ML20029B248
| ML20029B248 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/31/1990 |
| From: | Wallace E TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9103060296 | |
| Download: ML20029B248 (62) | |
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d fedesseeAw usa,. E cm e ru,mr n , r,a s n .ee vn February 25, 1991 U.S. Nuclear Regulatury Commission AT'IN : Document Cont-rol Desk Washington, D.C. 20555 Centlemen:
In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 - SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND THE RADIOLOGICAL 'MPACT ASSESSMENT REPORTS Enclosure 1 contains the Semiannual Radioactive Ef fluent Release Report that is being submitted in accordance wi'_h SQN Technical Specification 6.9.1.8 f or the period of July 1 to December 31, 1990. Enclosure 2 contains the Radiological Impact Assessment Report for the period of January 1 to December 31, 1990.
Please direct questions concerning this issue to J. D. Smith at (615) 843-6672.
Very truly yours, .
l TENNESSEE VALLEY AUTl!0RITY G)&
E. G. Wallace, Manager l Nuclear Licensing and l Regulatory Affairs l
Enclosures I
cc: See page 2 c,
f 9103060296 901231 P' ' -
PDR ADOCK 05000327 i '/ i i R PDR v 'l
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U.S.. Nuclear-Regulatory Commission February 25, 1991 cc (Enclosures):
Ms. S. C. Black, Deputy Director
. Project Directorate,II-4 U.S. Nuclear; Regulatory Commission One White' Flint,' North 11555 Rockville Pike ,
Rockville, Maryland 20852 Mr.'J. N. Donohew Project Manager U.S. Nuclear degulatory Commission-
.One White ^ Flint, North' 11555'Rockville Pike
, Rockville, Maryland 20852 NRC. Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy. Daisy Tennessee 37379 Mr. B.'A. Wilson,LProject. Chief U.S.~. Nuclear Regulatory Commission Region II 101.Marietta: Street, NW, Suite:2900.
- Atlanta. Georgia 30323
' I
. .. . .. . . - . . . . _ .-.. ._~ . - . . . ... .. . . . . -. - ..-.- .. . -. . . . ._. ,
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ENCLOSURE 1 SEQUOYAH NUCLEAR-PLANT EFFLUENT AND WASTE DISPOSAL SE?ilANNUAL REPORT SUPPLEMENTAL INFORMATION July 1 to December 31,'1990 x
e G
5 4
5 y w m + +s m ,
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFOP.MATION 2nd KALF 1990
- 1. Regulatory Limits
- a. Fission and Activation cases:
Instantaneous - Radionuclide Dependant (all release points)
Administrative release rate limite per radionuclide have been established and are besed upon the methodology in Section 1.2.3 of the Sequoyah Offsite Dose Calculation Manual (ODCM) for each vent based on design flowr2te. The ODCM will not be exceeded until the sum of individual radionuclide release rate to ODCN limit ratios axceed 1.0.
- b. and c. 1-131, 1-133, tritium, and particulates with half-lives 40 Days Instantaneous - Radionuclide Dependant Total plant release rate limits per radionuclide have been established and are based upon the methodology in Section 1.2.4 of the Sequoyah Offsite Dose Calculation Manual,
- d. Liquid effim34t: J.MPC&1.0 (reference 10CFR20, Appendix B.
Table II, column 2).
P.
l l
I EFFLUPNT AND WASTE DISPOSAL SEM1 ANNUAL REPORT SUPPLEM3NTAL INFORMATION And HALF }jlQ
- 2. Maximum pern8.ssible concentratit.ns
- a. Fission and Activation Cases Not Applicable
- b. lodines: Not Applicable
- c. particulates, half-lives 48 days Not Applicable
- d. Liquid effluents: sum of individual MPC ratios 61.0 (ref.
- 3. Average Energy - Not Applicable
- d. Measurements and ApproximationJ of Total Radiosctivity NOTE: Every effort la made to ensure that all effluents from Sequoyah are conducted such that all Offsite Dose calculation Manual (ODCM) Lower Limits of Detection (LLDs) are met. L'henever an analysis does not identify a radioisotope, a "0.00E-01 Ci" is recorded for the rolsace. This does not necessarily mean that no activity was teleased for that particular radtonuclide, but that the concentration wen below the ODCM and analysis LLDs. Refer to Tab 1vs A and B for estimates of these typical LLD values.
- s. Fission and Activation Cases Airborne effluent gaseous activity is continuously monitored and recot ;sd . A/04 onal grab samples from the shield bu11 dins, auxiliary br !d as, service building, and condenser vacuum exhausts are . ken and analyzed at least monthly to determine the quantity of noble Sao activity released for the mor.th cased on the averaf.e 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 parcent within one hour (samplins only required it dose equivalent 1-131 concentration in the primary coolant has inercased more than a factor of 3 and the noble ses activity monitor shows that the conisinment activity has increased more than a factor of 3). The vent flowrates for the shleid buildles, auxiliary building, service building, and condenser vacuum exhauste are determ).ned and recorded once a shift.
EFFLUENT AND WASTE DISPOSAL SEM1ANKVAL rep 0RT SUPPLEMENTAL INFORMATION 2nd HALF 1932
! 4. Measurements ant *pproximation of Total Radioactivity (esntinu.4)
I
- a. Fission and Activation Cases (continuet)
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 periode, the activity released from purging or venting of containment, and the activity released from waste gas decay tank (s),
- b. and c. Todines and iarticulates lodi'se and particulate activity is continuously monitored and recorded. Charcoal and particulate samples are taken from the shield and auxiliary building exhausts and analyzed at least weekly to determine the total activity released f rom the plant based on the average vent flowrates recorded for sampling period.
Also, particulate and charcoal samples are taken from the auxiliary and shield building exhausts once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 2 days following startup, shutdown, or a rated thermal power change exceeding 15 percent within one hour. The quantity of iodine and particula'a t eleased f rom each vent during each sampling period is then dete: mined using the average vent flowrates recorded for the sampling period and activity concentration.
The vent flowrates from the shield and auxiliary building exhausts are recorded once a shift.
The total particulate and iodine activity released for the month is then determined by summing all of the activity released from the shield and auxiliary bt'ilding exhausts for all sampling periods,
- d. Liquid Effluents (1) patch (Radwaste and condensato regenerants to cooling tower blowdown)
Total samma isotopic activity concentrations are detetmined 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 guitiplying by the total volume discharged. The total activity released during a month is then determined by cumming the activity content of each batch discharged during the month.
3
EFFLUENT AND WASTE DISPOSAL SEMIAWWUAL REPORT SUPPLEMENTAL INFORMATIOW 2nd RALF 1193
- 4. Measurements and Approximation of Total Radioactivity (continued)
(2) Continuous Releases and periodic Continuous Releases (Condensate regenerants, turbine building sump and steam generator blowdown)
Total samma isotopic activity concentration is determined dally 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 nultiplying by the total volume
.scharged. The total activity released during the month is then t.4ter3Lned by summing the activity content of each daily and weekly composite for month, f -5. Batch Quarter Value guarter Un_its 3rd 4th a.. Liquid
- 1. Number of. batches released (Radwasto only) 126 122 Rech
- 2. _ Total time period for batch '
releases 18,265 16,668 Minutes
- 3. Maximum time period for a batch release 305 180 Minutes
- 4. Average time period _for batch
. releases 145 137 Minutes
- 5. Minimum stream flow during periods of effluent into a flowing stream: (a) (a)
(a) -See annual !
Radiological impact Assssement Report.
b.. Gaseous
- 1. Number of batches released 200. 117 Each
- 2. Total time period for batch releases .
25,264 14,828 Minutes 3., Maximum time period for a batch release 2,039 1,440 Minutes
- 4. Average time period for batch-releases 126 84 Minutes
- 5. Minimum time period for a batch '
release 15 19 Minutes
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 2nd HALF 1990 1
- 6. Abnormal Releaseo Value Units Ouarter Quarter )
3rd a t,L l
- a. Liquid !
(1) Number of P.oleases 0 0 (2) Total Activity Released LOOE-01 0,00E-01 Ci
- b. Caseous ]
(1) Number of Releases 0._ 0 1 (2) Total Activity Released 0,00E-01 0.00E-01 C1
- 7. Offsite Dose calculation Manual (ODcM)
Were any char 4cs made to the ODCM during the reporting periodt Yes K___ No l
L.
.__ ..--.--- -.- - . ..~...--_ - _ -. .--- _-._ .
, 1 I
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT !
2nd RALF 1192 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES l
.ir,s_ 4th A. Fission and Activation Unit _gte % Error .Qtr. %ErrgI Productt i
- 1. Total Released Curies 2.63E-01 11.8E+01 3.89E-01 11.8E+01
- 2. Avera5e Diluted Cone.
During Period of All Identified Isotopes pCi/mi 1.84E-07 4.69E-07
- 3. Percent of Applicable Limit ({MPC61) % 4.48E-01 2.63E-01 M21Et Percent of applicable limit is based on identified isotope concentration after dilution, related to their apprortiate NPC concentration and sum of all the isotope fractions compared to 1.0.
