the three setpoints as described below to choose the appropriate setpoint for the monitor during the release (after the release, the monitor should be retumed to the l default setpoint). For almost all releases, the setpoint for the discharge monitor will be the default setpoint.

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1. If X1 times the expected monitor response is less than the calculated maximum setpoint and less than the normal default setpoint, and the default setpoint is less than the calculated maximum setpoint, then the setpoint shall be set equal to the normal default setpoint.

IF X*R<S, AND X

R < S ,,, AND So .,,, < S ,

THEN Setpoint = 3S ,,,

2. If X1 times the expected monitor response is less than the calculated maximum setpoint, but greater than the normal default setpoint, and the normal default setpoint is less than the calculated maximum setpoint, then the setpoint shall be set equal to X1 times the expected monitor response:

IF X

R < S , AND X*R>S ,,, AND S 3 ,,,<S ,

g THEN Setpoint = X

R

3. If X1 times the expected monitor response is less than the calculated maximum setpoint, and less than the normal default setpoint, and the normal default setpoint is greater than the calculated maximum setpoint, then the setpoint shall be set equal to the calculated maximum setpoint:

IF X*R<S , AND X

R < 3S ,,, AND Seafad> S mx THEN Setpoint = S ,

4. If X1 times the expected monitor response is greater than the calculated maximum setpoint ,

the release should not be made under the assumed plant release conditions.

1 X is an administrative factor designed to account for expected variations in monitor response, it will bc afined in approved plant instnJctions.

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SON ODCM Revision 35 Page 100 of 163 7.1.3 Discharge Point Effluent Monitor Default Setpoints 7.1.3.1 Shield Building Vents (1,2-RE 90-400), Auxiliary Building Vent (0-RM-90-101), and Service Building Vent (0-RM-90-132)

These discharge point effluent monitors are set to ensure compliance with ODCM Control 1.2.2.1.

The default setpoints are controlled by plant instructions and are based on design flowrate, release rate limits equivalent to the dose rate limits in ODCM Control 1.2.2.1, and the monitor efficiencies. D The default setpoints for the shield building monitors are calculated in units of pCi/sec.

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

This discharge point effluent monitor is set to ensure compliance with ODCM Control 1.2.2.1 and to identify the presence of primary to secondary leakage of radioactivity. The default setpoint is determined in one of two ways: by calculating the maximum calculated setpoint described by Equation 7.2 for Xe-133, and then taking a percentage of this value as the setpoint; or by defining the setpoint as a low value above the normal background. The default setpoint will be defined in 33 plant instructions. Once a primary to secondary leak is identified, the setpoint on this monitor may be adjusted upward to enable it to be used to identify any further increases in the leak rate.

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Revision 35 !

Page 101 of 163 7.2 GASEOUS EFFLUENTS - DOSE RATES .

I 7.2.1 (Deleted) 7.2.2 RELEASE SAMPLING >

i Prior to each release (excluding an incore instrument Room Purge), a grab sample is taken and analyzed to determine the concentration, Ci/cc, of each noble gas nuclide. On at least a weekly basis, filters are analyzed to determine the amount of iodines and pasticulates released.

Composite samples are maintained (as required by Table 2.2-2) to determine the concentration of certain nuclides (Sr 89, Sr 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 7.3,7.4, and 7.5. The actual measured concentrations will be used for the dose calculations described in Section 7.6.

7.2.3 NOBLE GAS DOSE RATES Dose rates are calculated for total body and skin due to submersion within a cloud of noble gases j using a semi-infinite cloud model.

7.2.3.1 Total Body Dose Rate ,

The dose rate to the total body, DR Ts in mrem / year, is calculated using the following equation:

DRyg = (X/ Q) F I C, DFB, (7.3) i i where !

1/ O = relative concentration, s/m 3. Relative air concentrations are calculated for the unrestricted 5 area boundary in each of the sixteen sectors as described in Section 7.8.2 using the 33 i

historical meteorological data for the period 1972-1975 given in Table 7.2. For dose rate calculations, the highest value from the sixteen unrestricted area boundary locations is 33 used.

= 5.12E-06 s/m3 (from Table 7.1).

F = flowrate of effluent stream, cc/s.

Ci = concentration of noble gas nuclide iin effluent stream, CL/cc, DFB, = total body dose factor due to gamma radiation for noble gas nuclide i, mrem /y per pCi/m3 (Table 7.3).

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SON ODCM l Revision 35 Page 102 of 163 7.2.3.2 Skin Dose Rate -

l The dose rate to the skin, DRs in mrem / year, is calculated using the following equation:

/

DRs = (% Q) F I C,(DFS, + 1.11 DF) (7.4)

I where X/ Q = relative concentration, s/m .3 Relative air concentrations are calculated for the unrestricted l 33 l area boundary in each of the sixteen sectors as described in Section 7.8.2 using the l historical meteorological data for the period 1972-1975 given in Table 7.2. For dose rate I calculations, the highest value from the sixteen unrestricted area boundary locations is used.

33 l 3

= 5.12E-06 s/m (from Table 7.1). l F- = flowrate of effluent stream, cc/s.

C, = concentration of noble gas nuclide iin effluent stream. Ci/cc.

DFSi = skin dose factor due to beta radiation for noble gas nuclide i, mrem /y per Cl/m3 (Table 7.3).

1.11 = the average ratio of tissue to air energy absorption coefficients, mrem / mrad.

DFg = dose conversion factor for extemal gamma for noble gas nuclide i, mrad /y per pCi/m3 (Table 7.3).

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SQN ODCM Revision 35 Page 103 of 163 7,2.41-131,I-133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS - ORGAN DOSE RATE Organ dose rates due to 1131,1-133 Tritium and all radionuclides in particulate form with half-lives of greater than 8 days, DR in mrem /y, are calculated for all age groups (adult, teen, child, as and infant) and all organs (bone, liver, total body, thyroid, kidney, lung, and GI Tract) using the following equation:

DR yg = F [ C 7(X /Q)[R7+Rc7p] + I C,[(1 Q)R/

n+ (D/Q) [RCPi + RG;))] (7.5)

I where:

F = flowrate of effluent stream, cc/s.

C7 = concentration of tritium in effluent stream, pCl/cc.

%/ Q = relative concentration, s/m 3. Relative air concentrations are calculated forthe unrestricted 33 area boundary in each of the sixteen sectors as described in Section 7.8.2 using the historical meteorological data for the period 1972-1975 given in Table 7.2. For dose rate calculations, the highest value from the sixteen unrestricted area boundary locations is 33 used.

3

= 5.12E-06 s/m (from Table 7.1).

R,7 = inhalation dose factor for tritium, mrem /y per Ci/m 3. Dose factor is calculated as described in Section 7.7.13.

RCTP= Grass-cow-milk dose factor for tritium, mrem /y per Ci/m3 . Dose factor is calculated as described in Section 7.7.7.

C, = concentration of nuclide iin effluent stream, Ci/cc. t R H = inhalation dose factor for each identified nuclide i, mrem /y per Cl/m3 . Dose factors are calculated as described in Section 7.7.13.

D/Q = relative deposition,1/m2. Relative deposition is calculated for the unrestricted area l boundary in each of the sixteen sectors as described in Section 7.8.3 using the historical l33 meteorological data for the period 1972-1975 given in Table 7.2. For dose rate calculations, the highest value from the sixteen unrestricted area boundary locations is 33 used.

= 1.29E-081/m 2(from Table 7.1). l RCPi = Grass-cow-milk dose factor for each identified nuclide i, m2-mrem /y per pCi/s. Dose l

factors are calculated as described in Section 7.7.1. '

RG3 = ground plane dose factor for each identified nuclide i, m2 -mrem /y per Ci/s. Dose factors are calculated as described in Section 7.7.14.

The maximum organ dose rate is selected from among the dose rates calculated for all the organs and all age groups.

l i

l SQN ODCM Revision 35 Page 104 of 163 7.3 DOSE - NOBLE GASES Doses to be calculated are gamma and beta air doses due to exposure to an infinite cloud of noble gases. These doses will be calculated at the unrestricted area boundary location with the highest annual-average XI Q based on 1972-1975 mets rological data (Table 7.2). This location is chosen l

from the UNRESTRICTED AREA BOUNDARY locations listed in Table 7.1. Dispersion factors are calculated using the methodology described in Section 7.8.2.

No credit is taken for radioactive decay.

7.3.1 Gamma dose to air

, The gamma air dose, D, in mrad, is calculated for each release using the following equation:

/

D, = 1.9E-06 (% Q)I Q, DFj T (7.6)

I where:

1.9E-06= conversion factor, y/ min.

1Q/ = highest unrestricted area boundary annual-average relative concentration,5.12x10-8 33 s/m3 (from Table 7.1). ,

Q, = release rate for nuclide i, Ci/s.

DFj = dose conversion factor for extemal gamma for nuclide i (Table 7.3), mrad /y per Ci/m3 .

T = duration of release, min, j l

The gamma-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.3.3.

7.3.2 Beta dose to air The beta air dose, Dpin mrad, is calculated for each release using the following equation:

I Dp = 1.9E-06 (X Q) I Q iDF p; T (7.7) I i

where:

1.9E-06= conversion factor, y/ min.

1Q/ = highest unrestricted area boundary annual-average relative concentration,5.12x104 33 :

s/m3(from Table 7.1).

Q, = release rate for nuclide i, pCi/s.

DF p3 = dose conversion factor for extemal beta for nuclide i, mradly per pCi/m3 (from Table 7.3).

T = duration of release, min.

The beta-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.3.3.

SON ODCM Revision 35 ;

Page 105 of 163 7.3.3 Cumulative Dose - Noble Gas Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in ODCM Control 1.2.2.2.

For noble gases, cumulative doses are calculated for gamma and beta air doses. Doses due to each release are summed with the doses for all previous release in the quarter or year to obtain cumulative quarterly and annual doses.

7.3.4 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits ,

once per 31 days to determine compliance.

i i

l 4

SQN ODCM Revision 35 Page 108 of 163 7.4 DOSE DUE TO l-131.1-133. TRITIUM AND A8 I P_ADONUC artes IN PARTICULATE FORM WITH HALF 4.NES OF GREATER THAN 8 DAYS 7.4.1 Organ dose Calculation Organ doses due to 1-131,1-133, tritium and all radionuclides in particulate form with half-lives of greater than 8 days are calculated for each release for the critical receptor. The critice' Weptor is defined as the unrestricted area boundary in the sector with the highest annual average XI Q. The annual average XIQ and D/Q are calcuisted using the methodology in Sections 7.8.2 and 7.8.3 using the historical 1972-1975 meteorological data (Table 7.2). Pathways considered to exist at this location are inhalation, ground plane exposure, grass-cow-milk ingestion, grass-cow-beef ingestion and fresh leafy and stored vegetable ingestion. All age groups are considered (adult, teen, child and infant). Dose factors for these age groups and pathways are calculated as described in Section 7.7. For the ground exposure pathway, which has no age or organ specific dose factors, the total body dose will be added to the intomal organ doses for all age groups No credit is taken for radicadive decay.

The general equation for the calculation of organ dose is:

D, = 3.17E-06 T I I Rpi [ Wp Qi ] (7.8) iP where:

3.17E-08 = conversion factor, y/s T = duration of release, s.

Rp, = dose factor for pathway P for each identified nuclide i, m2-mrom/y per pCi/s for ground plane, grass-cow-milk, grass-cow-meat, and vegetation pathways, and mrom/y per Ci/m3for inhalation and tritium ingestion pathways. Equahons for calculating these dose factors are given in Sedion 7.7.

Wp = dispersion factor for the location and pathway,

/

= I Q for the inhalation and tritium ingestion pathways,

= 5.12E-06 s/m3.

.D/Q for the food and ground plane pathways,

= 1.29E-08 m-2 Q, = release rate for radionuciede I, pCi/s From the four age groups considered, the maximum is determined by comparing all oigan 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 7.4.2.

SQN ODCM Revision 35 Page 107 of 163 7.4.2 Cumulative Doses Quarter 1y and annual sums of all doses are calculated for each release as described below to compare to the limits listed in ODCM Control 1.2.2.3.