B. Tritium
- 1. Total Released Curies 1.78E+02 11.8E+01 1.64E+02 11.8E+01
- 2. Average Diluted pCi/mi 1.24E-04 1.13E-04 Conc. Durin8 Period
- 3. Percent of Applicable Limit (3.0E-03 pCi/ml) % A.14E+00 3.17E+00 C. Dissolved and Entrained Gases 1.- Total Released Curies 1.05E+00 13.9E+01 9.52E-02 13.9E+01 2.. Avera5e Diluted pC1/mi 7.34E-01 6.58E-08 Conc. During Period
- 3. Percent.of Applicable Limit.(2.0E-04 pCL/ml) % 3.61E-01 3.29E-02 D.. Gross Alpha Radioactivity
- 1. Total Released curies 3.44E-06 12.0E+01 0.00E-01 12.0E+01 E. .19,1ume of Weste Releasof l(Before Dilution) Liters 1.05E+07 14.0E+00 2.13E+01 14.0E+00 F. 12. lune of Dilukign Liters 1.42E+09 11.1E+01 1.42E+09 11.1E+01 Water for Pers,gd L
EFFLUENT AND WASTE DISPOSAL SEMIANKUAL REPORT Znd HALF 1990 LIQUID EFFLUENTS TOTAL PLANT DISCKARGE G. Isotope Summary (Note Refer to Table A for values reported as 0.00E-01)
Required by ODCM/Others Fission and Activation Products Continuous Mode Eatch Mode Nuclide Unit Quartet Qyarter QuarteI Quartet 3rd__ 4th , 3rd . 4th
- 2. Strontium-90 CL 0,00E-01 0.00E-01 0.00E-01 Q100E-01
- 4. Manganese-54 Ci 0,00E-01 0.00E-01 4,03E-03 9,05,E-04
- 10. todine-131 Ci 0,00E-Q1 3,07E-06 8,06E-04 2.00E-04 Cesium-134 Ci 3.07E-05 1,36E-04 3,64E-04 9,19E-04 11.
- 12. Cosium-13 7 Ci 8.29E-05 3.00E-04 4,38E-04 1.48E-03 Cerium-141 Ci 0,00E-Q1 2.11E-06 1,66E-04 9,09E-05 13.
Ci 0.00E-01 lx57E-03 1,37E-04
- 14. Corium-144._ Q 00E-01 Others.(Specify)
- 16. Niobium-95 1 248-03
-1
, EFELUENT AND WASTE DISPOSAL SEMIAWWUAL REPORT j 1r,td HALF 1D,Q LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE ,
(CONT 1WUED) {
i Continuous Mode Batch Mode !
Welide Unit gyotter Quarter Quer19.r guterte.t i 3rd 4th _3 rd _ 4 t h __ _
- 19. Barium-140 Ci 0.00E-01 0.00E-01 0.00E-01 1.91E-05
- 20. lodit.e-133 CL 0.00E-01 0.00E-01 8.54E-06 3.86E-05
- 21. Zirconium-95 Ci 0.00E-01 0.00E-01 5.10E-04 1.31E-04
- 22. Technetium-99m Ci 0.00E-01 0.00E-01 4.762-05 0.00E-01 Ci 0.00E-01 0.00E-01 1.18E-04 1.12E-05
- 23. -Ruthenium-103-
- 24. Tellurium 132 CL 0.00E-01 0.00E-01 3.34E-05 0.00E-01
- 25. Antimony-124 Ci 0.00E-01 0.00E-01 9.0?E-05 8.66E-E
- 26. Manganese-56 CL 9,3,p0E-01 0.00E-01 0.00E-01 7.67E-06 i
- 27. Lanthanum-140 -Cl 0.00E-01 0.00E-01 4.12E-05 5.56E-05
- 28. Cesium-136 Ci Q 00E-01 0.00E-01 5.87E-05 0.00E-01
- 29. Rubidium-86 Ci 0.00E-01 0.00E-01 3.13E-05 6.04E-05 30.. Tellurium-129m Ci 0.00E-01 0.00E-01 0.00E-01 2.77F-04 t
- 31. Yttrium-91m 01 0.00E-01 '0.00E-01 7.43E-06 ,4 39E-05
'33.
Yttrium-93 Ci 0.00E-01. 0.00E-01 0.00E-01 H., 7 0 E 34 lodine-135 Ci 9 00E-0,,1, '0.00E-01 1.49E-05 Q200E-01
- 35. Strontium-91 Cl 0.00E-01 0.00E-01 ja76E-06 ) 32E-05
- 36. Yttrium-91 Ci 0,00E-01 0.00E-01 1.59E-03 1.33E-03 Total for Period Ci 1.14E-04 4.41E-04' 2.62E-01 3.8BM-01
-B-
_ ., . - ~ _ . ~ . . . . . _ _ _... . . _ _ . - - . - . _ . . , _ . . . - . _ . . . . - _ _ - . - . , _ _- __ . _ - . _ _ , . _ . .
1 1
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT End RALF 1990 LIQUID EFFLUENTS - TOTAL PLANT DISCHARCE (CONTINUED)
G. Isotope Summary (NOTE: Refer to Table A for values reported as 0.00E-01)
Required by ODCH/Others Dissolved and Entrained Noble Cases Continuous Mode gaith. Mode Nuclide Unit Quarter Quarter Quncter Quarter 3rd 4th 3rd , 4th
- 1. Krypton-87 Ci 0.00E-01 0.00E-01 1.09E-05 lx16E-05
- 3. Xenon-133 Ci 0.00E-01 1.03E-0$ 1.00Et90 8.95E-02
- 4. Xenon-133m Ci 0.00E-01 0.00E-01 1.47E-02 1st4E-04
- 6. Kenon-138 Ci 0_qqp,,_ql 0,00E-01 0.00E-01 0.00E-01 Others (Specify)
- 1. Krypton-85m Ci 0.00E-01 g_00E-01 1.30E-04 1.14E-05
- 8. Argon-41 Ci 0.00E-01 0,00E-01 2.23E-05 0.00E-01
- 9. Xenon-131m Ci 0.00E-01 0.00E-01 1.07E-02 2232E-03
- 10. Xenon-135tn ci 0.00E-01 0.00E-01 0.00E-01 2296E-05 Total for Period Ci 0.00E-01 1.03E-05 1,05E+00 9.52E-02
_g_
EFFLUENT AND JASTE DISPOSAL SEMI ANNUAL REPORT ins MALF-ligg TABLE A LIQUID "Tb 7. CAL LLD" EVALUATION (1) l At(2) l Wuclide- ODCM LLD 15 min _}0_ min 1 hr 2 he
- .M nBanese-54 5,0E-0,1 9.12E-09 9.12E-09 9.12E-09 9.12E-09 I Cobalt-58 SiOE-07 R221E-09 [321E-09 8.21E-ov 8,21E-09
. Iron-59 5.0E-07 1.62E-08 1.62E-08 1.62E-08 1.62E-08 Cob 41t 5.0E-07 1.08E-08 120]E-08 1 08E-08 1.08E-08 -
Zinc 5.0E-07 2.14E-0) gu,14 E-08 2.14E-08 2.14E-08 Molybdenum-99 5.0E-07 5.24E-08 5.25E-08 5.28E-08 5.34E-08 .
Costum-134 5.0E-01 12 ELE 9.82E-09 - 9.82E-09, 1282E-09
- _ C3stum-137 5.0E-07 9.31E-09 9.31E-09 9.31E-09 9_131E-09
- Corlum-141 5.0E-07 1.06E-08 12261-91 1.07E-08 1.07E-08 Carium-144 5.0E-06 4.03E-08 42 Q31-08 4.03E-08 4,03E-08
' Iodine-131 1.0E-06 7.28E-09 7,28E-09 7.30E-09 7.32E-09 Krypton-87 1.0E-05 1.62E-08 1.85E-08 2.43E-08 4.20E-08 ,
Krypton-88 120E-05 2.13E-08 2.27E-Q1 2.56E-08 3.27E-08 Xenon-133 1 0E-05 2.03E-08 2.04E-08 2.04E-08 2.05E-08 Xenon-133m 1.0E-05 5.05E-08 5.07E-08 5.102-08 5.17E-08 Xenon-135 1.0E-05 5,60E-09 5.70E-09 5.93E-09 6.40E-09 Xenon-138 1,0E 2.82E-Og 1,87E-08 2.55E-07 4.79E-06 l
, , . - . _ ~ , . , _ . . _ _ . - - _ _ _ . . _ , - ~ . _ . . . _ . , . _ . - _ _ _ . . . _ . ..__ _ ~ _ - _ . . -
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd KALF 111Q TABLE A LIQUID " TYPICAL LLD" EVALUATION (1)
(Continued)
Nuclide ODCH LLD Iy2}fe3J LLD (Others) (s)
Tritium 1.0E-05 1,0E-06 Gross Alpha 1,0E ,_0J. 2.0E-08 Strontium-89 $.0E-08 2.0E-08 Strontium-90 $,0E-0Q 1.0E-08 Iron-55 1. 0 E-06_ 3.0E-07 WOTESI (t) All evaluations are in pCi/ml. All analyses are performed to ensure that ODCH LLD limite are met, and these are typical LLD valuce.
(a) 6t is the time between sample collection and counting time.
(s) All of these analyses are required to meet ODCM LLD limits, and are individually evaluated to ensure compliance.
N
i-ErPLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT 2nd HALF 1112 GASE00S EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)
.3rd. 4th Summation of_All Releases Unli . 0tr. % Error _Qir. % Error A. E2ble Cases
- 1. Total Released Cl- 1.27E&O3 11.1E+01 1.0$E+02 11.1E+01 2._ Average Release Rate of Period uCL/see 1.59E+02 1.32E&O1
- 3. Percent of ODCM Limit % 5.66E-02 4.58E-03 B._ lodines
-1.- Total Iodine-131 CL ' 21E-04
.. 11.3E+01 S.47E-05 11.3E+01
- 2. Average Release Rate for Period uC- " 05- 6.88E-06
- 3. -Percent-of ODCM Limit (1.60E-01 uCi/sec) % 9.50E-03 4.30E-03 C.- Particulates
- 1. Particulates with Cl 1.703-05 11.6E&01 1.15E-05 11.6E+01 half-lives 48 days
- 2. Average Relesse Rate for Period uCL/sec 2.14E-06 1.45E-06
- 3. Percent of ODCM Limit % 1.55E-06 8.61E-07
- 4. Gross Alpha RadLo- CL 0.00E-01 12.1E&O1 0.00E-01 12.1E+01 j activity
.D. Tritium
't . Total Release Cl 1.69E+00 11.5E+01 2.24E+00 11.5E+01
- 2. Average Release Rate for Period uCL/sec 2.13E-01 2.82E-01
- 3. Percent of ODCM-
. Limit % 2.51E-04 3.33E-04 (8.47E+04 uCL/sec) 1 l
1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Znd HALF 1122 CASE 0VS EFFLUENTS-SUKKATION OF ALL RELEASES (GROUND LEVEL RELEASES) ggntinuous Modg gg_e_hyg Unit Quarter 29erter Qyarter Quart.er 3rd. Ath 3rd 4th E. Noble Cases Required by ODCH/Others
- 1. Krypton-87 Ci 0.00E-01 p_.00E-01 4,5AE-03 5.24E-04
- 3. Xenon-133 C1 1,26E+b/ 1,81E-0,1 1,. 0 ? E &O 3 ,9.8AE4Q1
- 5. Xenon-135 Ci 2.ABC-01 6,$8E-02 L.48E+01 7.93E-01
- 7. Krypton-85 Ci 9,00E-01 Q200E-01 5,68E+00 3,75E+0.2
- 8. Argon-Al Ci 0.00E-01 0,00E-01 1.60E+00 4,3?E-01
- 11. Xenon-135m Ci 0,00E-01 0,00E-01 8,11E-02 0,00E-01 Total for Period Ci 122]E&O2 2,74E-01 1,13E+03 1.0AE&O2 F. l_odines
- 1. Jodine-1:,.
- 2. Jodine-;Lg gi 1,46E-05 gug0E-01
- 3. Todine-135 gi 0,00E-01 0,00E-01 Total for Period Cl 1.35E-04 5.47E-05 NOTE: Refer to Table U for values reported as 0.00E-01.
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ,
2nd HALF 1990 '
CASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)
C. Particulates Required by ODCM/Others Nuclide Unit continuous Mode ouerter Qu3y_t.e_,n 3rd Ath
- 1. Strontium-89 Ci 0.005-01 0.00E-01 i
- 2. Strontium-90 Ci 0.00t-01 0.00t-01
- 3. Iron-59 CL 0.00E-01 0.00t-01
-4 Cobalt-60-- Ci 0.00E-01 0,00t-0,},
- 5. Zine-65 Ci 0.00t-01 0.00E-01 6.- Manganese-54 Ci 0.00E-01 0.00t-01
- 7. Cobalt-58 C1 * ,192-05 6.575-06
- 8. Molybdenum-99 Ci v.00E-01 0.00t-01 9.- Ceslum-134L Ci 0.00r 01 0.00E-01
- 10. - Cesium-137 Cl 0.00t-01 0.00E-01
- 11. Cerium-141 CL 0.00t 0 2 00E-01
- 12. Carlum-144 - Ci 0.00E-01 0.005-01 Others (Specify)
- 13. Chromius-St- CL 5.043-06 4.93E-06 14 Cobalt-57 Ci 0.005-01 0.00t-01 Total'for Period CA -1.69t-05 1.15t-05 NOTtt Refar to Thbie B for values reported.as 0.00E-01.
T
4 EFFLUENT AND WASTE DISPOSAL SEMIANWUAL REPORT IA( HALF li1Q TABLE B GASEOUS " TYPICAL" LLD EVALUATION (1)
Noble Oas At(s)
- Eyclide ODCH LLD 15 min 30 min 1 hr 2 hr - 2,hrt ,
Krypton-87 1.0E-04 2.91E-07 3.34E-07 4.398-07 7,56E-07 Krypton-88 1.0E-04 3.59E-07 3.82E-07 4.31E-07 5.51E-07 ,
K non-133 1.0E-04 1.97E-07 }.98E-07 1.98E-07 1.99E-07 1snon-133m 1.0E-04 8.75E-07 8.78E-07 8.84E-07 8.95E-07 l
K:non-135 1.0E-04 9.76E-08 9.95E-08 1.03E-07 1.12E-07 K:non-138 1.0E 4.93E-07 1.03E-06 4.46E-06 8.38E-05 Particulate Sample Manganese-54 1.0E-10 2268E-14 3.88E-1), 3.88E-14 3,88E-14 3.88E-li 1,0E-10 3.49E-14 3.49E-14 3.49E-14 3.50E-14 221,0E-14 Cabalt-58 1.0E-10 1.25E-14 7.25E-14 7.25E-14 !_.26E-14 1.26E-14 1ron-59 1.0E-10 4.95E-14 4.95E-14 4 . 95 E-_Li 4.95E-14 4.95E-14 Cabalt-60 1.0E-10 9.54E-14 0.54E-14 9.54E-14 9.54E;11 9254E-14 Zine 2.51E-13 2.53E-13 2.56E-13 Molybdenum 1.0E-10 2.49E:11 2.49E-13 7 1.0E-10 4 4.15E-14 4.15E-li 1 15E-14 4.15E-14 C:s ium-134 _.15E-14 1.0E-10 3.85E-14 3.85E-14 3.85E-li 3.85E-14 3.85E-14 Ccsium-137 l '. 0E-10 3.70E-14 3_. 7 0E-14 2 70E-li 3.70E-14 3.71E-14 Cerium-141 1.0E-10 1.32E-13 1.32E-13 1,32E-13 1.32E-13 1.32E-13 Cerium-144.
3.09E-14 3.11E-14 3,12E-14 lodine-131 1 0E-10 3.09E-14 3.09E-14 Strontium-8h3) 1.0E-11 l
Strontium-90-(3) 1.0E-11
' Gross Alpha-(3) 'lu oE-11 g
-_...a,,,--,,--,,.~..,-.n. - . , , . , - .,, ~ , - . . -, , - - , , , . . . . . . , .
l EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT I
ids HALF 1,990 TABLE B <
I GASEQUS " TYPICAL" LLD EVALUATION (1)
(continued) I l
at(8) l
)
Charcoal 3 he fampls_. ,_,,__oDcM LLD ,_15 mi.tt. 30 min- I he ,_2 hr l 4.34E-14 4,36E-14 Iodine-131 1,0E-11 4.31E-14 4_32E-14 4.32E-11 OTHERE Tritium (3) 1.0E-06 NOTES 1 (1) All evaluations are in uCi/cc. All analyses are performed to ensure that ODCM LLD limits are met, and these are typical LLD values. Alpha emitters are counted for e set time of 20 minutco.
(2) at for noble gases is the time from sampilns to analysis. 6t for charcoal and particulate samples is the midpoint of sampling to filter removal from sampling apparatus to analysis, assuming an average flow of 2 CFM for a 24-hour sampling period.
(3) These isotopes are individually evaluated to ensure compliance with ODCM LLD limits. For tritium, a typical LLD is 1.0E-11 uCl/cc. For strontium and gross alpha, a typical LLD is 1.0E-15 uCi/ce.
ErrLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 1990 SOLID WASTE (RADICACTIVE SHIPMENTS)
A. Solid Waste Shipped-of fsite for Burial or Disposal (not Irradiated Fuel) 6 Month Est. Tot.
- 1. Type of Weste Unit Period Error %
- a. Spent resins, filter niud5es, m3 3.01E+1 11.00E-1 evaporator bottoms, etc. Ci 6.26E+2 tl.50E+1
- b. Dry Active Waste, Compressible Waste m3 1.37E+2 11.00E-1 Contaminated Equipment, etc. Ci 2.72E+2 tl.50E+1 !
-c. Irradiated Components, m3 None N/A Control Rods, etc. Ci None N/A
- d. Other (describa) m3 None N/A Composite linwes (containing wet rags, Ci None N/A resin, mechanical filters and me,a1 oxides in boric-acid concentrates) and oil liners
- 2. Estimate of Major Nuclide componi, tion (by tYDe of W89tel
- a. Spent resin, fliter slud6es, evaporator bottoms, etc.
(nuclides determined by measurement)
Curieg Percent
- 1. Manganese-54 3.14E+1 5.01E&O
- 2. Iron-55 1.13E+2 1.81E&1 3.- Cobalt-58 2.34E+2 3.74E+1
- 4. Cobalt-60 1.03E&2 1.64E&1
- 5. Nickel-63 3.55E+1 5.67E+0
- 6. Cesium-134 4.88E+1 7.79E+0
- 7. Cesium-137 5.79E+1 9.26E&O b.- Dry active waste, compressible waste, contaminated equipment etc.
(nuclides determined by estimate)
- 1. Chromium-51 2.34E+0 8.64E&O
- 2. Iron-55 1.14E+1 4.21E+1 4
- 3. Cobalt-58 7.11E+0 2.62Ett
- 4. Cobalt-60 3.51E+0 1.30E&1
- 5. - Nickel-63 1.58E+0 5.83E&O
- 6. Niobium-95 6.03E-1 2.23E+0
- c. Irradiated Components N/A N/A 4
- d. 'Other (describe) N/A N/A 0419a
I EFFLUENT AND WASTE DISPOSAL SEMIANKUAL REPORT 2"0 RALF 1990 I l
SOLID WASTE (RADICACTIVE SHIPMENTS) .
f
- 3. Solid Waste Disposition '
Nupber of_ Shipments Type Ouantity Mode of Transportation Destination a) -Spent resin, filter sludges, evaporator bottoms, etc.
4 A-LSA Motor Freight Be rnwell, SC 2 B-LSA Motor Freight Barnwell, SC a Number of Shipments Type Ouantity Mode of Transportation Destination I
b) Dry active waste, compressible waste, contaminated equipment, etc.
153 A-LSA Motor Freight Darnwell, SC Mumber of Shipnents Type Ouanti(y -Mode of Transportation _
Destination c) Irradiated components, control rods, etc.
None 2 .
Number of Shipments Type Ouantity Mode of Transportation Dentination i d) Composite liners (containing wet rego, resin, mechanical filters and oxides on boric acid) and oil liners None i
4 Irradiated Ibel Shipments (Disposition)
, Number of Sh,ipments Type Ouantity Hodo of Transportation Destination None N/A N/A N/A
- 5. polidification of Waste Was solidification performedt .No If yes, so!';dification median _ _ N/A
- 6. Were any changes made to the process control program? Yes K No*
- 7. Were any major changes made to the radioactive waste systems (liquid, gaseous or solid)? Yes I Wo.