For maximum organ dose, cumulative quarterly and annual doses are maintained for each of the eight organs considered. The cumulative dose is obtained by summing the doses for each organ of the critical age group (as calculated in Section 7.4.1) as determined for each release with the organ doses for all previous releases in the quarter or year to obtain the cumulative quarterly and annual doses. Thus, the cumulative organ doses will be conservative values, consisting of doses betonging to various age groups depending on the mix of radionuclides. The highest of these cumulative organ doses is used for the comparison to the limits described in ODCM Control 1.2.2.3. ,

7.4.3 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance.

l SQN ODCM Revision 35 Page 108 of 163 7.5 DOSE PROJECTIONS in accordance with ODCM Surveillance Requirement 2.2.2.4, dose projections will be performed.

This will be done by maintaining running 31-day totals for the gamma dose, the beta dose and the maximum organ dose. Once per 31 days, these 31-day running totals will be compared to the limits given in ODCM Control 1.2.2.4 to determine compliance.

If the projected doses exceed any of these limits, the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous effluents to areas at or beyond the UNRESTRICTED AREA N j BOUNDARY.

7.5.1 GASEOUS RADWASTE TREATMENT SYSTEM DESCRIPTION The GASEOUS RADWASTE TREATMENT SYSTEM (GRTS) described below shall be maintained and operated to keep releases ALARA.

A flow diagram for the GRTS is given in Figure 7.3. The system consists of two waste-gas compressor packages, nine gas decay tanks, and the associated piping, valves, and instrumentation. Gaseous wastes are received from the following: degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown, displacing of cover gases caused by liquid accumulation in the tanks connected to the vent header, and boron recycle process operation.

d a

_________m . _ _ _ _ - -

r- - -

v -

SON ODCM Revision 35 Page 109 of 163 7.6 QUARTERLY DOSE CALCULATIONS A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter i will be performed and reported as required in ODCM Administrative Control 5.2. Methodology for this analysis is that which is described in this section usin0 the quarterly release values reported by the plant personnel, All real pathways and receptor locations identified by the most recent land l

use survey are considered, in addition, actual meteorolog: cal data representative of a ground i level release for each corresponding calendar quarter will be used. For iodine releases, it is i assumed that half the iodine released is in organic form. Organic lodine causes a dose only by inhalation. For cow-milk and beef ingestion doses, the fraction of the time the animals are on {

stored feed (identified in the survey) is used in the calculation.

The highest organ dose for a real receptor is determined by summing the dose contribution from all identified pathways for each receptor including ground contamination, inhalation, vegetable ingestion (for identified garden locations), cow and/or goat milk ingestion (if a cow or goat is identified for the location), beef ingestion (the beef ingestion dose for the location of highest beef j dose for all receptors will be considered the beef dose for all receptors). I 7.6.1 NOBLE GAS -GAMMA AIR DOSE Gamma air doses due to exposure to noble gases, D, in mrem, are calculated using the following equation:

D,= g DFj (7.g) where:

g = concentration of nuclide i at location m, Ci/m . Air 3 concentrations are calculated as described by Equation 7.14.

DFg = dose conversion factor for extemal gamma for nuclide i, mrad /y per Ci/m3 (Table 7.3).

7.6.2 NOBLE GAS - BETA AIR DOSE Beta air doses due to exposure to noble gases, Dp in mrem, are calculated using the following l

equation: 1 Dp = g DFp (7.10) where:

g = concentration of nuclide i at location m, Ci/m3. Air concentrations are calculated as !

described by Equation 7.14.

DFp = dose conversion factor for extemal beta for nuclide i, mrad /y per Ci/m3(Table 7.3).

l SQN ODCM Revision 35 Page 110 of 163 7.6.3 RADIOlODINE, PARTICULATE AND TRITIUM - MAXIMUM ORGAN DOSE Organ doses due to radiciodine, particulate and tritium releases, D in mrem, are calculated wo using the following equation:

D,, = 3.17E-08 ( (XI Q) IRPT OT II(Dja) ra +p (D /Q)Ra+ (1 /Q)RJ Q) (7.11)

P 1 P where:

3.17E-08 = conversion factor, y/s.

I XQ = Relative concentration forlocation under consideration, s/m3. Relative concentrations are calculated as described by Equation 7.15.

Rp7 = ingestion dose factor for pathway P for tritium, m 2 -mrem /y per Ci/s. Ingestion pathways available for consideration are the same as those listed above for Rpi.

Equations for calculating ingestion dose factors for tritium are given in Sections 7.7.7 through 7.7.12.

QT = adjusted release rate for tritium forlocation under consideration Ci/s. Calculated in the same manner as Q, above.

Rp, = ingestion dose factor for pathway P for each identified nuclide I (except tritium), m2 mrem /y per Ci/s. Ingestion pathways available for consideration include:

pasture grass-cow-milk ingestion stored feed-cow-milk ingestion pasture grass-goat-milk ingestion stored feed-goat-milk ingestion pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetable ingestion Equations for calculating these ingestion dose factors are given in Sections 7.7.1 through 7.7.6.

D/Q = Relative deposition for location under consideration, m-2. Relative deposition is calculated as described in Equation 7.16.

Ra = Dose factor for standing on contaminated ground, m2-mremly per pCi/s. The equation for calculating the ground plane dose factor is given in Section 7.7.14.

Ru = Inhalation dose factor, mrem /y per Ci/m3. The equation for calculating the inhalation dose factor is given in Section 7.7.13.

O, = adjusted release rate for nuclide i for location under consideration, Cl/s. The initial release rate is adjusted to account for decay between the release point and ths 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 during the period.

9

, Qo I f jexp(- x/u) (7.12)

( M where Qo = initial average release rate for nuclide i over the period, Ci/s.

fj = joint relative frequency of occurrence of winds in windspeed class j blowing toward this exposure point, expressed as a fraction.

= radiological decay constant for nuclide i, sd .

x = dowr wind distance, meters.

uj = midp sint value of wind speed class intervalJ, m/s.

SQN ODCM Revision 35 Page 111 of 163 7.6.4 POPULATION DOSES For determining population doses to the 50-mile population around the plant, each compass sector is broken down into elements. These elements are defined in Table 7.4. For each of these sector elements, an average dose is calculated, and then multiplied by the population in that sector element. Dispersion factors are calculated for the midpoint of each sector element (see Table 7.4).

For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally.

The general equation used for calculating the population dose in a given sector element is: l Doseg = I RATIOp

POPN

AGE

0.001

DOSEp (7.13)

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.) .

l

= 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 anU adult, respectively. (It is assumed that the ratio of average to maximum infant milk ingestion rates is the same as that for child.)

= 1.0,0.90,0.91,0.86 for beef ingestion, for infant, child, teen and adult, respectively.

= 1.0,0.38,0.38,0.37 for vegetable ingestion, for infant, child, teen and adult, respectively. (It is assumed that the average individual eats no fresh leafy vegetables, only stored vegetables.)

POPN = the population of the sector element, persons (Table 7.5).

AGE = fraction of the population belonging to each age group.

= 0.015,0.168,0.153,0.665 for infant, child, teen and adult, respectively (fractions taken from NUREG/CR 1004, Table 3.39).

0.001 = conversion from mrem to rem.

DOSEp = the dose for pathway P to the maximum individual at the location under consideration, mrem. For ingestion pathways, this dose is multiplied by an average decay correction to account for decay as the food is moved through the food distribution cycle. This average decay correction, ADC, is defined as follows:

For milk and vegetables, ADC = exp(-\t) where

\ = decay constant for nuclide i, s.

t = distribution time for food product under consideration (values from Regulatory Guide 1.109, Table D-1).

= 1.21E+06 s (14 d) for vegetables.

= 3.46E+05 s (4 d) for milk.

exp( \t) \te For meat, ADC =

1 - exp(-\ty where

= decay constant for nuclide i, s.

l l

SON ODCM Revision 35 Page 112 of 163 l l

I t = additional distribution time for meat, over and above the time for slaughter to consumption described in Section 7.7.3,7 d.

ta = time to consume a whole beef, as described in Section 7.7.3.

For beef ingestion, the additional factors in the calculation of ADC negate the integration of the dose term over the period during which a whole beef is consumed, for the calculation of population dose. In other words, this assumes that the maximum individual freezes and eats a whole beef, while the average individual buys smaller portions at a time.

Population doses are summed over all sector elements to obtain a total population dose for the 50-mile population.

1 7.6.5 REPORTING OF DOSES The calculated quarterly doses and calculated population doses described in this section are reported in the Annual Effluent Release Report as required by ODCM Administrative Control 5.2.

7.6.6 DOSE TO A MEMBER OF THE PUBLIC INSIDE THE UNRESTRICTED AREA 133 '

BOUNDARY The Basis for ODCM Control 1.2.2.1 states that for MEMBERS OF THE PUBLIC who may at times be within the UNRESTRICTED AREA BOUNDARY, the occupancy factor of that MEMBER l33 l

OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric l dispersion factor above that for the UNRESTRICTED AREA BOUNDARY. This basis also states l33 i that examples of calculations for such MEMBERS OF THE PUBLIC will be given in the ODCM. l The determination presented here assumes that the most exposed MEMBER OF THE PUBLIC will

32. l be an adult TVA employ (e who works just outside the restricted area fence for the entire workyear (2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months ). Results from onsite Thermoluminescent Dosimeter (TLD) measurements from the years 19901992 indicate that the highest onsite extemal dose was 72.6 mrem. Using this value, subtracting an annual background value of 55 mrem / year, and multiplying by the ratio of the occupancy times, the highest extemal dose to a MEMBER OF THE PUBLIC inside the UNRESTRICTED AREA BOUNDARY is 4 mrem. Historical records show that the total dose 3 contribution from effluent releases is normally less than 2 mrem. The combination of the measured direct dose (part of which is from effluent releases) and the calculated effluent dose will be below both the 10 CFR Part 20 limit of 100 mrem / year and the 40 CFR Part 190 limit of 25 mrem / year. In addition to this analysis, the dose to this hypothetical MEMBER OF THE PUBLIC will be determined on an annual basis (using the methodology above) to ensure that the actual dose to any individual is less than 100 mrem / year. The results of this review will be included in i the Annual Radiological Effluent Report pursuant to ODCM Administrative Control .S.2. I I

l SON ODCM Revision 35 :

Page 113 of 163 l 7.7 GASEOUS RELEASES - Dose Factors 7.7.1 PASTURE GRASS. COW / GOAT-MILK INGESTION DOSE FACTORS (m2-mrem /y per Ci/s)

I r(1 exp(-AE IM) Bw(1-exp(-%ty)

RCP,= 10eDFLw U ,F n Qgexp(-%t%)f,{ , ) l Yh p P i where:

10e = conversion factor, pCi/ Cl. I DFL, = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCi (Table 6.4).

U = milk ingestion rate for age group a, IJy.

Fw, = transfer factor for nuclide i from animal's feed to milk, d/L(Table 6.2).

Q, = animal's consumption rate, kg/d. ;

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

tg '

= transport time from milking to receptor, s.

f, = fraction of time animal spends on pasture, dimensionless.

r = fraction of activity retained on pasture grass, dimensionless. !

LE = the effective decay constant, due to radioactive decay and weathering, s-1, equal to + !

br

( = weathering decay constant for leaf and plant surfaces, s-1 I t, = time pasture is exposed to deposition, s. .

Y, = agricultural productivity by unit area of pasture grass, kg/m2, By = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per i pCi/kg (dry soil).

t, = time period over which accumulation on the ground is evaluated, s. i P = effective surface density of soil, kg/m2, NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

l

7 SON ODCM Revision 35 Page 114 of 163 7.7.2 STORED FEED COW / GOAT-MILK INGESTION DOSE FACTORS (m 2-mrem /y per pCL/s)

(1-exp(-htg)) r(1-exp(-AE t,,,)) B,(1-exp(-hty)

RCSi = 10e DFQU,F m Q, f.exp(-hts,y ( + }

tw Y,, AE Py where:

10s = conversion factor, pCi/pCl.

DFQ = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCi (Table 6.4).

U = milk ingestion rate for age group a, tJy.

Fw, = transfer factor for nuclica i from animal's feed to milk, d/L (Table 6.2).

Q, = animal's consumption rate, kg/d.

fs = fraction of time animal spends on stored feed, dimensionless.

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

th = transport time from milking to receptor, s.

tg = time between harvest of stored feed and consumption by animal, s.

r a fraction of activity retained on pasture grass, dimensionless.

AE = the effective decay constant, due to radioactive decay and weathering, s-1, equal to h+Aw-A, = weathering dscay constant for leaf and plant surfaces, s-1 ,

t, = time stored feed is exposed to deposition, s.