- NOTE: .The content-of the process Control-program has not changed, but the procedure portion has been removed _from Technical Specifications and placed in its own stand alone document.
0419a
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL rep 0RT
[g1 HALF 1990 ATTACHMENT 1 INOPERABLE INSTRUMENTATION r
Pursuant to ODCM Section 1.3.1, the following information is provided concerning radioactive ef fluent moniAoring instrumentation which was inoperable for greater than 30 consecutive days during the period July 1, 1990 through December 31, 1990.
Flow indicator 1-FI-30-242, which measures air flow rate through Unit 1 Shield Building Exhaust, was declared inoperable on October 31, 1987, for exhaust flow rates of less than 8000 cubic feet per minute and remains inoperable at this time. 2-F1-30-242, which noasures air flow rate through Unit 2 Shield Building Exhaust, was declared inoperable for exhaust flow rates of less than 8000 cubic feet per minute on November 25, 1987, and ,
remains inoperable. It was determined that these two instruments cannot accurately measure exhaust flow rates that are less than 8000 CFM; they are considered operable for flows above 8000 CFM. This instrumentation on both shield building exhausts was replaced and the new instrumentation was put in service on 1/31/91.
The Waste Gas analyzer oxygen channel (0-02 AN-43-5000) was declared inoperable on March 22, 1990. The oxygen channel had become erratic in its readings and out of tolerance when compared to grab samples. Initial investigation revealed that the instrument is sensitive (cannot compensate) to changes such as system pressure. Condition adverse to Quality Report, SQp 900110, was initiated on April 5, 1990. Long term corrective actions include designing a suitable replacement for the obsolete equipment. Interim corrective actions include obtaining original vendor (Servonex) services to assist in stablizing the analyzers oxygen channel. This will enable Sequoyah to continue operation to meet technical specifications 3.11.2.5. Current grab samplings will continue until this instrument is made operable or ,
replaced. Troubleshooting investigations are in progress to identify and correct probless associated with instrument stabilization.
! 19
d ENCLOSL'RE 2 TENNESSEE VALLEY AUTHORITY SEQVOYAll NUCLEAR PLANT RADIOLOGICAL IMPACT ASSESSMENT REPORT JANUARY THROUGH DECEMBER 1990 Prepared by: ht d (l;>n& A/Mb/
Reviewed by: d -
se I//thi I p) "Q) 4 6/ lA l./:.4n, -- 2/r>/.7f
(,/( '
Approved by: .
2804e
SQW Rad Impact Jan-Dec 1990 Page 1 of 39 Radiological Impact Assessment Sequoyah Nuclear plant January - December 1990 INTRODUCTIOW
.putential maximum doses to individuals and the population around Sequoyah are calculated for each quarter as required in offsite Dose Calculation Manual (00CM) Section 5.2. Measured plant esleases for the esporting period are used to estimate these doses. Dispersion ,f radioactive effluents in the environment is estimated in-accordance with th* guidance provided by .
Regulatory Culdes 1.109. 1.111 and 1.113 using meteorological data and ,
riverflow data measured during the period. Using dose calculation methodologies which are described in detail in the Sequoyah ODCM, the doses are calculated and used to determine compliance with the dose limits contained in Sequoyah's ODCH. In this report._the doses resulting from releases are described and compared to quarterly and annual limits established for Sequoyah.
SUMMARY
OF L1001D AND CASEOUS EFFLUENT RELEASES - 1990 Although nuclear plants are designed to contain the radioactive material created by the fission process, small amounts of this material escape from the fuel rods e Also. very small amounts of the structures and components of the ';
systems-become activated through the bombardment of neutrons and are worn away. This radioactive material can be transported throughout plant systems and released to the environannt.
Effluent Monitorint.
Plant paths through Which radioactivity is released are monitored. These monitors record the radiation levels for each release.- Monitors which are used for liquid releases will automatically alarm and stop any release which is above regulatory limits. Gaseous release monitors also provide isolation i and alarming mechanisms to allow for the termination'of any relear,a_above limits.
Airborne Releases The noble gas fission products for the most part do not mix with water:and.are given of f -in a gaseous form. A very small amount of particulate radioactivity is given off along with these noble gases. These releases are processed so that the radioactive material is filtered and/oe decayed prior to reicase- '
-through the plant vents. Sampling and monitoring methods are used to-determine'the' amount of. radioactive _ material. released. If'these methods indicate that radioactivity in airborne effluents above preset limits, then releases are terminated.
7 l~ -2857e . . _ . . . .. . . .. .. . . . -
SQN Rad Impact Jan-Dec 1990 page 2 of 39 klauld Releases Some small amounts of radioactive material migrate into the primary coolant water. The primary coolar.t water is routed through a purification system to remove most of these particles; however, not all are removed. Some of the radioactive liquids may leak from pipes or valves in the system. These liquids are collected in floor and equipment drains and sumps. The collected 11gulds are then processed through a clean-up system, composed of storage tanks, recycling systems, and dominerali:ers, to remove contaminants. The purified water is then monitored to determine the amount of radioactive material remaining in the water prior to its release. Steps are taken to ensure that the amount of radioactivity released to the environment is as low as reasonably achievable (ALARA). If the levels of radioactivity are above preset limits, the releases are circulated through the clean-up system again for additional processing. All radioactivity released from the plant into the Tennessee River is quantified.
DOSE L1HIIg The U.S. Nuclear Regulator Commission (HRC) requires nuclear power plants to be designed, built, and operated in such a way that the levels of radioactive material released into unrestricted areas is as low as reasonably achievable fALARA). To ensure that this is done, the plant's operating license includes requirements for a program to be in the ODCM which governs the release of radioactivity. The ODCH specifies limits for the release of radioactive effluents, as well as limits for doses to the general public from the release of these effluents. These limits are set well below the NRC 10 CFR 20 limits which govern the concentrations of radioactivity and exposures permissible in unrestricted areas. This nasures that radioactive effluent releases are ALARA.
The ODCM limits for doses at or beyond the site boundary f rom airborno nobic gases releases are:
Less than or equal to 5 mrad per quarter and 10 mrad per year for gance radiation.
- and -
Less than or equal to 10 mrad per quarter and 20 mrad per year for beta radiation.
i
SQW Red Impact Jan-Dec 1990 page 3 of 39 The ODCM ilmit for the dose to a member of the general public at or beyond the site boundary f rom todines and particulates released in airb ene ef fluents ici tens than or equal to 7.5 meem per quarter and 15 mrem per year to any organ.
The Ot<M limit for doses to a member of the general public from radioactive material in liquid ef fluents released to unrestricted areas, ist Less than or equal to 1.5 mrem per quarter and 3 mrem per year to the total body.
- and -
Less than or equal to 5 prem per quarter and 10 mrem per year 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 Less than or equal to 25 mrem per year to the total body, Less than or equal to 75 mrem per year to the thyroid.
- and -
Less than or equal to 25 mrem per year to any other organ.
DOSE CALCULATIONS Estimated doses to the public are determlned using computer models (the Gaseous Effluent Licensing Code, GM.C, and the Quarterly Water Dase Assessment Code, QWATA) . These models are based on guidance provided by tho JRC (in Regulatory Guides 1.109, 1.111 and 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 pay-receive a dose. The doses calculated are a representation of the dose to a " maximum exposed individual." Some of the factors used in these calculations.(such as ingestion rates) are maximum values. Many of these factors are obtained from NUREG/CR-1004. The values chosen will tend to overestimate the dose to this " maximum" person. In reality, the expected dose to actual individuals-is: lower. -The calculation methods and results of the-calculations are presented in_the following sections.
1 SQN Rad Impact Jan-Dec 1990 page 4 of 39 DOSES FROM AIRBORNE O RffJ,tJENTS For airborne effluents, the pub 1!c can be exposed to radiation from several sources:
direct radiation from the radioactivity in the air, direct radiation from radioactivity deposited on the ground, inhalation of airborne radioactivity, ingestion of vegetation which contains radioactivity deposited from the atmosphere, and ingestion of milk and beef which contains radioactivity dtposited from the atmosphere onto vegetation which is then eaten by milk and beef animals.
The concentrations of radioactivity in the air and the soil are estimated by the computer model GELC which uses the actual meteorological conditions to determine the distribution of the effluents in the atmosphere. Assin, as many of the parameters as poss:ble are based on actual site specific data. The model that is used to estimate dose, as well as the parameters input to the sedel, is described in detail in Section 1.1 of the Sequoyah Nuclear plant Offsite Dose Calculation Manual.
M rborne Rejease points and MeteoroloRical Data Mateorological data at Sequoyah are mousured continuously. Measurements co11ec6ed include the wind speed, wind direction, and the temperature at heights of 10, 46 and 91 meters above the ground. Average quarterly joint frequency distributions (JFDs) are calculated for each release pcint uslug the appropriato levels of meteorological data. A joint frequency distribution gives the percentage of the tiam 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. For calculational purposes, calms are distributed into the lowest windspeed range (0-0.5 mph) according to the directional probabilities
)
in the 0.6-1.4 mph range. Stability classes are determined from the vertical temperature gradient between two measurement levels.
. - . - _ . . - . - - - . - - - _ . - . - - - . - . . . . _ . - . . . - . - . ~ - . - _ _ - . .
I SQW Rad Impact Jan-Dec 1990 Page 5 of 39 i
All releases from Sequoyah are considered ground-level releases to determine ,
the dispersion of the airborne effluents. The ground-level JFD is derived I from windspeeds and directions measured 10 meters above ground and from the l vertical temperature gradient between 10 and 46 mett,rs.
The JFDs for each quarter of 1990 are listed in Tables 1, 2, 3 and 4.