Y, = agricultural productivity by unit area of stored feed, kg/m2, Bu = transfer factor for nuclide i from soll to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

t. = time period over which accumulation on the ground is evaluated, s.

P = effective surface density of soil, kg/m2 ,

NOTE: Factors defined above which do not reference a table for their numerical values are liven in Table 6.3.

SQN ODCM Revision 35 Page 115 of 163 7.7.3 PASTURE GRASS-BEEF INGESTION DOSE FACTORS (m2-mrem /y per Cl/s) '

(1-exp(- tc y) r(1-exp(-1 E Q) Bu(1-exp(-\t b))

RMP = 10s DFLw U FriOr exp(-htsp)ff + }

hteb YA p E Py where:

10e = conversion factor, pCi/pCl.

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

U, = meat ingestion rate for age group a, kgly.

Fra = transfer factor for nuclide i from cow's feed to meat, d/kg (Table 6.2).

Op = cow's consumption rate, kg/d.

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

tcb = time for receptor to consume a whole beef, s. J ts = transport time from slaughter to consumer, s. 1 f, = fraction of time cow spends on pasture, dimensionless.

r = fraction of activity retained on pasture grass, dimensionless.

IE = the effective decay constant, due to radioactive decay and weathering, s-1, equal to +(

( = weathering decay constant for leaf and plant surfaces, s-1 ,

t, = time pasture is exposed to deposition, s.

Y, = agricultural productivity by unit area of pasture grass, kg/m2, By a transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCl/kg (dry soil).

to = time over which accumulation on the ground is evaluated, s.

P = effective surface density of soll, kg/m2.

NOTE: Factors defined above which do not reference a table for their numerical values are liven in Table 6.3.

l I

I

f i

SQN ODCM Revision 35 Page 116 of 163 7.7.4 STORED FEED 8EEF INGESTION DOSE FACTORS (m2-mrom/y per pCi/s)

(1-exp(;ten)) (1-exp(-%t e g)) r(1-exp(-yt.g))

RMS3 = 10e DFQ U Fri Op exp(-;ts ) fs I +

\ te Ntg o Yg Q j BJ1-exp(- t e)) !

)

P I j

where:

10e = conversion factor, pCi/pCl.

DFQ = ingestion dose conversion factor for nuclide I, age group a, organ o, mrem /pCi (Table 6.4).

U. = meat ingestion rate for age group a, kO /Y-Fri = transfer factor for nuclide i from cow's feed to meat, d!k0 (Table 6.2).

Op = cow's consumption rate, k0ld.

y = decay constant for nuclide I, s-1 (Table 6.2).

toe = time for receptor to consume a whole beef, s.

t, = transport time from slau0hter to consumer, s.

f, = fraction of time cow spends on stored feed, dimensionless.

tg o = time between harvest of stored feed and consumption by cow, s.

r = fradion of activity retained on pasture grass, dimensionless t,,, = time stored feed is exposed to deposition, s.

Y, = agricultural productivity by unit area of stored feed, kg/m2, Q = the effective decay constant, due to radioactive decay and weathering, s-1, equal to +( l

( = weathering decay constant for leaf and plant surfaces, s-1 By = transfer factor for nuclide i fmm soil to vegetation, pCi/k0 (wet weight of vegetation) per pCl/k0 (dry soil),

to = time over which accumulation on the gmund is evaluated, s.

P = effective surface density of soil, kO/m2, NOTE: Factors defined above which do not reference a table for their numerical values are liven in Table 6.3.

SON ODCM Revision 35 Page 117 of 163 7.7.5 FRESH LEAFY VEGETABLE INGESTION DOSE FACTORS (m2-mrem /y per Ci/s) r(1-e(-1Eel )) Bw(1-e(-\ty)

RVFi = 108 DFL% e(- tg) UFL,ft i +

_} j Yp AE P where:

108 conversion factor, pCl/ Cl.

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

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

tg = average time between harvest of vegetables and their consumption and/or storage, s.

UFL, = consumption rate of fresh leafy vegetables by the receptor in age group a, kg/y.

ft = fraction of fresh leafy vegetables grown locally, dimensionless.

r = fraction of deposited activity retained on vegetables, dimensionless.

LE = the effective decay constant, due to radioactive decay and weathering, s-1,

=y+(

( = decay constant for removal of activity on leaf and plant surfaces by weathering, s-1 t, = exposure time in garden for fresh leafy and/or stored vegetables, s.

Yp = agricultural yield for fresh leafy vegetables, kg/m2, Bu = transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per pCl/kg (dry soil),

tb = time period over which accumulation on the ground is evaluated, s.

P = effective surface density of soil, kg/m2, NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

l 1

i 1

I l l

l I-l:

SQN ODCM Revision 35 l Page 118 of 163

\ .

7.7.6 8TORED VEGETABLE INGESTION DOSE FACTORS m2-mrem /y per Ci/s)

(1-e(Atsv)) f(1**(-lEt,)) ' Bg(1-e(-zty)

RVS, = 10e DF6 exp( u;t )saU fg i +

}

hIsv Y,AE Py where: 1 10s = conversion factor, pCi/ Cl.

DFI, = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCi i (Table 6.4).

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

tg = average time between harvest of vegetables and their consumption arid /or storage, s.

U, s = consumption rate of stored vegetables by the receptor in age group a, kg/y.

f = fraction of stored vegetables grown locally, dimensionless.

t,,, = time between storage of vegetables and their consumption, s.

r = fraction of deposited activity retained on vegetables, dimensionless.

l AE = the effective decay constant, due to radioactive decay and weathering, s-1 I =4+4

( = decay constant for removal of activity on leaf and plant surfaces by weathering, s 1 t, = exposure time in garden for fresh leafy and/or stored vegetables, s.

Y,, = agricultural yield for stored vegetables kg/m2, ,

j By = transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per i pCi/kg (dry soil). j l to = time period over which accumulation on the ground is evaluated, s. 1 P = effective surface density of soil, kg/m2, !

NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. l l

l l l 1

k I

I' - - , , . . . . . _ _

SQN ODCM Revision 35 Page 119 of 163 7.7.7 TRITIUM-PASTURE GRASS-COW / GOAT-MILK DOSE FACTOR (mrem /y per Ci/m3)

RCTp = 103 10e DFL7 FmT Op U ,[0.75(0.5/H)] f exp(-Ap IT Fm) where:

103 = conversion factor, g/kg.

10s = conversion factor, pCi/ Cl.

DFLTm = ingestion dose conversion factor for trhium for age group a, organ o, mrem /pCl (Table 6.4).

F mT = transfer factor for tritium from animal's feed to milk, d/L (Table 6.2).

Op = animal's consumptiori rate. kg/d.

U = milk ingestion rate Mr age group a, L/y.

0.YS = Gie fraction of total feed that is water.

0.5 = the ratio of the spe .ific activity of the feed grass water to the atmospheric water.

H = absolute humidity ci tae atmosphere, g/m3, f, = fraction of time anima spends on pasture, dimensionless.

AT = decay constant for tritiuin, s-1 (Table 6.2).

tp, = transport time from milking to receptor, s.

7.7.8 TRITIUM-STORED FEED-COW / GOAT-MILK DOSE FACTOR (mrem /y per Cl/m3)

RCTs = 103 10e DFL7 . Fp7 Qp U ,[0.75(0.5/H)] is exp( ATIs)

AT t,,, At Te where:

103 = conversion factor, g/kg.

10s = conversion factor, pCi/pCl.

DFLTm = ingestion dose conversion factor for H-3 for age group.a organ o, mrem /pCi (Table 6.4).

F FT = transfer factor for H-3 from cow's feed to meat, d/kg (7able 6.2).

Op = cow's consumption rate, kg/d.

U,, = meat ingestion rate for age group a kg/y.

0.75 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3 , '

is = fraction of time cow spends on stored feed, dimensionless.

AT = decay constant for tritium, s-1 (Table 6.2).

is = transport time from slaughter to consumer, s.

1,,, = time to consume stored feed, s.

tg = time for receptor to consume a whole beef, s.

NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

SQN ODCM Revision 35 l Page 120 of 163 7.7.9 TRITlUM-PASTURE GRASS-BEEF DOSE FACTOR (mrem /y per Ci/m3) 3 8 RMTP = 1010 DFLTm F OF FT am [0.75(0.5/H)] f, exp(-AT ts)

AlT ep At T eb 1 03 = conversion factor, g/kg.

108 = conversion factor, pCi/ Cl.

DFLTm = ingestion dose conversion factor for H-3 for age group a, organ o, mremipCi (Table 6.4).

F FT = transfer factor for H-3 from cow's feed to meat, d/kg (Table 6.2).

Op = cow's consumption rate, kg/d.

Uam = meat ingestion rate for age group a, kgly.

0.75 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3 f = fraction of time cow spends on pasture, dirnensionless.

AT = decay constant for tritium, sd (Tablo 6.2).

is = transport time from slaughter to consumer, s.

t,p = time pasture is exposed to deposition, s.

ten = time for receptor to consume a whole beef, s.

7.7.10 TRITIUM-STORED FEED-BEEF DOSE FACTOR (mrem /y per Ci/m3)

RMTS = 10 3 10 8 DFL F O U,m[0.75(0.5/H)) f exp( A t )

Tw FT F s T AIT csf At T eb where:

103 = conversion factor, g/kg.

106 = conversion factor, pCi/ Cl.

DFLTm = ingestion dose conversion factor for H-3 for age group a, organ o, mrem /pCi (Table 6.4).

F FT = transfer factor for H-3 from cow's feed to meat, d/kg (Table 6.2).

Op = cow's consumption rate, kg/d.

U,, = meat ingestion rate for age group a, kg/y.

0.75 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

11 = absolute humidity of the atmosphere, g/m3 fs = fraction of time cow spends on stored feed, dimensionless.

AT = decay constant for tritium, s*1 (Table 6.2).

t, = transport time from slaughter to consumer, s.

Icsf = time to consume stored feed, s.

te = time for receptor to consume a whole beef, s.

NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

i

t SQN ODCM Revision 35 Page 121 of 163 7.7.11 TRITIUM-FRESH LEAFY VEGETABLES DOSE FACTOR (mrem /y per Ci/m3) -

RVTF = 103 10 8 DFLTm [d.75(0.5/H)] Uruf t exp( Art )

g where:

103 = conversion factor, g/kg.

106 = conversion factor, pCi/ Cl.

OFLTw = ingestion dose conversion factor for tritium for age group a, organ o, mrem /pCi (Table 6.4). ,

0.75 = the fraction of total vegetation that is Mier. 1 0.5 = the ratio of the specific activity of the vegetables water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3, Uru = consumption rate of fresh leafy vegetables by the receptor in age group a, kg/y. ,

ft = fraction of fresh leafy vegetables grown locally, dimensionless. !

AT = decay constant for tritium, s-1 (Table 6.2). I tg = time between harvest of vegetables and their consumption and/or storage, s. l l

l NOTE: Factors defined above which do not reference a table for their numerical values are given l in Table 6.3. 1 l

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SQN ODCM ,

Revision 35 Page 122 of 163 7.7.12 TRITIUM-STORED VEGETABLES DOSE FACTOR (mrem / year per Cl/m3)

RVTs = 103 10 6 DFL ,[0.75(0.5/H)] Us,f 7 s exp(-AT% t) .

Ai T sv where:

103 = conversion factor, g/kg, 108 = conversion factor, pCi/ Cl.

DFLTm = ingestion dose conversion factor for tritium for age group a, organ o, mrem /pCi (Table 6.4).

0.75 = the fraction of total vegetation that is water.

0.5 = the ratio of the specific activity of the vegetation water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

U se = consumption rate of stored vegetables by the receptor in age group a, kgly.

fg = fraction of stored vegetables grown locally, dimensionless.

l AT = decay constant for tritium, s-1 (Table 6.2).

1,3 = time between harvest of stored vegetables and their consumption and/or storage, s.

tg = time between harvest of vegetables and their storage, s.

7.7.13 INHALATION DOSE FACTORS (mrem /y per Ci/m3)

Rli = DFA BR,10 6 where:

DFA, = inhalation dose conversion factor for nuclide i, age group a and organ o, mrem /pCi (Table 7.7).

BR, = breatning rate for age group a, m 3/y (Table 6.3).

109 = conversion factor, pCl/pCi.

7.7.14 GROUND PLANE DOSE F (ORS (m2-mremly per Cl/s) i RGi = DFG 1/ 10e 8760 [1 - exp(-\ty) where: l DFGe = dose conversion factor for standing on contaminated ground for nuclide i and organ o (total body and skin), mrem /hr per pCL/m2 (Table 6.6). l

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

10s = conversion factor, pCl/pCl.

8760 = conversion factor, h/y.

tb = time period over which the ground accumulation is evaluated, s (Table 6.3).

i SQN ODCM Revision 35 Page 123 of 163 7.8 DISPERSION METHODOLOGY Dispersion factors are calculated for radioactive effluent releases using houriy average meteorological data consisting of wind speed and direction measurements at 10m and temperature measurements at 9m and 46m.

A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The j dispersion model considers plume depletion (using information from Figure 7.4), and building ;

wake effects. Terrain 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 Gi ven in Table 7.2.

l The wind speed classes that are used are as follows:

Number Ranoe (m/s) Midooint fm/s) !

1 <0.3 0.13 .

2 0.3-0.6 0.45 l 3 0.7-1.5 1.10 4 1.6-2.4 1.99 5 2.5-3.3 2.88 6 3.45.5 4.45 7 5.6-8.2 6.91 8 8.3-10.9 9.59 9 >10.9 10.95 The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A=1, B=2, .... G=7.

7.8.1 AIR CONCENTRATION Air concentrations of nuclides at downwind locrtions are calculated using the following equation:

1 97 fpQ; p ya = I E (2/n[1/2 exp(-Q/u) (7.14)

J 1 k=1 Ia ju(2xx/n)

I where fp = 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 i, pCi/s.

p = fraction of radionuclide remaining in plume (Figure 7.4).

In = vertical dispersion coefficient for stability class k which includes a building wake adjustment,

= (o 2 + cA/n)14, or = (3) G c3, whichever is smaller, where o, is the vertical dispersion coefficient for stability class k (m) (Figure 7.5),

c is a building shape factor (c=0.5),

?

SON ODCM Revision 35 Page 124 of 163 A is the minimum building cross-sectional area (1800 m2).

uj = midpoint value of wind speed class intervalJ, m/s.

x = downwind distance, m.

n = number of sectors,16.

A, = radioactive decay coefficient of radionuclide i, s-1 2xx/n = sector width at point of interest, m.

7.8.2 RELATIVE CONCENTRATION Relative concentrations of nuclides at downwind locations are calculated using the following l equation:

97 fp x/Q = I I (2/x)1/2 (7.15)

P1 k=1 E3u,(2xx/n) where fp = joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction.

In = vertical dispersion coefficient for stability class k which includes a building wake adjustment, i

= (a 2 + cA/x)10, I or = (3) U ca, whicheveris smaller, where og is the vertical dispersion coefficient for stability class k (m) (Figure 7.5),

c is a building shape factor (c=0.5),

A is the minimum building cross-sectional area (1800 m2) ,

u = midpoint value of wind speed class intervalJ, m/s.

3 x = downwind distance, m.

n = number of sectors,16, 2xx/n = sector width at point of interest, m.

i 7.8.3 RELATIVE DEPOSITION Relative deposition of nuclides at downwind locations is calculated using the following equation:

9 7 fp DR D/Q = E E (7.16) p1 k=1 (2xx/n) where fp = joint relative frequency of occurrence of winds in windspeed class j and stability class k, blowing toward this exposure point, expressed as a fraction.

DR = relative deposition rate, m-1 (from Figure 7.6).

x = downwind distance, m.

n = number of sectors,16.

2xx/n = sector width at pcint of interest, m.

SON ODCM Revision 35 ,

Page 125 of 163 j Table 7.1 SON - OFFSITE RECEPTOR LOCATION DATA ,

DISTANCE y/Q D/Q POINT from plant (m) (s/m3) (1/m2)-

Unrestricted Area Boundary N 960 5.12E 06 1.29E-08 Unrestricted Area Boundary NNE 2260 1.93E-06 5.28E-09 ,

Unrestricted Area Boundary NE 1910 2.32E-06 6.33E-09 Unrestricted Area Boundary ENE 1680 1.12E-06 2.64E-09 Unrestricted Area Boundary E 1570 7.10E-07 1.46E-09 Unrestricted Area Boundary ESE 1460 7.91 E-07 1.58E-09 Unrestricted Area Boundary SE 1460 9.14E-07 2.41E-09 Unrestricted Area Boundary SSE 1550 1.34E-06 3.23E-09 33 Unrestricted Area Boundary S 1570 2.37E-06 4.18E-09 Unrestricted Area Boundary SSW 1840 4.51E-06 9.26E-09 ,

Unrestricted Area Boundary SW 2470 1.38E-06 2.63E-09 '

Unrestricted Area Boundary WSW 910 2.93E-06 3.86E-09 Unrestricted Area Boundary W 670 3.63E-06 3.74E-09 Unrestricted Area Boundary WNW 660 2.49E-06 2.44E 09 ,

Unrestricted Area Boundary NW 660 2.85E-06 3.67E-09 Unrestricted Area Boundary NNW 730 <

3.95E-06 6.59E-09 Liquid Discharge S 870 N/A N/A NOTE: For quarterly airbome dose calculations, doses will also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary.

i-SQN ODCM Revision 35 Page 126 of 163 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES *

(Page 1 of 7)

Sequoyah Nuclear Plant Meteorological Facility

Jan.1,72 Dec. 31,75 Stability Class A Delta TS 1.9 deg. C/100m Wind Speed (mph) 0.6- 1.5- 3.5 5.5- 7.5- 12.5- 18.5-Calm 1.4 . 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.01 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 7.0 0.0 0.0 0.0 0.03 SSE 0.0 0.0 0.01 0.03 0.02 0.02 0.01 0.0 0.0 0.09 S 0.0 0.0 0.01 0.04 0.06 0.05 0.01 0.0 0.0 0.17 SSW 0.0 0.0 0.01 0.09 0.18 0.16 0.01 0.0 0.0 0.45 SW 0.0 0.0 0.04 0.12 0.10 0.09 0.02 0.0 0.0 0.37 WSW 0.0 0.0 0.02 0.03 0.03 0.02 0.02 0.0 0.0 0.12 W 0.0 0.0 0.01 0.0 0.01 0.02 0.0 0.0 0.0 0.04 WNW 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.02 NW 0.0 0.0 0.01 0.01 0.01 0.05 0.01 0.0 0.0 0.09 NNW 0.0 0.0 0.01 0.0 0.02 0.08 0.01 0.0 0.0 0.12 Sub-total 0.01 0.01 0.31 0.80 0.83 0.83 0.12 0.0 0.0 2.90 958 stability class A occurrences out of total 32723 valid temperature difference readings.

934 valid wind direction / wind speed readings out of total 958 stability class A occurrences.

All columns at d calm total 100 percent of net valid readings

Meteorolog; cal Facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature instruments 33 and 150 feet above ground.

Wind instruments 33 feet above ground.

. . - . .~. . - - . -- -- -- . - . - .

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Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED l FOR DIFFERENT STABILITY CLASSES

i (Page 2 of 7) ,

J Sequoyah Nuclear Plant Meteorological Facility

l Jan.1, 72 - Dec. 31,75 l

l Stability Class B !

-1.9 < delta T5-1.7 deg. C/100m !

Wind Speed (mph) 0.6- 1.5 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.01 0.01 0.02 0.03 0.0 0.0 0.0 0.07 :

NNE 0.0 0.0 0.05 0.23 0.20 0.18 0.01 0.0 0.0 0.67 ;

NE 0.01 0.0 0.08 0.29 0.09 0.06 0.0 0.0 0.0 0.52 i ENE 0.0 0.0 0.03 0.03 0.01 0.0 0.0 0.0 0.0 0.07 E 0.0 0.0 0.02 0.01 0.0 0.0 0.0 0.0 0.0 0.03 ESE 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.01 l 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 l WSW 0.0 0.0 0.01 0.01 0.03 0.02 0.01 0.01 0.0 0.09 i W 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 WNW 0.0 0.0 0.0 0.01 0.01 0.03 0.0 0.0 0.0 0.05 NW 0.0 0.0 0.0 0.0 0.01 0.05 0.0 0.0 0.0 0.06 ,

NNW 0.0 0.0 0.01 0.02 0.02 0.06 0.01 0.0 0.0 0.12 i SUBTOTAL 0.01 0.0 0.33 0.90 0.81 0.81 0.09 0.01 0.0 2.95 i l

I 969 stability class B occurrences out of total 32723 valid temperature difference readings. 8 953 valid wind direction / wind speed readings out of total 969 stability class B occurrences.

All columns and calm total 100 percent of net valid readings.

Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant. ,

Temperature instruments 33 and 150 feet above ground.

Wind instruments 33 feet above ground.

f i

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Revision 35 }

Page 128 of 163

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Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED !

FOR DIFFERENT STABILITY CLASSES

l (Page 3 of 7) !

Sequoyah Nuclear Plant Meteorological Facility * !

Jan.1, 72 - Dec. 31, 75 ;

Stability Class C I

-1.7 < delta TS-1.5 deg. C/100m l Wind Speed (mph) i 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.01 0.02 0.02 0.02 0.0 0.0 0.0 0.07 1 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 j ENE 0.0 0.0 0.03 0.02 0.0 0.0 0.0 0.0 0.0 0.05 E 0.0 0.0 {

0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 i ESE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 SE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 SSE 0.0 0.0 0.01 0.02 0.0 0.02 0.0 0.0 0.0 0.05 S 0.0 0.0 0.03 0.04 0.06 0.05 0.0 0.0 0.0 0.18 SSW 0.0 0.0 0.01 0.11 0.14 0.13 0.02 0.0 0.0 0.41 SW 0.0 0.0 0.03 0.08 0.12 0.07 0.01 0.0 0.0 0.31 WSW 0.0 0.0 0.01 0.02 0.03 0.02 0.0 0.01 0.0 0.08 W 0.0 0.0 0.0 0.01 0.0 0.01 0.01 0.0 0.0 0.03 WNW 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 NW 0.0 0.0 0.0 0.0 0.02 0.03 0.01 0.0 0.0 0.06 NNW 0.0 0.0 0.0 0.02 0.02 0.05 0.0 0.0 0.0 0.09 SUBTOTAL 0.0 0.0 0.26 0.64 0.58 0.55 0.05 0.0 0.0 2.08 684 stability class C occurrences out of total 32723 valid temperature difference readings.

672 valid wind direction / wind speed readings out of total 684 stability class C occurrences.

All columns and calm total 100 percent of net valid reacirgs.

Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature instruments 33 and 150 feet above ground.

Wind instruments 33 feet above ground.

T i

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t Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

l (Page 4 of 7) !

f Sequoyah Nuclear Plant Meteorological Facility

i Jan.1, 72 - Dec. 31, 75 Stability Class D

-1.5 < delta T<.0.5 deg. C/100m Wind Speed (mph) {

0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5- l Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total '

N 0.003 0.01 0.24 0.22 0.16 0.17 0.0 0.0 0.0 0.80 l NNE 0.017 0.06 0.73 1.03 0.84 0.78 0.07 0.0 0.0 3.51 l NE 0.006 0.02 0.76 0.88 0.42 0.42 0.05 0.0 0.0 2.55 ENE 0.003 0.01 0.21 0.11 0.03 0.0 0.0 0.0 - 0.0 0.36 E 0.003 0.01 0.12 0.03 0.02 0.01 0.0 0.0 0.0 0.19 ESE 0.003 0.01 0.06 0.02 0.0 0.0 0.0 0.0 0.0 0.09 SE 0.0 0.0 0.12 0.08 0.0 0.0 0.0 0.0 0.0 0.20 SSE 0.0 0.0 0.15 0.15 0.05 0.06 0.01 0.01 0.0 0.43 S 0.003 0.01 0.31 0.53 0.38 0.25 0.02 0.0 0.0 1.50 SSW 0.003 0.01 0.44 1.25 0.95 0.70 0.07 0.0 0.0 3.42 SW 0.003 0.^ 1 0.47 1.17 1.03 0.52 0.03 0.01 0.0 3.24 WSW 0.0 0.0 0.22 0.34 0.18 0.21 0.07 0.01 0.0 1.03 W 0.003 0.01 0.06 0.08 0.10 0.19 0.02 0.01 0.0 0.47 WNW 0.003 0.01 0.06 0.05 0.11 0.18 0.01 0.0 0.0 0.42 NW 0.0 0.0 0.08 0.08 0.22 0.31 0.03 0.0 0.0 0.72 NNW 0.003 0.01 0.15 0.14 0.25 0.36 0.02 0.0 0.0 0.93 SUETOTAL 0.05 0.18 4.18 6.16 4.74 4.16 0.40 0.04 0.0 19.86 6567 stability class D occurrences out of total 32723 valid temperature difference readings.