External Exposure those - Airborne Ef fluents i
Dose estimates for maximum external air exposures (gamma-air and beta-air l doses) are made for points at and beyond the site boundary. These doses are l calculated based on the reported releases for all noble gas nuclides. The I reported. dose is chosen for the offsite location with the highest calculated I wposure during the quarter. The doses calculated for Sequoyah Nuclear plant l
.or each quarter are shown below.
Individual Doses from Airborne Effluents External Air Exposures (mrad)
Dose _ Location with Hithest Offsite Exposure First Ouarter Y Air dose- 2.6E-01 mead =N at 950 meters 8 Air dose 6.9E-01 mead- N at 950 meters Second Quarter Y Air dose $.6E-02 mead: N at 950 meters 8 Air dose 1.5E 01 mrad N at 950 metere Third Quarter, Y Air dose 9.9E-02 mead- SSW at 1840 meters 8 Air dose- -2.7E-01 , mrad SSW at 1840 meters Fourth Ouarter .
l Y Air dose 8.3E-03 mead NNW at 730 meters
- p. 8 Air dose 2.4E-02 mead WNW at 730 meters t.
l l
l 3+ =
SQN Rad Impact Jan-Dec 1990 Page 6 of 39 Submersion Dose - Airborne Ef fluents 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. These doses are calculated based on the reported releases for noble gas nuclides.
The highest of these exposures is chosen ant. is assumed to be the maximum individual dose. The submersion doses calculated for S quoyah Nuclear Plant for each quarter are shown below.
Individual Doses f rom Airborne Ef fluents Submersion Exposures (mrem)
Dose Location Maximum Nearest Resident First Ouarter Total Body 1.7E-01 meem SSW at 2019 meters Skin 4.1E-01 meem SSW at 2019 meters Second Ouarter Total Body 4.0E-02 mrem SSW at 2019 meters Skin 9.4E-02 mrem SSW at 2019 metets Third Ouarter Total Body 7.AE-02 mrem SSW at 2019 meters Skin 1.7E-01 mrem SSW at 2019 meters Fourth Ouarter Total Body 5.9E-03 mrom SSW at 2019 meters Skin 1.5E-02 meem SSW at 2019 mt srs
[
l l
l l
1 l
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SQN Rad Impact Jan-Dec 1990 page 7 of 39 Orr.an Dqge - Airborne Ef fluents Internal doses to organs due to releases of airborne ef fluents are estimated for the inhalation, ground contamination, and ingestion pathways. The ingestion pathway is further divided into four possible contributing pathway;:
ingestion of cow / goat milk, ingestion of beef, and ingestion of vegetables.
Doses from applicable pathways are calculated t'or ecch real receptor location defined in Table 5. Doses are calculated based on the reported iodine and particulate releases. To determine the maximum organ dose, the dose contribution from the three pathways are summed for each receptor. For the ingestion doso, however, only those pathways that exist for each receptor are considered in the sum, i.e., milk ingestion doses are included only for farms where milk is consumed without comoercial preparatien and vegetable ingestion is included only for those locations where a garden is identiflod. To conservatively account for beef ingestion, a beef ingestion dose equal to that for the highest site boundery location is added to each identified receptor.
For ground contamination, the done added to the organ dose being calculated is the total body dose calculated for that location, i.e., it is assumed that the dose to an individual organ in equal to the total body dose. The organ doses calculated for Sequoyah Nuclear plant for each quarter ere shown below.
Individual Doses from Airborne Effluento Maximum Organ (mrem)
Orr.an . Ar.e Group _ Dose E,irst Ouarter biver Child 2.2E-03 mrom Individual pathway Contributions:
Vesotable Ingestion 1 1.4E-03 Beef Ingestion 2 1.5E-04 Inhalation 1 6.4E-04 Cround Contamination 1 5.0E-05 Milk Ingestion N/A i Maximum real receptor is located at 2686 meters in the SSW sector.
2C alculated for the site boundary at 950 meters in the N sector.
I SQW Rad Impact ;
Jan-Dec 1990 Page 8 of 39
) Individual Doses from Airborne Effluents (Continued)
Maximum Organ (mrem)
Organ - Ar.e Group _. Dose ;
Second Ouartet Thyroid Child 1.9E-03 meem Individ,a1 Pathway contributions:
Vegess ble Ingestion 3 1.3E-03 Beef Ing ition e 1.7E-04 Inhalationk 4.5E-03 Ground Contamination 3 3.2E-06 4 Milk Ingestion- N/A 3Maximum real receptor is located at 2324 meters in the NE sector.
40alculated for the site boundary at 950 meters in the N sector.
Third Quarter- Thyroid Child 2.4E-03 mesm Individual Pathway Contributions:
Vegetable Ingestion $ 1.1E-03 Beef Ingestion 6 9.6E-05 Inhalation 5 6,3E-04 Ground Contamination 5 8.7E-06 Milk Ingestion N/A SMaximum real receptor is located at 2686 meters in the SSW sector.
6Calculated for the site boundary at 1840 meters in the SSW sector.
child Fourth Ouarter Thyroid 2.4E-03 mrem Individua1LPathway Contributtonst Vegetable _ Ingestion I 1.wE-03 Beef. Ingestion 8 1.3E .
-Inhalation? 6.5E Ground Contamination 7 7.2E-07 Milk Ingestion- N/A 7 Maximum real receptor is located at 991 meters in the NKW sector.
8 Calculated for the site boundary at 730 meters in-th? NNW sector.
k%-- ewwyr w ve *lhw w e 3--wri,w---d-wg *ev v vT-*--NT- yr-e<- 3'r--yW wg-yd---s-t wt=g'g-.irepFww'*ew=*#re'rW--'**-tr '
p9F#$' e d v 4-we*t=c'e--fQ'u' W-'
- .~. . _ . - - . - -. - ~ ._ . ~ . - . . - -- - . - . . . _ . . - - . - . - . . - - - - - . . -
SQW Rad Impact i Jan-Dec 1990 ,
page 9 of 39 5
pose Summery - Airborne Effluents The table below Rives a comparison of the calculated doses to their respectivo quarterly limits. ,
Airborne Effluents Sequoytsh Nuclear plant Quarterly Percent of '
Dose pathway Quarter Dose Limit _,ktmit Gamma air Dose 1 2.6E-01 mrad 5 mead 5.2 %
2 5.6E-02 mrad 1.1 %
3 9.9E-02 mrad 2.0 %
4 8.3E-03 mrad 0.2 t i Beta air Dose 1 6.9E-01 mrad 10 mrad 6,9 %
2 1.5E-01 mead 1.5 %
-3 2.7E-01 mrad 2.7 % ;
4 2.4F.-02 mead 0.2-%
Max Or5an Dose 1 2.2E-03 mrem 7.5 mrom <0.1 %
2 1.9E-03 mrem <0.1 %
3 2.4E-03 mrem <0.1 %
4 2.4E-03 mrem <0.1 %
As is shown by the table, all calculated quarterly doses were well below the allowable limits established in-Sequoyah's ODCH. For a comparison to previous releases and doses. Eraphs are presented as Figures 1 and 2 which show correspondin5 airborne releases and doses for the period 1983 to the present.
The doses _are presented by quarter in Table 6.
P t
-ww-,,y,+r.,---r-e-o,e ~
-, - - ~ ,- w -
- . , .=, - - ..er,>ww,,wy,,w e+--,~, e
3 SQW Rad Impact Jan-Dec 1990 ;
Page 10 of 39 QOSES FROM LIOUID EFFtUENTS i l
Fce liquid ef fluents, the public can be exposed to radiation from three I sources:
the ingestion of cater from the Tennessee River, the ingestion of fish caught in the Tennessee River, and direct exposure from radioactive material deposited in the river 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 maxinum ingestion rates, exposure times, etc. Wherever possible, parameters uc3d 'sn 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 Section
.2.6 of the Sequoyah Nuclear Plant Offsite Dose Calculation Manual.
Liquid Release Points and River Data Radioactivity concentrations in the Tennessee River are calculated assuming that releases of liquid effluents are continuous. All routine liquid releases
.trom Sequoyah are made through diffusers which extend into the Tennessee River.- It is assumed that releasss to the river through these diffusers wLil initially be entrained in one-fif th 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 S. The average river flows past the plant site were as follows:
~
Quarter Average River Flow (ft3/mi 1 77673
'2 24842 3 29827 4 '34960 l-i t
, , , _ . ~ , , _ _ . , . . _ . _
SQW R-d impact Jan-Dec 1990 Page 11 ofR39
' Dose Estimates - Liquid Effluents Doses are calculated for recreation. - consumpt'.on of fish, and drinking water for locations between the plant site ard the mouth of the Tennessee River.
The maximum potential recreation dose is ...lculated for a location immediately downstream from the plant outfall. The maximum individual dose from insostion 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 delnking wa';er is assumed to be that calculated at the nearest downstream public water supply (C. F. Industries).
This could be interpreted as indicat t is that the maximum individual, as assumed for liquid releases from Sequoyah, is an individual who obtains all of his drinking water at C. F. Industetes, consures 21 kg (6.9 kg for a child) per year cf fish caught from the "ennessee River between Sequoyah and
~chickamauga Dam, and spends 500 aours per year standing on the shoreline just below the outfall from Sequoyah. Dose estimates for the maximum individual due to liquid effluents for 1989 are presented below.