6345 valid wind direction / wind speed readings out of to'tal 6567 stability class D occurrences.

All columns and calm total 100 percent of net valid readirgs.

Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature instruments 33 and 150 feet above ground. l Wind instruments 33 feet above ground. i i

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(Page 5 of 7)

Sequoyah Nuclear Plant Meteorological Faci!ity*

Jan.1, 72 - Dec. 31, 75 Stability Class E i

-0.5 < delta T< 1.5 deg. C/100m Wind Speed (mph) l 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5- '

Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.017 0.23 1.26 0.83 0.39 0.27 0.0 0.0 0.0 2.98 NNE 0.023 0.31 2.83 2.46 1.07 0.92 0.03 0.0 0.0 7.62 NE 0.011 0.15 1.03 0.71 0.31 0.18 0.01 0.0 0.0 2.39 ENE 0.009 0.12 0.48 0.16 0.04 0.0 0.0 0.0 0.0 0.80 E 0.010 0.14 0.24 0.05 0.01 0.01 0.0 0.0 0.0 0.45 ESE 0.007 0.09 0.11 0.01 0.01 0.01 0.01 0.0 0.0 0.24 SE 0.007 0.10 0.37 0.06 0.01 0.01 0.0 0.0 0.0 0.55 i SSE 0.008 0.11 0.58 0.24 0.13 0.23 0.04 0.02 0.0 1.35 S 0.013 0.17 1.33 1.49 0.91 1.05 0.08 0.0 0.0 5.03 SSW 0.007 0.10 1.67 2.32 1.67 1.45 0.11 0.0 0.0 7.32 SW 0.013 0.17 1.59 2.07 1.30 0.99 0.10 0.0 0.0 6.22 WSW 0.010 0.13 0.87 0.55 0.35 0.40 0.06 0.0 0.0 2.36 W 0.007 0.10 0.42 0.28 0.21 0.22 0.03 0.0 0.0 1.26 WNW 0.010 0.14 0.37 0.22 0.19 0.27 0.02 0.0 0.0 1.21 NW 0.007 0.10 0.50 0.37 0.43 0.38 0.02 0.0 0.0 1.80 NNW 0.011 0.15 0.80 0.68 0.57 0.40 0.01 0.0 0.0 2.61 SUBTOTAL 0.17 2.31 14.45 12.50 7.60 6.79 0.52 0.02 0.0 44.19 14624 stability class E occurrences out of total 32723 valid temperature difference readings.

14146 valid wind direction / wind speed readings out of total 14624 stability class E occurrences. l l

All columns and calm total 100 percent of net valid readings. )

Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature instruments 33 and 150 feet above ground.

Wind instruments 33 feet above ground.

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(Page 6 of 7)

Sequoyah Nuclear Plant Meteorological Facility

l Jan.1, 72 - Dec. 31, 75 l 1

Stability Class F i 1.5 < delta T< 4.0 deg. C/100m j Wind Speed (mph) ;

0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5- !

Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.011 0.21 1.37 0.44 0.04 0.0 0.0 0.0 0.0 2.06 NNE 0.018 0.35 3.61 0.84 0.05 0.0 0.0 0.0 0.0 4.85 NE 0.011 0.21 1.15 0.28 0.01 0.0 0.0 0.0 0.0 1.65 ,

ENE 0.008 0.16 0.39 0.03 0.0 0.0 0.0 0.0 0.0 0.58 E 0.010 0.20 0.22 0.0 0.0 0.0 0.0 0.0 0.0 0.42 ESE 0.007 0.13 0.18 0.02 0.0 0.0 0.0 0.0 0.0 0.33 SE 0.007 0.14 0.23 0.02 0.0 0.0 0.0 0.0 0.0 0.39 i SSE 0.008 0.15 0.37 0.07 0.03 0.01 0.0 0.0 0.0 0.63 S 0.009 0.17 0.77 0.30 0.10 0.06 0.0 0.0 0.0 1.40 SSW 0.006 0.12 1.13 0.71 0.26 0.11 0.0 0.0 0.0 2.33 )

SW 0.005 0.10 0.99 0.86 0.27 0.13 0.0 0.0 0.0 2.35 ,

WSW 0.005 0.09 0.46 0.19 0.04 0.01 0.0 0.0 0.0 0.79 l W 0.004 0.07 0.20 0.07 0.01 0.0 0.0 0.0 0.0 0.35 WNW 0.005 0.10 0.24 0.07 0.01 0.0 0.0 0.0 0.0 0.42 NW 0.003 0.05 0.29 0.15 0.05 0.01 0.0 0.0 0.0 0.55 NNW 0.005 0.09 0.52 0.34 0.05 0.01 0.0 0.0 0.0 1.01 SUBTOTAL 0.12 2.34 12.12 4.39 0.92 0.34 0.0 0.0 0.0 20.11 6542 stability class F occurrences out of total 32723 valid temperature difference Tedings.

6461 valid wind direction / wind speed readings out of total 0542 stability class F occurrences.

All columns and calm total 100 percent of net valid readings.

" Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature instruments 33 and 150 feet above ground.

Wind instruments 33 feet above ground.

I l

i 4

~

l SON ODCM Revision 35 Page 132 of 163 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES *

(Page 7 of 7)

Sequoyah Nuclear Plant Me eorological Facility

i Jan.1, 72 - Dec. 31, 75 l

Stability Class G l

Delta T > 4.0 deg. C/100m 1

Wind Speed (mph) '

O.6- 1.5 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total 1 N 0.003 0.06 0.33 0.09 0.0 0.0 0.0 0.0 '0.0 0.48 l NNE 0.005 0.10 1.03 0.20 0.0 0.0 0.0 0.0 0.0 1.33 i NE 0.005 0.09 0.74 0.12 0.0 0.0 0.0 0.0 0.0 0.95 ,

ENE 0.007 0.13 0.42 0.02 0.0 0.0 0.0 0.0 0.0 0.57 E 0.007 0.14 0.18 0.01 0.0 0.0 0.0 0.0 0.0 0.33 ESE 0.006 0.11 0.08 0.01 0.0 0.0 0.0 0.0 0.0 0.20 SE 0.005 0.09 0.08 0.0 0.0 0.0 0.0 0.0 0.0 0.17 SSE 0.008 0.16 0.21 0.0 0.0% 0.0 0.0 0.0 0.0 0.37 S 0.006 0.11 0.39 0.04 0.02 0.0 0.0 0.0 0.0 0.55 SSW 0.003 0.06 0.48 0.32 0.06 0.01 0.0 0.0 0.0 0'.89 SW 0.002 0.03 0.44 0.42 0.0 0.0 0.0 0.0 0.0 0.95 WSW 0.001 0.01 0.11 0.07 0.0 0.0 0.0 0.0 0.0 0.19 W 0.002 0.03 0.08 0.02 0.0 0.0 0.0 0.0 0.0 0.13 WNW 0.001 0.01 0.03 0.01 0.0 0.01 0.0 0.0 0.0 0.06 NW 0.001 0.02 0.06 0.03 0.0 0.0 0.0 0.0 0.0 0.11 NNW 0.001 0.02 0.08 0.03 0.0 0.0 0.0 0.0 0.0 0.13 SUBTOTAL 0.06 1.17 4.74 1.39 0.09 0.2 0.0 0.0 0.0 7.41 2379 stability class G occurrences out of total 32723 valid temperature difference readings.

2378 valid wind direction / wind speed readings out of total 2379 stability class G occurrences.

All columns and calm total 100 percent of net valid readings.

Meteorological facility located 0.74 Miles SW of Sequoyah Nuclear Plant.

Temprature Instruments 33 and 150 feet above ground.

Wind instruments 33 feet above ground.

i L

I SQN ODCM Revision 35 Page 133 of 163 i

Table 7.3 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES Submersion dose Air dose mrem /y per Ci/m3 mrad /y per Ci/m3 J DF ei DFsi DFg DFp ,

Kr-83m 7.56E-02 -

1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr 85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 Kr 90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51 E+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 7.11 E+02 3.36E+03 7.39E+02 I Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 I Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21 E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 I

Reference:

Regulatory Guide 1.109, Table B-1.

SQN ODCM Revision 35 Page 134 of 163

I Table 7.4 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES -

Range of Midpoint of Sector Element Sector Element Unrestricted Area boundary - 1 mile 0.8 mile 33 1 - 2 miles 1.5 miles 2 - 3 miles 2.5 miles 3 - 4 miles 3.5 miles 4 - 5 miles 4.5 miles '

S - 10 miles 7.5 miles 10 - 20 miles 15 miles j 20 - 30 miles 25 miles 30 - 40 miles 35 miles 40 - 50 miles 45 miles l

l

SQN ODCM Revision 35 Page 135 of 163 Table 7.5 POPULATION WITHIN EACH SECTOR ELEMENT Sector Midpoint (miles) 0.8 1.5 2.5 3.5 4.5 7.5 15 25 35 45 N 20 41 213 129 66 1784 5453 3470 2610 11145 NNE O 30 123 182 62 600 0628 4910 8250 10625 NE O O 67 67 94 581 2884 6998 7047 18080 ENE O 11 24 222 300 773 4707 5747 29477 18679 E O 70 11 191 137 918 7440 6808 5072 4129 ESE O 118 113 194 137 1849 46521 5044 1896 3624 SE O 179 322 168 205 1507 6005 5461 15641 3417 SSE O 125 370 750 601 2347 13242 8596 34279 1648 S 0 67 143 229 811 3930 28008 26690 19642 11622 SSW 0 82 140 400 170 8927 96966 55597 21349 11978 SW 0 10 306 634 194 9787 94225 23455 11641 11109 WSW 20 190 642 1124 1669 19089 28405 4106 15081 9548 W 10 20 233 657 657 5225 1580 6350 5699 7707 WNW 10 30 365 598 598 2622 6540 4920 6699 2450 NW 50 80 292 569 336 2696 1410 1750 1217 15856 NNW 10 263 80 75 213 1610 471 3130 2835 5719 1

SQN ODCM Revision 35 Page 136 of 163 Table 7.6 INHALATION DOSE FACTORS (mrem /pClinhaled)

(Page 1 of 8) ,

ADULT bone liver tbody thyroid kidney lung gi-lli H-3 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E 06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07

- Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 0.00E+00 0.00E+00 0.00E+00 1.08E-05 Cr-51 0.00E+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0.00E+00 ' 4.95E-06 7.87E-07 0.00E+00 1.23E-06 1.75E-04 9.67E-06 Mn-56 0.00E+00 1.55E 10 2.29E-11 0.00E+00 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E 06 2.12E 06 4.93E-07 0.00E+00 0.00E+00 9.01E-06 7.54E-07 i Fe-59 1.47E-06 3.47E-06 1.32E-06 0.00E+00 0.00E+00 1.27E-04 2.35E-05 Co-57 0.00E+00 8.65E-08 8.39E-OS 0.00E+00 0.00E+00 4.62E-05 3.93E-06 Co-58 0.00E+00 1.98E 07 2.59E-07 0.00E+00 0.00E+00 1.16E-04 1.33E-05 Co 60 0.00E+00 1.44E 06 1.85E 06 0.00E+00 0.00E+00 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E 06 0.00E+00 0.00E+00 2.23E-05 1.67E-06

! Ni-65 1.92E-10 2.62E 11 1.14E-11 0.00E+00 0.00E+00 7.00E-07 1.54E-06

~

Cu-64 0.00E+00 1.83E-10 7.69E 11 0.00E+00 5.78E-10 8.48E-07 6.12E-06 L Zn-65 4.05E-06 1.29E-05 5.82E-06 0.00E+00 8.62E-06 1.08E-04 6.68E-06 I 3 Zn-69 4.23E 12 8.14E 12 5.65E-13 0.00E+00 5.27E-12 1.15E-07 2.04E-09 Zn-69m 1.02E-09 2.45E-09 2.24E-10 0.00E+00 1.48E-09 2.38E-06 1.71E-05

. Br-82 0.00E+00 0.00E+00 1.69E-06 0.00E+00 0.00E+00 0.00E+00 1.30E-06 l Br 83 0.00E+00 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.90E-08 Br-84 0.00E+00 0.00E+00 3.91E-08 0.00E+00 0.00E+00 0.00E+00 2.05E 13

. Br-85 0.00E+00 0.00E+00 1.60E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb 86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E+00 2.08E-06 Rb-88 0.00E+00 4.84E-08 2.41E 08 0.00E+00 0.00E+00 0.00E+00 4.18E-19 Rb-89 0.00E+00 3.20E-08 2.12E 08 0.00E+00 0.00E+00 0.00E+00 1.16E 21 '

l Sr-89 3.80E-05 0.00E+00 1.09E-06 0.00E+00 0.00E+00 1.75E-04 4.37E-05 Sr-90 1.24E-02 0.00E+00 7.62E-04 0.00E+00 0.00E+00 1.20E-03 9.02E-05

! Sr 91 7.74E-09 0.00E+00 3.13E 10 0.00E+00 0.00E+00 4.56E-06 2.39E-05 i Sr 92 8.43E-10 0.00E+00 3.64E-11 0.00E+00 0.00E+00 2.06E-06 5.38E 06 l Y-90 2.61E-07 0.00E+00 7.01E-09 0.00E+00 0.00E+00 2.12E-05 6.32E-05 j Y-91m 3.26E-11 0.00E+00 1.27E 12 0.00E+00 0.00E+00 2.40E-07 1.66E 10

! Y-91 5.78E-05 0.00E+00 1.55E-06 0.00E+00 0.00E+00 2.13E-04 4.81E-05 i l

~

Y-92 1.29E-09 0.00E+00 3.77E-11 0.00E+00 0.00E+00 1.96E-06 9.19E-06 I Y 93 1.18E-08 0.00E+00 3.26E-10 0.00E+00 0.00E+00 6.06E-06 5.27E-05 i Zr-95 1.34E-05 4.30E-06 2.91 E-06 0.00E+00 6.77E-06 2.21E-04 1.88E-05 )

! Zr-97 1.21E-08 2.45E-09 1.13E-09 0.00E+00 3.71E-09 9.84E-06 6.54E-05 1

] Nb 95 1.76E-06 9.77E-07 5.26E-07 0.00E+00 9.67E-07 6.31E-05 1.30E-05 Nb-97 2.78E-11 7.03E-12 2.56E-12 0.00E+00 8.18E-12 3.00E-07 3.02E-08 ;

Mo-99 0.00E+00 1.51 E-08 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.10E-05 i i To 99m 1.29E 13 3.64E-13 4.63E 12 0.00E+00 5.52E-12 9.55E-08 5.20E-07 !

Tc 101 5.22E-15 7.52E-15 7.38E 14 0.00E+00 1.35E-13 4.99E-08 1.36E 21 4 Ru-103 1.91 E-07 0.00E+00 8.23E 08 0.00E+00 7.29E-07 6.31 E-05 1.38E-05 Ru-105 9.88E-11 0.00E+00 3.89E-11 0.00E+00 1.27E 10 1.37E-06 6.02E 06 Ru-106 8.64E 06 0.00E+00 1.09E-06 0.00E+00 1.67E-05 1.17E-03 1.14E-04 A9110m 1.35E 06 1.25E-06 7.43E-07 0.00E+00 2.46E 06 5.79E-04 3.78E-05 l

e

+ * ,.-.v -.--.e , m - - . - - r ,- --wt - - - -.-

I i

SQN ODCM Revision 35 ,

Page 137 of 163 l l

Table 7.6 INHALATION DOSE FACTORS j (mrem /pCiinhaled)

(Page 2 of 8)

ADULT ,

bone liver tbody thyroid kidney lung gi-Ili l Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0.00E+00 3.10E-04 5.08E-05 ]

Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.26E-05 l Sn-125 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0.00E+00 7.37E-05 6.81E-05 l

Te-125m 4.27E 07 1.98E-07 5.84E-08 1.31 E-07 1.55E-06 3.92E-05 8.83E-06 l Te-127m 1.58E-06 7.21 E-07 1.96E-07 4.11 E-07 5.72E-06 1.20E-04 1.87E 05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E 07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E 12 1.55E-12 4.87E-12 2.34E 11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E 12 5.46E 12 1.74E-07 2.30E Te 132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 l-130 5.72E-07 1.68E 06 6.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 l-131 3.15E-06 4.47E 06 2.56E-06 1.49E-03 7.66E-06 0.00E+00 7.85E-07 l-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.00E+00 5.08E-08 l-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0.00E+00 1.11E 06 l-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.00E+00 1.26E-10 1135 3.35E 07 C.73E-07 3.21 E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07 Cs 134 4.66E-05 1.06E-04 9.10E-05 0.00E+00 3.59E-05 1.22E-05 1.30E-06 Cs 136 4.88E-06 1.83E-05 1.38E-05 0.00E+00 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E 05 7.76E-05 5.35E-05 0.00E+00 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.145-08 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 9.41 E-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 1 Ce-143 2.33E-08 1.72E 08 1.91E-09 0.00E+00 7.60E-09 9.97E 06 2.83E-05 l Ce-144 4.29E-04 1.79E-04 2.30E-05 0.00E+00 1.06E-04 9.72E-04 1.02E 04 !

Pr-143 1.17E-06 4.69E-07 5.80E-08 0.00E+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E 13 0.00E+00 8.81E-13 1.27E-07 2.69E-18

~

Nd 147 6.59E-07 7.62E-07 4.56E-08 0.00E+00 4.45E-07 2.76E 05 2.16E-05 1 W 187 1.06E-09 8.85E-10 3.10E 10 0.00E+00 0.00E+00 3.63E-06 1.94E-05 Np 239 2.87E 08 2.82E-09 1.55E-09 0.00E+00 8.75E-09 4.70E-06 1.49E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

l

Reference:

Regulatory Guide 1.109, Table E 7.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG-0172 Ace Specific Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977 Table 8.

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I SQN ODCM I Revision 35 !

Page 138 of 163 l

Table 7.6 INHALATION DOSE FACTORS (mrem /pClinhaled) !

(Page 3 of 8) !

TEEN 5 bone 8iver ibody thyroid kidney lung gi ili H-3 f 1.59E-07 1.59E-07 1.59E 07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 i C-14 3.2SE-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 ;

Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 i P 32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1.16E-05 !

Cr-51 0.00E+00 0.00E+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 >

Mn-54 0.00E+00 6.39E-06 1.05E-06 0.00E+00 1.59E-06 2.48E-04 8.35D06 !

Mn-56 0.00E+00 2.12E 10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 7.18E-06 Fe-55 l 4.18E-06 2.98E-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E-07 i Fe 59 1.99E-06 4.62E 06 1.79E-06 0.00E+00 0.00E+00 1.91E-04 2.23E-05 Co-57 0.00E+00 1.18E-07 1.15E-07 0.00E+00 0.00E+00 7.33E-05 3.93E-06 ?

Co-58 0.00E+00 2.59E-07 3.47E-07 0.00E+00 0.00E+00 1.68E-04 1.19E-05 Co40 0.00E+00 1.89E-06 2.48E-06 0.00E+00 0.00E+00 1.09E-03 3.24E-05 !

Ni43 7.25E-05 5.43E-06 2.47E 06 0.00E+00 0.00E+00 3.84E-05 1.77E-06 ;

Ni45 2.73E-10 3.66E-11 1.59E 11 0.00E+00 0.00E+00 1.17E-06 4.59E-06 Cu44 0.00E+00 2.54E-10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 0.00E+00 1.08E-05 1.55E-04 5.83E-06 !

Zn-69 6.04E 12 1.15E-11 8.07E-13 0.00E+00 7.53E-12 1.98E-07 3.56E-08 }

Zn-69m 1.44E-09 3.39E-09 3.11E 10 0.00E+00 2.06E-09 3.92E 06 2.14E-05 i Br-82 0.00E+00 0.00E+00 2.28E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 4.30E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 - !

Br-84 0.00E+00 0.00E+00 5.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '

Br-85 0.00E+00 0.00E+00 2.29E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 Rb 88 0.00E+00 6.82E-08 3.40E-08 0.00E+00 0.00E+00 0.00E+00 3.65E-15 Rb-89 0.00E+00 4.40E-08 2.91E-08 0.00E+00 0.00E+00 0.00E+00 4.22E-17 Sr 89 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 Sr-90 1.35E-02 0.00E+00 8.35E-04 0.00E+00 0.00E+00 2.06E-03 9.56E 05 Sr-91 1.10E-08 0.00E+00 4.39E-10 0.00E+00 0.00E+00 7.59E-06 3.24E 05 Sr-92 1.19E-09 0.00E+00 5.08E 11 0.00E+00 0.00E+00 3.43E-06 1.49E-05 Y 90 3.73E-07 0.00E+00 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.99E-05 Y 91m 4.63E-11 0.00E+00 1.77E-12 0.00E+00 0.00E+00 4.00E-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.21E-06 0.00E+00 0.00E+00 3.67E-04 5.11E-05 Y-92 1.84E-09 0.00E+00 5.36E 11 0.00E+00 0.00E+00 3.35E-06 2.06E-05 Y-93 1.69E-08 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E 04 1.86E-05 Zr 97 1.72E-08 3.40E-09 1.57E 09 0.00E+00 5.15E-09 1.62E-05 7.88E-05 Nb 95 2.32E-06 1.29E-06 7.08E-07 0.00E+00 1.25'i-06 9.39E-05 1.21E-05 Nb-97 3.92E-11 9.72E 12 3.55E 12 0.00E+00 1.14E-11 4.91E-07 2.71E-07 Mo-99 0.00E+00 2.11E-08 4.03E-09 0.00E+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 0.00E+00 7.20E 12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 0.00E+00 1.90E 13 8.34E-08 1.09E-16 Ru-103 2.63E 07 0.00E+00 7.70E-07 0.00E+00 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E 10 0.00E+00 5.42E-11 0.00E+00 1.76E 10 2.27E-06 1.13E-05 Ru-106 1.23E-05 0.00E+00 1.55E 06 0.00E+00 2.38E-05 2.01 E-03 1.20E-04 Ag 110m 1.73E-06 1.64E-06 9.99E 07 0.00E+00 3.13E-06 8.44E-04 3.41 E-05

SQN ODCM Revision 35 Page 139 of 163 Table 7.6 INHALATION DOSE FACTORS (mrem /pCi inhaled)

(Page 4 of 8)

TEEN bone liver tbody thyroid kidney lung gi-Ili Sb-124 5.38E-06 9.92E 08 2.10E-06 1.22E-08 0.00E+00 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01 E-07 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-05 Sn-125 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0.00E+00 1.26E-04 7.29E-05 Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 0.00E+00 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E 10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01 E-05 Te-129m 1.74E-06 8.23E-07 2.81 E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te 129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 l-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 l-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 l132 1.99E 07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-07 l-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E-06 l-134 1.11 E-07 2.90E-07 1.05E-07 4.94E 06 4.58E-07 0.00E+00 2.55E-09 l-135 4.62E 07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0.00E+00 8.69E-07 Cs-134 6.28E-05 1.41 E-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 1.51 E-05 1.06E-06 Cs-138 5.82E 08 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E 10 1.18E-13 4.87E-12 0.00E+00 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E 06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E 11 1.32E-14 5.93E-13 0.00E+00 1.23E-14 4.11 E-07 9.33E 14 Ba-142 4.62E 12 4.63E 15 2.84E-13 0.00E+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E 08 2.95E-08 7.82E-09 0.00E+00 0.00E+00 2.68E-05 6.09E-05 ;

La-142 1.20E 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 2.71 E-07 0.00E+00 1.11 E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 0.00E+00 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11 E-04 2.53E-04 5.28E-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 6.41 E-08 0.00E+00 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E 10 0.00E+00 0.00E+00 5.92E-06 2.21E-05 Np 239 4.23E-08 3.99E-09 2.21E-09 0.00E+00 1.25E-08 8.11E-06 1.65E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

Reference:

Regulatory Guide 1.109, Table E-8.

J Dose Factors for Co-57, Zn-69m, Br-82, Nb.97, Sn-125. Sb-124 and Sb 125 are from NUREG-0172 Ace Specific Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 8.