Individual Doses from Liquid Effluents
-(mrem) organ Age Group Dose First Quarter' Total Body Child 6.0E-04 mrem Individual pathway Contributions:
Water Ingestion 4.5E-04 Fish Ingestion 3.4E-05 Recreation 1.2E-04 GI Tract Adult 1.2E-03 meem Individual pathway Contributions:
Water Ingestion 3.6L-04
-Fish Ingestion 7.1E-04 Recreation 1.2E-04 l
SQN Rad Impact Jan-Dec 1990 Page 12 of 39 Individual Doses from Liquid Effluents (Continued)
(mrem) e Second Ouarter Total Body Child 2.2E-03 meem Individual Pathway Contributions:
Water Ingestion 1.1E-03 Fish Ingestion 1.0E-04 Recreation 9.6E-04 GI Tract Adult 5.3E-03 neem Individual Pathway Contributions:
Water Ingestion 9.9E-04 Fish Ingestion 3.4E-03
)
Recreation 9.62-04 Third Quarter Total Body Child 1.9E-03 meem Individual Pathway Contributions:
Water Ingestion 7.2E-04 Fish Ingestion 1.0E-04 Recreation 1.1E-03 GI Tract Adult 3.1E-03 meem Individual Pathway Contributions:
Water Ingestion 6.4E-04 Fish ingestion 1.3E-03 Recreation 1.1E-03 Fourth Quarter Total Body Child 1.3E-03 mrom Individual Pathway Contributions:
Water Ingestion 5.6E-04 Fish Ingestion 1.7E-04 Recreation 5.9E-04 Liver Child 1.9E-03 meem Individual Pathway ' Contributions:
Water Ingestion 5.7E-04 Fish Ingestion 7.4E-04 Recreation 5.9E-04 A
SQN Rad Impact Jan-Dec 1990 Page 13 of 39 Dose summary - Liquid Effluents The table below gives a comparison of the calculated doses to their respective quarterly limits.
Liquid Effluents Sequoyah Nuclear plant Percent of Quarterly Quarterly Dose pathway Quarter Dose Limit Limit Liquid-Total Body Dose 1 6.0E-04 meem 1.5 mrom <0.1 %
2 2.2E-03 meem <0.1 %
3 1.9E-03 mrem 0.1 %
4 1.3E-03 meem <0.1 %
Liquid-Max Organ Dose 1 1.2E-03 meem 5 meem <0.1 %
2 5.3E-03 mrem 0.1 %
3 3.1E-03 mrem <0.1 %
4 1.9E-03 mrom <0.1 %
As is shown by the table, all calculated quarterly doses vere well below the allowable limits established in Sequoyah's ODCM. For a comparison to previous releases and doses, graphs are presented as Figure 3 which shows corresponding liquid releases and doses for the period 1983 to the present. Doses are presented by quarter in Table 6.
. SQN Rad Impact Jan-Dec 1990 Page 14 of 39-POPULATION DOSES Population ~ doses for highest exposed organ due to airborne ef fluents are calculated for an estimated 1,060,000 persons living within a 50-mile radius of the plant site. Ingestion population doses are calculated assuming that each individual consumes milk, vegetables, 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 dose estimates for aleborne effluents are presented below.
From liquid releases, the total population along the Tennessee River was e
' estimated to receive population-doses as shown below.
I Sequoyah Nuclear Plant Population Dos _es T 6.a' Rody Dose -Maximum Organ Dose (orga )
First Ouarter Liquid 4.2=,-v2-man-rem 4.5E-02 man-rem (GI Tract) f Airborne 1.0E-00 man-rem 1.0E-01 man-rem (Liver)
Second Quarter Liquid 1.?E-011 man-tem 1.9E-01 man-rem (GI Tract)
Airborne 2.3E-01 man-rem ~2.3E-01 man-rem (Thyroid)
Third Quarter Liquid 1,7E-01 man-rem 1.8E-01 man-rem (GI Tract)
Airborne 3.4E-01 man-rem 3.4E-01 man-rem (thyroid)
Fourth Quarter
-Liquid 7.7E-02 man-rem 7.8E-02 man-rem (Liver)-
Airborne 4.9E-02 man-rem: 5.3E-02 man-rem'(Thyroid)
Population doses can be compared to the natural background dose to the same population of about 159,000 man-rem /yr (Based on 150 mrem / year for natural background.).
___ _ . . ~ . _ _ _ . _ _ _ _ _ _ . _ ._ ._ _ .. _.- __ _ _ _ . . _ . _ _ . .
-[
SQN Rad -Impact Jan-Dec 1990 Page 15 of 39 DIRECT RADIATION External samthe radiation levels were measured by thermoluminescent dosimeters (TLDs) deployed around SQN. During the preoperational period from August 1975 to January 1980, those levels averaged approximately 23 mR/ quarter at onsite stations and 19 mR/ quarter offsite. These data reflect a difference of 2-5 mR/ quarter (average approx 1gately 4 mR/ quarter) between onsite and offsite radiation levels. These higher values measured onsite may be attributable to natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the construction of the plants, or other influences.
Analysis of environmental TLD data for the period of November 1989 to November 1990 showed that gamma radiation levels determined from these TLDs during this reporting period averaged approximately 15.6 mR/ quarter at onsite stations and 13,6 mR/ quarter offsite. This indicates that there was no identifiable increase in dose rate levels attributable to direct radiation _from plant equipment and/or gaseous effluents. Fluctuations in natural background dose rates and'in TLD readings tend to mask any smap increments which may be due to plant operations.
DOSE TO MEMBERS OF THE pVBLIC INSIDE THE SITE BOUNDARY No_ routine activities withln the site boundary by members of the public have been identified which would lead to their radiation exposure.
TOTAL DOSE To determine-compliance with 40 CFR 190, annual total dose contributions to the maximum individual from SQH radioactive effluents and all other nearby uranium fuel cycle sources.are considered.
The annual total body dose to'the maxlmum individual' is conservattvely estimated by sunning the following doses:
the total body air submersion dose for each quarter, l
the critical organ dose -from airborne effluents for each quarter, l-the total body doce from liquid ef fluents for each quarter, the maximum organ dose from liquid effluents for each quarter, and m x sv ,v- w w - - w -~-e ,
n SQN Rad-Impact Jan-Dec 1990 Page 16 of 39 any identifiable increase in direct radiation dose levels as measured by the environmental monitoring program.
This dose is compared to the limit for total body or any organ doso (other than-thyroid) to determine compliance.
The annual thyroid dose to the maximum individual is conservatively estimated by summing the following doses:
the total body air submersion dose for each quarter, the thyroid dose from airborne ef fluents 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 ths environmental monitoring program.
This dose is compared to the limit for thyroid dose to determine compliance.
Total Dose from Fuel Cycle Sequoyah Nuclear Plant First Second Third Fourth Quarter Quarter . Quarter. Quarter Total Body or any' Organ Dose (except thyroid)
Total body air submersion dose 1.7E-01 4.0E-02 7.4E-02 5.9E-03 Critical organ dose- (altborne) 2.2E-03 1.9E-03 2.4E-02 2.4E-03 Total' body dose (liquid) 6.0E-04 2.2E-03 1.9E-03 1.3E-03 Maximum organ dose (liquid) 1.2E-23 5.3E-03 3.1E-03 1.9E-03 Direct radiation = dose 0.0E-00 0.0E-00 0.0E-00 0.0E-00 Total '1.7E-01 4.9E-02 1.0E-01 1.2E-02 Cumulative Total Dose (Total Body or other organ) 3.3E-01 i
... - .- ..-.-.. . . . _ - . . ...~n.. - - . _ - . - . .-. . .- . . .
"'a SQW Rad Impact-.
Jan-Dec-1990 Page 17.of 39 Total-Dose from Fuel Cycle Sequoyah Nuclear Plant First SecorS Third Fourth Quarter Qur,cter Quarter Quarte r -'
Thyroid Dose Total-body air submersion dose 1.7E-01 4.0E-02 7.4E-02 5.9E-03 Thyroid.-dose (altborne) 2.1E-03 1.9E-03 2.4E-03 2.4E-03
. Total body dose (liquid) 6.0E-04 2.2E 1.9E-03 1.3E Thyroid dose (liquid): 6.8E-04 -2.3E-03 1.9E-03 1.2E-03 Direct radiation dose 0.0E-00 0.0E-00 0.0E-00 0.0E-00 Total (Thyroid) 1.7E-01 4.6E-02 8.0E-02 1.1E-02 Cumulative Total Dose (Thyroid) 3.1E !"
i i
12.
i 1
i
.- ' e .- ..- .- . . _ . , , , _ . . . , , , . . . _ . . . , _ . . . . . _ , _ . , _ , . , _ , , . , _ . _ , , _ . . . _ . , _ . _ ,.
SQN Red impact ;r Jan-Dec 1990 Page 18 of 39 CONCLUSION aAs a result of. operation of Sequoyah Nuclear Plant, radioactive effluents were released to the atmosphere and the Tennessee River. The roleased radioactivity resulted in estimated potential doses to tne public whleh are well below the ODCM Limits and Regulatory Guidance. Cumulativo doses for the calendar year are Siven below along with a comparison to the respective annual limits for the doses, i
Cumulative Doses from Effluents Sequoyah Nuclear Plant Percent of Annual Annual pose Pathway Rose Limit Limit Airborne-Gamma air Dose 4.2E-01 mcad 10 mead 4%
Airborne-Beta = air Dose 1.1E-00 mead 20 mead 6%
Airborne-Max Organ Dose 8.9E-03 mrem 15 meem (1 %
Liquid-Total Body Dose. 6.0E-03 mrem 3 meem <1 %
LLquid-Max organ Dose 1.1E-02 mrem 10 meem <1 %
Total Dose-- Total Body 3.3E-01 mrem 25 mrem 1%
or organ other than thyroid Total Dose - Thyroid 3.1E-01 mrem- 75 mrem <1 %
g --
i
-( e SQN Rad Impact Jan-Dec 1990__ !
Page 19 of 39
- ?
TABLE I (page 1 of 4)
.SE000YAH NUCLEAR PLANT METEOROLOGICAL DATA.