1 SON ODCM Revision 35 Page 140 of 163 i Table 7.6 INHALATION DOSE FACTORS {

(mrem /pClinhaled) I (Page 5 of 8) ,

CHILD l bone liver ibody thyroid kidney lung gi-Ili i H-3 3.04E-07 3.04E 07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 i C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 0.00E+00 0.00E+00 0.00E+00 1.14E-05 Cr 51 0.00E+00 0.00E+00 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 0.00E+00 1.16E-05 2.57E-06 0.00E+00 2.71E-06 4.26E-04 6.19E-06 Mn 56 0.00E+00 4.48E 10 8.43E-11 0.00E+00 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 0.00E+00 0.00E+00 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 0.00E+00 0.00E+00 3.43E-04 1.91E-05 Co-57 0.00E+00 2.44E-07 2.88E-07 0.00E+00 0.00E+00 1.37E-04 3.58E-06 Co-58 0.00E+00 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2.99E-04 9.29E-06 Co40 0.00E+00 3.55E-06 6.12E-06 0.00E+00 0.00E+00 1.91E-03 2.60E-05 Ni43 2.22E-04 1.25E 05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 0.00E+00 0.00E+00 2.21E-06 2.27E-05 Cu44 0.00E+00 5.39E-10 2.90E-10 0.00E+00 1.63E-09 2.59E-06 9.92E-06 Zn45 1.15E-05 3.06E-05 1.90E 05 0.00E+00 1.93E 05 2.69E-04 4.41E-06 Zn-69 1.81 E-11 2.61E-11 2.41E-12 0.00E+00 1.58E-11 3.84E-07 2.75E-06 Zn-69m 4.26E-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71E-05 Br-82 0.00E+00 0.00E+00 5.66E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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-85 0.00E+00 0.00E+00 6.84E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb 86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+00 2.16E-06 Rb-88 0.00E+00 1.52E 07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E-09 Rb-89 0.00E+00 9.33E 08 7.83E-08 0.00E+00 0.00E+00 0.00E+00 5.11E-10 Sr 89 1.62E 04 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr 90 2.73E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 Sr 92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E-06 6.55E-05 Y-90 1.11 E-06 0.00E+00 2.99E-08 0.00E+00 0.00E+00 7.07E 05 7.24E-05 Y-91m 1.37E 10 0.00E+00 4.98E-12 0.00E+00 0.00E+00 7.60E 07 4.64E-07 Y-91 2.47E-04 0.00E+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.97E-05 Y 92 5.50E-09 0.00E+00 1.57E-10 0.00E+00 0.00E+00 6.46E 06 6.46E-05 Y 93 5.04E-08 0.00E+00 1.38E-09 0.00E+00 0.00E+00 2.01E-05 1.05E-04 Zr 95 5.13E-05 1.13E-05 1.00E-05 0.00E+00 1.61E 05 6.03E-04 1.65E-05 Zr 97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-05 9.49E-05 Nb 95 6.35E-06 2.48E-06 1.77E-06 0.00E+00 2.33E-06 1.66E-04 1.00E-05 Nb-97 1.16E 10 2.08E-11 9.74E 12 0.00E+00 2.31E-11 9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E 13 9.41E-13 1.56E 11 0.00E+00 1.37E 11 2.57E-07 1.30E-06 i Tc-101 2.19E 14 2.30E-14 2.91E 13 0.00E+00 3.92E-13 1.58E-07 4.41E-09 !

Ru-103 7.55E-07 0.00E+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 ,1.21E-05 Ru-105 4.13E-10 0.00E+00 1.50E-10 0.00E+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E 05 0.00E+00 4.57E-06 0.00E+00 4.97E-05 3.87E-03 1.16E-04 Ag-110m 4.56E-06 3.08E-06 2.47E-06 0.00E+00 5.74E-06 1.48E-03 2.71 E-05 i

l l

1

SQN ODCM Revision 35 Page 141 of 163 Table 7.6 INHALATION DOSE FACTORS (mrem /pCIinhaled)

(Page 6 of 8)

CHILD bone liver tbody thyroid kidney lung gi-lli Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 0.00E+00 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.00E+00 6.27E-04 1.09E-05 Sn-125 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0.00E+00 2.43E-04 7.17E-05 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.00E+00 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E 07 1.71 E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E 05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 l-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61 E-06 0.00E+00 1.38E-06 l-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0.00E+00 7.68E-07 l-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0.00E+00 8.65E-07 l133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0.00E+00 1.48E-06 l-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.00E+00 2.58E-07 l-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 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 0.00E+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71 E-07 2.27E-07 1.50E-07 0.00E+00 1.68E-07 1.84E-08 7.29E-08 Ba 139 4.98E-10 2.66E-13 1.45E 11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E 12 0.00E+00 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E 15 7.54E-13 0.00E+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 0.00E+00 0.00E+00 4.94E-05 6.10E-05 La-142 3.50E 10 1.11E-10 3.49E-11 0.00E+00 0.00E+00 2.35E-06 2.05E 05 Ce-141 1.06E-05 5.28E-06 7.83E-07 0.00E+00 2.31E-06 1.47E-04 1.53E-05 Ce 143 9.89E-08 5.37E-08 7.77E-09 0.00E+00 2.26E-08 3.12E 05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 0.00E+00 8.11E-07 1.17E 04 2.63E-05 Pr-144 1.61E-11 4.99E 12 8.10E-13 0.00E+00 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 0.00E+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E 09 2.61 E-09 1.17E-09 0.00E+00 0.00E+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.57E-05 1.73E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

Reference:

Regulatory Guide 1.109, Table E-9.

Dose Factors for Co-57,2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG-0172 Ace Specific Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 8.

I I

SQN ODCM Revision 35 Page 142 of 163 Table 7.6 INHALATION DOSE FACTORS (mrem /pCiinhaled)

(Page 7 of 8)

INFANT bone liver tbody thyroid kidney lung gi-ill H-3 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E 06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E 06 P-32 1.45E-03 8.03E+05 5.53E-05 0.00E+00 0.00E+00 0.00E+00 1.15E-05 Cr 51 0.00E+00 0.00E+00 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E 07 j Mn-54 0.00E+00 1.81E-05 3.56E-06 0.00E+00 3.56E-06 7.14E-04 5.04E-06 Mn-56 0.00E+00 1.10E-09 1.58E-10 0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 l Fe 59 9.69E-06 1. bee 05 6.77E-06 0.00E+00 0.00E+00 7.25E-04 1.77E-05 Co-57 0.00E+00 4.65E-07 4.666-07 0.00E+00 0.00E+00 2.71E-04 3.47E-06 Co-58 0.00E+00 8.71E-07 1.30E-06 0.00E+00 0.00E+00 5.55E-04 7.95E-06 ,

Co40 0.00E+00 5.73E-06 8.41E-06 0.00E+00 0.00E+00 3.22E-03 2.28E-05 ;

Ni-63 2.42E-04 1.46E-05 8.29E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 :

Ni45 1.71E-09 2.03E 10 8.79E-11 0.00E+00 0.00E+00 5.80E-06 3.58E-05 l Cu44 0.00E+00 1.34E-09 5.53E-10 0.00E+00 2.84E-09 6.64E-06 1.07E-05 l Zn-65 1.38E-05 4.47E-05 2.22E-05 0.00E+00 2.32E-05 4.62E-04 3.67E-05 Zn-69 Zn-69m 3.85E-11 6.91E-11 5.13E-12 0.00E+00 2.87E-11 1.05E 06 9.44E-06 i 8.98E-09 1.84E-08 1.67E-09 0.00E+00 7.45E-09 1.91E-05 2.92E-05 '

Br-82 0.00E+00 0.00E+00 9.49E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 2.72E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 2.86E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Br-85 0.00E+00 0.00E+00 1.46E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 J Rb-86 0.00E+00 1.36E-04 6.30E-05 0.00E+00 0.00E+00 0.00E+00 2.17E-06 Rb-88 0.00E+00 3.98E-07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 2.42E-07 Rb-89 0.00E+00 2.29E-07 1.47E-07 0.00E+00 0.00E+00 0.00E+00 4.87E-08 Sr-89 2.84E-04 0.00E+00 8.15E-06 0.00E+00 0.00E+00 1.45E-03 4.57E-05 1 Sr-90 2.92E-02 0.00E+ 00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr 91 6.83E-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 0.00E+00 2.79E-10 0.00E+00 0.00E+00 1.70E-05 1.00E-04 Y-90 2.35E 06 0.00E+00 6.30E-06 0.00E+00 0.00E+00 1.92E-04 7.43E-05 Y-91m 2.91E 10 0.00E+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 Y-91 4.20E-04 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1.75E-03 5.02E-05 Y-92 1.17E 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.75E-05 9.04E-05 Y-93 1.07E-07 0.00E+00 2.91E-09 0.00E+00 0.00E+00 5.46E 05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 0.00E+00 2.22E-05 1.25E-03 1.55E-05 Zr 97 1.07E-07 1.83E-08 8.36E-09 0.00E+00 1.85E-08 7.88E-05 1.00E-04 Nb 95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.05E-06 Nb-97 2.44E 10 5.21E 11 1.88E-11 0.00E+00 4.07E-11 2.37E-06 1.92E-05 Mo-99 0.00E+00 1.18E-07 2.31E-08 0.00E+00 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E 11 0.00E+00 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 0.00E+00 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 0.00E+00 4.85E-07 0.00E+00 3.03E-06 3.94E 04 1.15E-05 Ru-105 8.74E 10 0.00E+00 2.93E-10 0.00E+00 6.42E-10 1.12E-05 3.46E 05 Ru-106 6.20E-05 0.00E+00 7.77E-06 0.00E+00 7.61E-05 8.26E-03 1.17E-04 Ag-110m 7.13E-06 5.16E-06 3.57E-06 0.00E+00 7.80E 06 2.62E-03 2.36E-05 l l

SQN ODCM Revision 35 Page 143 of 163 Table 7.6 INHALATION DOSE FACTORS

, (mrem /pCiinhaled)

(Page 8 of 8)

INFANT bone liver tbody thyroid kidney lung gi-Ill Sb-124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0.00E+00 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 Sn-125 1.01E-05 2.51E-07 6.00E-07 2.47E-07 0.00E+00 6.43E-04 7.26E-05 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 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81 E-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 3.91 E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E 10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51 E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 l-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 l-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E+00 7.56E-07 l-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.00E+00 1.36E-06 l133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 l-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E-07 l-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E 06 0.00E+00 1.31 E-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 Cs-138 3.61 E-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 1.11 E-06 4.95E-07 La-140 3.61 E-07 1.43E-07 3.68E-08 0.00E+00 0.00E+00 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E 10 6.46E 11 0 ME+00 0.00E+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E 05 1.42E-06 C E+00 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 0 00E+00 4.03E-08 8.30E-05 3.55E-05 Ce 144 2.28E-03 8.65E-04 1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 0.00E+00 1.41E-06 3.09E-04 2.6SE-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 5.81 E-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 4.25E-05 1.78E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

Reference:

Regulatory Guide 1.109 Table E 10.

Dose Factors for Co-57, Zn-69m. Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG-0172 Ace Soecific Radiation Dose Commitment Factors for a One Year Chronic intake. November 1977. Table 8.

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SON ODCM Revision 35 Page 146 of 163 Figure 7.3 GASEOUS RADWASTE TREATMENT SYSTEM CVCSVCT Unit 1

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SON ODCM Revision 35 Page 147 of 163 l l

Figure 7.4 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES (All Stability Classes) l 10 09 08 07 l

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l SON ODCM Revision 35 Page 148 of 163 Figure 7.5 VERTICAL FTANDARD DEVIATION OF MATERIAL IN A PLUME 1000 - , ,

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SON ODCM Revision 35 l Page 149 of 163 Figure 7.6 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES l (All Stability Classes) l l

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SON ODCM l Revision 35 Page 150 of 163 I

SECTION 8.0 TOTAL DOSE l

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SQN ODCM Revision 35 Page 151 of 163 SECTION 8.0 TOTAL DOSE 8.1 ANNUAL MAXIMUM INDIVIDUAL DOSES - TOTAL REPORTED DOSE To determine compliance with 40 CFR 190 as required in ODCM Administrative Control 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 sum for each quarter and summing over the four quarters. .

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i SON ODCM i Revision 35 i Pa0e 152 of 163 i

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SECTION 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l

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i SON ODCM Revision 35 Page 153 of 163 1

SECTION 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 9.1 MONITORING PROGRAM l An environmental radiological monitoring program shall be conducted in accordance with ODCM Control 1.3.1. The monitoring program described in Tables 9.1,9.2, and 9.3, and in Figures 9.1,

)

1 9.2 and 9.3 shall be conducted. Results of this program shall be reported in accordance with ODCM Administrative Control 5.1. 1 i

The atmospheric environmental radiological monitoring program shall consist of monitoring ;

stations from which samples of air particulates and atmospheric radiciodine shall be collected. j l

The terrestrial monitoring program shall consist of the collection of milk, soil, ground water, !

drinking water, and food crops. In addition, direct gamma radiation levels will be measured in the I vicinity of the plant.