FIRST OVARTER 1990 aJOINT FREQUENCY DISTRIBUTION IN PERCENT ,*, .,
FOR GROUND-LEVEL RELEASES
- 70 t #TFi t CtNT A$ t FitiYtWC1Et GP wtR$ itttt it W190 tittCTlet Pet STAT tLITT CLA43 ' A (DttTA T4**4 9 t/100 Ill
st0U9 TAR sutL8At PLAa) j _~ JAR 1. tt n 14A R 34. 90-vt90 vtND 89tIDtitttl 4,,t tit CTie s. ' CALM 0 . 8 + 1. 4 - 1.S=1.4 1.0-9.4 1,$.1.4 9.9 11.4 11,$.48.4 10.9 14.4 sett.l T9TAL
' ~
s 4.8 9.4 4.4 4.449 4.140 4.449 4.4
, Amt 6.4 4.4 4.4 4.4 9.341 til . 4.649 : 4.943 -1.119 9.4- 4.4 0.4 L.148 -!
st 0.0 4. 9 . -0.499 $.849 4,. t 6.049 0.0 4.0
- 7' tus e.4 e,8 6. 6 - ,6.949 6.4 0.191-4.get 4.s 0.4 6.4 .t 0 9.491 0.0 .
4 9.4- 64 4.0 0.0- 4,0 J 4.0 40 4.4 4.4 531 - 4.4 0.4 40 --4.8 88- 4.6 4,0 4.4 4.4 0.0 9.4 44- 4.4 4.9 4.449 4.089 6.4- 4.4 e.t 4.4 S.499
$38 0.4. 0.4- 4.4 0.4 4.6 4.999 tot 5.4 44 4.0- 4.6 -4.494 8 4.0 - 4.049 4.449 4.9 4.4 8.0 4.4 4.999 89w 4.1 ,0.8 4.6 0.191 4.396 4.344 4.0 0.0 4.4 4.439 .I b
u aw = - 4. 0 4*4 t ot - 9.999 4.494 -0.141 9.9 4.0 wtw - 4.4 .7 4.0 4 949 4.449 4.5 0,t39
'w.
tet 0.4 0.0 4,4 9.4 4.499 40 9.4 9 . 4 -- 4.0 0.449 a.4 4.499 4.0 4.8 4.144 www . 4.4 4.4 0.8 4.0 e.4 tw 4.449 4.648 t,8 4.4 1.191
'O.S. s.4 40 8.9 0.0 4.4
- 9 4,4 A rw 4.4 4.0 4*4 4.6 4.4 4.0 4.4 0.4 44 8.4 4.0 4.4 4 444 '
tWtfotAL 4.9~ 4.8 4.444 -0.591 1.138 3.43! 4.341 , 4.4 e.8 -4.831 T6TAL 20W38 0F TAL*0 STA8IL3ff testRTATIast- 1911
." TOTAL BOURS Of $TAatLITT CLASS A .
. 14-T9f A4 towt3 or T Abtl 4884 6titCT20NewtNO 8 tit 0*STA8tLITT CLAS$ A _ 14 -
. TOT &L 46Utt er T ALIO WIRD etalCTIta*W189 O p t tp.tT A31LITT 4684tf AT1958 atli
'T9fAL ROUta (ALM . 4 19 TWT 7ptaCtWTA48 FRIOUTNCit$ OP wtNO 17tt0 31 wt90 OtRfCTtop Pet S E ASILITT CLA49 4 (*L,94 83%TA*T4*aL*1 C/104 Al '
.*: 380VOTAN 50CLIAA PLANT-
% JAN=-4. to e RAA'31. 94- '
I
.wif e - -
ttitCT!09 CALM
./ . e vist Ittt9(MPa l 9.6-l.4 1.$=l.4 ).1-l.4 1. $+ 1. 4 1.9.ll.4 11 $= t l . 4 - ll. lait j left i M.
A -- 4.4 4.4 4.0 't.4 0.999 4,499 4.0 96-est ; 6.4 0.4 8.191 4.6 9.449 -4.144 4.241 4.J46- 4.4
,,, cat'. .4.0 4.6 9.444 4.019 9.4 0.0 0.194 -
4 191 6.0 238' 4.4 4.4 4.191 4.0 9.8 4.8 4.444
' 4.4 4.4 t 4.0 9.4 4.4 9.9 4.4 4.4 tstil 4.648 4.999 0.4 4,0 e.4 Jest . -8.4 _ e ,9 4.0 0. 4 - 6.8 6.0 9.140
. $t l 9.8 4.4 .
4.0 4.5 0.0- - 8,9 9.4 6.0 4.4 9.449 4.4 4.6 6.4 888. -S.4 4.4 4.0 4.4 Sit 4.449 0.0 -4.049 4.0 tot 0.0 4.0 1 4.9 3.1 4.9 9.4 - ' 4.4 0 144 9.948 S 8W - 4.0 4.4 6.4 9.4 4.1 4.148
-SW^
'O.4 0.146 6.197 4.049 6.049 4,4 4.4 9.8 8.4 0.491' 9.6 e.444
- wlW , 8.843 9.441 4.4 4.8. 4.4 0.4 0.4 6.4 4.0 4.4 4.619 4.194 F1 4.6 4.8 . 0.0 0.0 9.4 4.099 l.4 4.4 9.4 4.449 0.899 9.9 www 0.4 9.4 4.0 6.4 9.8 4.4 0.144 tw 0.8-
- f.9 4.4 4,0 4.4 4.0- 0.0 40 9.4 6.4 -4.0-4Ww 't.0 0. 0 - Gee 0.049 4.4 4.4 4.4 4.4 4.4' t.144 4.4 0.0 4.0 4.197
$UST0TAL-. ,4.8 4.4 4.444 - 8.194 1.333 4.341 6.144 - 4.4 4.4 3.192 a
'T4TAL 80V85 GP TALES STASILITT 84888TAft089 1927
- TOTAL 38988 Of $TASILITT CLASS 4 -
1S
.T9fAL 499ES Of T ALIS WING S tatCT!GN=Wl80 97tIDef1AstigTT CLASS 6 11 TOTA & 90498 TOTA & 80498 CALM ef 91Lt0 W159 OttsCTies.wlse 494tD-STASILif f 8082R?AT104I Itts 4
SQN Rad Impact Jan-Dec 1990 Page 20 of 39 TABLE 1 (page 2 of O SE000YAH NUCLEAR PLANT METEOROLOGICAL DATA FIRST OUARTER 1990 y JOINT FREQUENCY DISTRIBUTION IN PERCENT '
FOR GROUND-LEVEL RELEASES JetWT ttCTRTAet Ptt0Vtsetts #P v1N919tte Of vtN9 $t stCTtos Pts
. a 8
GTAttLITT CLAal C (*Leit 98LTA*f4**t.) C/ttt Ml
- 080U01AR SUCLEAR ILANT JA8 L. 94 . AAA 14. 44 s
WtND vlB9 8PitetaPel f
Otttetten _ C A L.'t 9.8-L.4 1181 4 QM 1.5-1.4 1 $=l1<4 '11.1-18.4 10.)-14.4 **I4-) 791AL 3
3 4,4 4.( 0.0 0.049 4.499 4.499 0.0 4.4 4.6 0.141 set 4.4 0.0 4.649 9.$4F 4.344 4.341 0.0 44 0.9 0.941 f** St 4.4 0.0 4.191 4.448 t,0 9.449 e.4 4.0 0.0 0.0 9.398 tat 9.8 9.649 0.049 44 9.0 9.4 4.0 9.8 4.499 t 4.8 4.4 0.9 0.0 0.6 4.4 6.6 4.0 9.8 0.0
. til 4.4 9.4 0.9 0.4 0.4 0.0 8.4 4.0 9.9 0.8 88 4.0 9.9 4.449 9.0 0.9 8.4 0.0 0.4 9.8 9.049 tat 4.9 0.0 4.049 4.9 4.4 a.4 4.0 9.4 0.0 0.440 3 4.0 4.4 0.049 9.ett 4.4 4.89) t,6 4.0 0.4 6.394 13w et s 6.6 0.0 0.191 4.191 4.141 0.0 6.4 9.6 4.841 sw 4.4 4.0- 4.4 9.144 0.141 0.0 0.0 4.0 0.4 0,992 wtw 4.0 0.9 4.049 4.f49 0.999 4.4 0.0 0.0 44 4.191 W 4.4 4.4 4.4 # 6 0.949 0.0 0.0 4.4 4.4 4.449 www 4.0 9.4 9.8 0.0 0.4 4.8 0.0 4.4 4.4 ' 4.4 tw 4.4 0.8 4.3 4.4 4.040 0.191 4.0 0.8 4.0 4.341 B rw 4.8 4.0 9.144 9.4 4.9 4.849 4.4 0.4 9.4 6.191 840teTAL tot. 0.4 9 494 1.134 1.234 1.4e6 4.4 4.8 0.0 4.44f TOTAL Gouta OF 9Ah!9 STAttutT1 04888TAftess 3411 TOTAL SOURS OF STAatLIT1 CLA48 C 83 total ROURS er TAtte w!ut eta 8CTisN=w150 JPst0*STASILITT CLASS C at TOTAL HOURS OF TALIO wtNO 6tt4CTlos*WIRO SP8tDasTAatLITT 00f tRTAT!t#8 1934 .
TOTAL 8048C CALJ4 4 f .