The reservoir sampling program shall consist of the collection of samples of surface water, sediment, clams, and fish.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavailability, or to malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.

9.2 DETECTION CAPABILITIES Analytical techniques shall be such that the detection capabilities listed in Table 2.3-3 are achieved.

9.3 LAND USE CENSUS A land use survey shall be conducted in accordance with Control 1.3.2. The results of the survey shall be reported in the Annual Radiological Environmental Operating Report.

9.4 INTERLABORATORY COMPA71 SON PROGR AM Analyses shall be performed on radioactive materials supplied as part of an interlaboratory Comparison Program which has been approved by the NRC. A summary of the results obtained in the intercompanson shall be included in the Annual Radiological Environmental Operating Report (or the EPA program code designation may be provided).

If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report.

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SQN ODCM l Revision 35 l Page 154 of 163 Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 1 of 4)

Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations

Collection Frequency of Analysis AIRBORNE Particulates 4 samples from locations Continuous sampler Analyze for gross beta (in different sectors) at or operation with sample radioactivity > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months near the site boundary collection once per 7 d following filter change.

(LM-2,3,4,and 5) (more frequently if Perform gamma required by dust isotopic analysis on 4 samples from loading) each sample if gross communities beta > 10 times year 1y approximately 6-10 miles mean of control i distance from the plant. sample.

(PM-2,3,8,and 9) Composite at least 1 once per 31 d (by 4 samples from control location for gamma locations greater than 10 scan) miles from the plant (RM-1,2,3,and 4)

Radioiodine Samples from same Continuous sampler 1-131 at least once per location as air operation with filter 7d particulates collection once per 7 d Soil Samples from same Once per year Gamma scan, Sr-89, locations as air Sr-90 once per year particulates DIRECT RADIATION 2 or more dosimeters Once per 92 d Gamma dose at least placed at locations (in once per 92 d different sectors at or near the site boundary) in each of the 16 sectors.

Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3 l

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SON ODCM Revision 35 Page 155 of 163 Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 2 of 4)

Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations

Collection Frequency of Analysis DIRECT RADIATION (continued) 2 or more dosimeters placed at stations located

>5 miles from the plant in each of the 16 sectors 2 or more dosimeters in at least 8 additional locations of special interest.

_WATERBORNE Surface TRM 497.0 Collected by Gamma scan of each TRM 483.4 automatic sequential composite sample.

TRM 473.2 type sampler"with Composite for H-3 composite samples analysis at least once collected at least per 92 d.

once per 31 d.

Ground 1 sample adjacent to At least once per 92 d Gross beta and gamma plant (location W-6) scan, Sr-89, Sr-90 and H-3 analysis at least 1 sample from once per 92 d.

groundwater source up-gradient

Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3

" Samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SON ODCM Revision 35 Page 156 of 163 Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 3 of 4)

Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations

Collection Frequency of Analysis WATERBORNE (continued)

Drinking 1 sample at the first potable Collected by automatic Gross beta and water supply downstream sequential type sampler" gamma scan of from the plant with composite samples each composite (TRM 473.0) collected at least once per sample.

31 d Composite for H-1 sample at the next 2 3, Sr-89, and Sr.

downstream potable surface Grab sample once per 31 90 at least once water rapplies (greater than d. per 92 d.

10 mises downstream)

(TRM 470.5 and 465.3) Samples collected by automatic sequential type 2 samples at controllocations sampler" with composite l (TRM 497.0 and 503.8)* sample collected at least once per 31 d.

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Sediment TRM 496.5,483.4,480.8, At least once per 184 d Gamma scan of TRM 472.8 each sample.

Shoreline TRM 485, TRM 478. TRM At least once per 184 d Gamma scan of 477 each sample.

INGESTION Milk 1 sample from milk producing At least once per 15 d. Gamma isotopic j animals in each of 1-3 areas and 1-131 analysis ;

indicated by the cow census of each sample. !

where doses are calculated to Sr 89, Sr-90 once be highest. per year.

If samples are not available from a milk animallocation, doses to that area will be estimated by projecting the doses from concentrations detected in milk from other sectors or samples of vegetation will be taken monthly when milk is not available.

At least 1 sample from a control location.

Sample 65utions are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3

" Samples scall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

" The surface water sample collected at TRM 497.0 is considered a control for the raw drinking water sample.

1 SON ODCM Revision 35 Page 157 of 163 Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 4 of 4)

Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations

Collection Frequency of Analysis INGESTION Fish 1 sample each from At least once per 184 Gamma scan on edible Chickamauga and Watts d. One sample of portion. ,

Bar Reserviors. each of the following I species:

Channel Catfish Crappie Smallmouth Buffalo invertebrates 1 sample downstream At least once per 184 d Gamma scan on edible (Asiatic Clams) from plant discharge" portion.

1 sample upstream of l plant discharge" Food 1 sample each of At least once per 365 d Gamma scan on edible Products principle food products at time of harvest. The portion.

grown at private gardens types of foods and/or farms in the available for sampling vicinity of the plant. will vary. Following is a list of typical foous which may be available:

Cabbage and/orlettuce Com Green Beans Potatoes Tomatoes ,

Vegetation Samples from farms At least once per 31 d 1-131 and gamma scan j producing milk but not at least once per 31 d '

providing a milk sample (Farm Em)

Control Sample from one I control dairy farm (Farm S)

Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3

" No permanent stations established. Locations depend on availability of clams.

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SQN ODCM Revision 35 Page 158 of 163 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map Location Approximate Indicator (I) Samples Number

Station Sector Distance or Control Collectedb 2 LM-2 N 0.8 l AP,CF,S 3 LM-3 SSW 2.0 l AP,CF,S 4 LM-4 NE 1.5 l AP,CF,S 5 LM-5 NNE 1.8 l AP,CF,S 7 PM-2 SW 3.8 i AP,CF,S 8 PM-3 W 5.6 l AP,CF,S 9 PM-8 SSW - 8.7 l AP,CF,S 10 PM-9 WSW 2.6 I AP,CF,S 11 RM-1 SW 16.7 C AP,CF,S 12 RM-2 NNE 17.8 C AP,CF,S 13 RM-3 ESE 11.3 C AP,CF,S 14 RM-4 WNW 18.9 C AP,CF,S ,

15 Farm B NE 43.0 C M 16 Farm C NE 16.0 C M 17 Farm S NNE 12.0 C M, V 18 Farm J WNW 1.1 1 M 19 Farm HW NW 1.2 i M. W, 20 Farm EM N 2.6 I V 24 Wellpo. 6 NNE 0.15 l W 31 TRM 473.0 (C. F. Industries) -

11.5, 1 PW 32 TRM 470.5 (E.1. DuPont) -

14.0, 1 PW 33 TRM 465.3 (Chattanooga) -

19.2, l, PW 34 TRM 497.0 -

12.5* C SW 35 TRM 503.8 (Dayton) -

19.3 C PW 36 TRM 496.5 -

12.q C SD 37 TRM 485.0 - 0.5* C SS 38 TRM 483.4 -

1.1 I SD, SW 39 TRM 480.8 -

3.7, 1 SD 40 TRM 477.0 -

7.5 , 1 SS 41 TRM 473.2 -

11.3, 1 SW 42 TRM 472.8 -

11.7, 1 SD 44 TRM 478.8 -

6.5 1 SS 46 TRM 471530 (Chickamauga -

1/C F/CL Reservoir) 47 TRM 530-602 - - C F 48 Farm H NE 4.2 1 M

See figures 9.1,9.2, and 9.3

, Samole Codes: AP = Air particulate filter CF = Charcoal filter CL = Clams F = Fish M = Milk PW = Public water R = Rainwater SD = Sediment S = Soil

, SS = Shoreline sediment SW = Surface water V = Vegetation W = Well water

, A control for well water.

TRM = Tennessee River Mile.

, Distance from plant discharge (TRM 484.5)

Surface water sample also used as a control for public water.

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SQN ODCM l

Revision 35 l Page 159 of 163 l l

l Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS (Page 1 of 2)

I Map Approximate (Onsite )a f Location Distance or '

Number Station Sector (Miles) Offsite (Off) 3 SSW 1C SSW 2.0 On 4 NE-1A NE 1.5 On :

5 NNE-1 NNE 1.8 On 7 SW-2 SW 3.8 Off 8 W-3 W 5.6 Off 9 SSW-3 SSW 8.7 Off 10 WSW-2A WSW 2.6 Off ;

11 SW 3 SW 16.7 Off .

12 NNE-4 NNE 17.8 off 13 ESE-3 ESE 11.3 Off 14 WNW-3 WNW 18.9 Off 49 N-1 N 0.6 On 50 N-2 N 2.1 Off 51 N-3 N 5.2 Off 52 N-4 N 10.0 Off 53 NNE-2 NNE 4.5 Off 54 NNE-3 NNE 12.1 Off 55 NE 1 NE 2.4 Off 56 NE 2 NE 4.1 off 37 ENE-1 ENE 0.4 On 58 ENE 2 ENE 5.1 Off 59 E-1 E 1.2 On 60 E-2 E 5.2 Off 61 ESE-A ESE 0.3 On 62 ESE-1 ESE 1.2 On 63 ESE 2 ESE 4.9 Off i 64 SE A SE 0.4 On 65 E-A E 0.3 On 66 SE 1 SE 1.4 On 67 SE 2 SE 1.9 On 68 SE-4 SE 5.2 Off l 69 SSE-1 SSE 1.6 On l 70 SSE-2 SSE 4.6 Off ;

71 S-1 S 1.5 On 72 S-2 S 4.7 Off 73 SSW-1 SSW 0.6 On 74 SSW 2 SSW 4.0 Off aTLDs designated onsite are those located two miles or less from the plant.

TLDs designated offsite are those located more than two miles from the plant.

SQN ODCM Revision 35 Page 160 of 163 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS (Page 2 of 2)

Map Approximate

, Onsite (On)a Location Distance or

. Number Station Sector (Miles) Offsite (Off) 75 SW-1 SW 0.9 On 76 WSW-1 WSW 0.9 On 77 WSW2 WSW 2.5 Off 78 WSW 3 WSW 5.7 Off 79 WSW-4 WSW 7.8 Off 80 WSW 5 WSW 10.1 Off 81 W1 W 0.8 On 82 W-2 W 4.3 Off 83 WNW-1 WNW 0.4 On 84 WNW 2 WNW 5.3 Off 85 NW-1 NW 0.4 On 86 NW-2 NW 5.2 Off i

87 NNW-1 NNW 0.6 On 88 NNW-2 NNW 1.7 on 89 NNW-3 NNW 5.3 Off 90 SSW-1B SSW 1.5 On l

I aTLDs designated onsite are those located two miles or less from the plant.

TLDs designated offsite are those located more than two miles from the plant.

i e

l i

SON ODCM Revision 35 Page 161 of 163 Figure 9.1 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THE PLANT I

348.75 N 11.25 !

NNW NNE 326.25 33.75 NW . 2 NE !

303.75 4

/ 56.25 WNW

' \ '8 ENE l

281.25 W-

- we

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/

EQUOYAH 78.75

' 5 NUCLEAR -E f ,, [ ~

,t PLANT l 258.75 y' #

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101.25 76 /

4 WSW */. ESE

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SSE 191.25 S

heale l O Mile 1 l

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Revision 35 Page 162 of 163

(

Figure 9.2 ENVIRONMENTAL MONITORING LOCATIONS FROM ONE TO FIVE MILES FROM I THE PLANT 34a.7s N 11.2s NNW NNE d 33.7s l assJs l i i j NW

/*

NE 303.75 ss.25 l

I 56 WNW ENE e55

1 1 I estas -

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1 59 to 2 i ass.7s 77 d6 t o t.as !

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SW SE

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'46 *70 213.7s tasas SSW ,

SSE t o t.as 3 iss.7s scALs 6 1 2 kmLES w

i SON ODCM Revision 35 Page 163 of 163 Figure 9.3 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN FIVE MILES FROM THE PLANT S48.75 e ,, ggag

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324.28 "N yg sw .

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178 se.2s

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e 88 W . 78.75 14 an

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