JetFt'PetCtNTAet F1844tMCtti OP w1RO 97tte et v1RD 0138C719M F68 8tAatLITT CLAJS 0 (*l.14 98LTA*ff==4.5 C/100 48 18000Tha EUCLEAR PLANT l JAA 1, 90 - RAS 11. De vt:0 wins'99810tMiti
. Etteitem C A s.Jt 4.4=1.4 1.5-l.4 3.5-4,4 6.5-1.4 1,1-1714 11.$.14.4 40.5-14.4 ute.$ TOTA'
! E C.844 4.499 4.419 4.941 4.393 0.916 4.9 f.4 0.0 3.441 NNt 9.444 4.099 8.Ill L.333 I.419 1.814 4.9 4.4 0.4 6.424 I' at 4.40$ 4.449 4.491 4.344 4 44e. 4.499 0.0 0.0 e.0 1.311
. I ,. . Est, 9.001 3.6 0.191 4.0 d.4
- 4.0 4.4 9.6 9.0 9.199 8 0.003. 4.499 4.144 9.699 4.d ' t.1 9.9 0.0 9.4 9.141 tat 4.003 4.599 4.140 0.0 8.9 4.6 0.0 0.0 9.4 4.344 53 4.stl .0,999 4.844 4.8 8.4 4.4 tot 4.0 tot 4.348 Ist 4.491 0.148 4.848 0.049 6.049 9.999 9.0 4.0 9.4 tetti
, 9 8.004 4.049 0.191 9.499 4.196 9.494 6.4 0.0 8.4 4.814 Ssw 4.00f 4.194 4.144 9.947 1.134 4.844 0.0 4.4 4.9 4.844 tw 4.944 - 0.4 L.343 1.938 4.19e 9.J94 4.0 9.8 4.4 4.303 wtw 4.843 9.441 4.444 6.341 4.140 9.497 4.4 4.0 4.0 n.401 w 4.444 4.849 4.9 9.9 4.341 0.396 6.449 6.4 4.4 4.841 a www 4,891 6.0 4.899 4.394 4.346 4.543 9.4 4.4 0.0 1.344 rw 4.08t s.8 4.140 0.195 0.196 4.349 0.0 e.9 1.0 1.335 e rv 9.448 0.449 4.341 0.196 0.*tl 9.444 9.4 0.0 4.0 1.413 SU570TAL 4.044 1.145 8.142 1.454 1.413 8.345 - 4.949 6.t' O.e 19.431
? -
TetAL 88948 0F TAtt0 8tAttLitt 488 Elvattoss 3431 TOTAL E0499 0F $taa!LITT CLA43 0 let TOTAL tows 3 of TAL10 wtp0 oth8CTles-w120 spitaattAttLITT CLAsl 0 190 ftTAL E0014 0F T alt 9 wtst SI A8CT10n*W180 sette stAa f LtTT 4tativattens atti f8TAL 54Wts CA&Je 1
4 i
SQN Rad. Impact' Jan-Dec 1990.
Page 21 of.39
~
TABLE 1 page_3_of 1)
SEOUOYAH NUCLEAR PLANT METEOROLOGICAL DATA FIRST OU ARTER 1990 --
JOINT FREOUEN':Y DISTRIBUTION IN PERCENT FOR GROUND-LEVEL RELEASES e #0 TNT *Pf Af tNTA4t Fif 0Vtwettf or wtND 99tt0 SY wtat 9tatttles re L
.; * - m .iu ,, m .. . i...it .. m .,4 i., Co.9 ,,
attV91A4 SUCLEAA PLAST .
I~ .
JAN z 1. 94 = MA8 31. 96 J i
W129
. littCTtGW W180 39ttelnF48 t _ p.. CALM -4.8-l.4 -1.9 9.4 1.5-t 4 5,5 1.4 1.l-lf 4 17.9-14.4 18 $a14;4 - P*lt.1 teTAL
'j est '
4.44.
'4.014 0.nl 4.444 _
o .i 1.681 i.i..
4.436 4.... ..n. . ...- 9.4 4..- .m ;
0.691 4.191 9.0 0.0 9. 4 . 8.439 '
at O .e t t '- 4.191- 4.444 - ' 4.4 tst 4.0 4,4 . 4.4 6.4 4.444 2[6
- 333- 4.40% ~4.499 'O.499 4 . 4 -- 4.4 4.0 4.4 4.6 4.4 0.190
-t .
4.84L 4.099. 4.499- 9.4 4.4 4.4 4.4 0.0
- tat-
-O. ten 4,499 . 4.499 ' 6.4 4.0 0.196-4.4 4.4 4.4 4.9 4.0 9.196 ft 4.441 '
O.949 '4.448 " 4.441 4.0 - 4.494 0.4 sat 4.049 0.0 4.0 4 448
.t.944 4.191 ' O.491 4.0 4.448 . 4 499- 4.4 6.4
- ' 3-.
4.443. .t.999 - 0.9 3 4 l % 441- 4.449 1.136 0.4 4.4 4,0
.4.493 tav . 4.414 , 0.444 - 3. Elf- .4.444
' '3.71S 'L.038 4.494 0.1 4.0: 6.4 sw 4.049- 4.398 3.448 '1.463- 4.444- 4.4 lenti usw i 6.003 4.449- 4.39
-4sett 4.0- 6.9 4.413 6.893 0.191 E 4.L 44 ~ 4.4.- . 4.4 6.4 1.843
- U - 4,tel 4.449 .4.399 4.191 4.e49. 9.191 -0.8 www , -4.481 ' 0.4 '4,348 4.4 84' 't, ate 4.494 4.099 6.0 9.449 4.4 4.4_ 4.944
. rw 4.040 0.4 4 444 - 4.494 4.141- 4.4%t 4,4 RWW . 0.001 4 844- - 4.494 4.444 4.4 4.0 4.934 4.398: 4.099 . - 4.4 4.0 0.4 n.343 89tTOTALI 4.449 ' 3.389 13. 4 3 L' ' '43.341 4 120
_.3 443- 4.848 - 4.4 4,4 14.834
- 10TAL 80448 er TAbi9 staatttTT 008ttTAT1454 3417 -I total taunt 9P StAllbt?T CLASS 8 9 144 te?AL touta Of TALie w!WD tit 8CT194=wtND tittD*ff ASILtti CLAJS 4 'iti.
2TetAL 80U84 0F TAL49 v130 StAtt* Tite +wlWO SP589 4TAalLt?T 00$88T&fttag 3436 -
efetAL EcVRJ CALM L-
^% -
Jotaf' PfletWT Att
- Fat 09tsetts or wtNS 9Pt30 St wtNS ttstef ten est
- g
,'* ST A8ttitt (LA8 a P _ (' 1.3 4 08f.fA*tte 4.8 C/tt4 nl
. 88099fA8 89CLEAa PLANT
, 3. ,Jha 1 t o . MAA 31. 94 -
vist- .
. vtps sp*tD{nts) s a 4tittTtts - CALM 6,4=l.4 1. t. ) . 4 - . ) . t.1, 4 -- 1.3-1.4 1;l.11,4 13.3 14.4 14.5 14.4 settet 70TAL=
. . O .' 0 x - 4. 4 0;m- - 4.0 4,0 9.4 .4 sa t i~ 4.0 0.198 3.11S 4.140'
..t-- -4.4 4. m J, et - 4. 0 -
t.4 0.0 4.4 . t .6 - 4.4 1.159 4.494 0.194 : 0.8 4.4 4.4 4.4 8.4 .4.4' 1.411
'R38 4.4- 4.049 0.449 4.4 4.4 - 1.4 t-
- 8. ' 4.4 4.4 0.0 4.899 -
't.4' .0.444 9.449 - 0. 0 - 4.0 9.4 - 4,4
- 888 = 0.9 . 0.049 - 9.449 6,4 L t.6 0.9 t etti -
4.4 9. 9 - 4.4 .t.0 9.4 4.999
$t - 4.4- :- 4.tti .4.140 4.0 4.0 9.4 9.4 835 t 4. 0 - 4.499' 40- 4.4 6 341 t.999 4.4 . 0.9 4.0 4.0 - 4.9 0.0 9.191 3- O.8 9.&40. 4.144' 4.499 0.0 saw - 1. 4 .
- 0,0 -
9.0 8,4 4.4~- 4.941 e.0 1.363.' 4.444 4.499 4.4 0.0 e.e n.935 Sw- 9.9 ; 9.499. 1.443 '4.140 0. 4 _
vaw 9.649 9.6 4.4 1.4 4.0^ 1 473 4,6 4.4- f.444 9.4
-w 4.8 4.049 4.0 4.4 9.4 9.197 4.6 4. t . 4.411 0.4 e.4 4.4 4. 0 - - 4. 4 wmf- 4.0 4.4 4.4 4.499-4.449 0.049 99 4 . 4 __ 4.0 48 0.0- 4.099 rw = 0.4 .8e4 . 4.4~ 4 949 9.4 s tw - 9.4 0,4 4.4 9.0 9.449 3.4 .4.049 6.4 4.049 4.4 4.0 49 4.4 4. 4 - 4.999 smatetAL 4.4 1.419 1.994 1.919 4.144 4,449 4.4 - 0.4 0.0 11.463 TOTAL testa 0F TALI 9 iTAllLITT 03384TAf tens . 3417
. TOTAL acets of staatLt?T CLAJa P .
llt 79tAL 3dvis GF Takt0 v1A0 StARCT!48=V170 af889*$tA81LITT CLA43 P 331 l
T9TAL 50VHS SP TAbl9 wtR$ DIS 8CT!ts.wl80 8P88D-STA8thtTT eastlf AT10W0 1934 .
tef4L 44488 CALM '
-4 i
SQN Rad Impact Jan-Dec 1990 Page 22 of 39 TABLE I page 4 of 4)
SE000YAH NUCLEAR PLANT METEOROLOGICAL DATA FIRST OUARTER 1990 JOINT FRFOUENCY DISTRIBUTION IN PERLt.it TOR GROUND-LEVEL RELEASES
. Setzt tesffwf Aos recovenett8 or vtne setts of wtFo OttacTron res
, 8?Aa1LITT 4LA88 9 (DELTA 1 1 4. 9 t/1,t e it t '
$t990tAA EUCLSAA P LA NT
, JA. a . 9. . .- si, ee vtNo wtWe sitteintal etStetten CAtM 9.4.t,4 1.5 1.4 3.1 5,4 1.3 1,4 9.).g3,q g3,s.gg.t ge.g.ge,e
. 34,5 goggg A 4.4 6.449 f.e49
- 4.8 4.4 4.8 4.4 4.6 sht 4,4 0.444 1.369 4.4 0.999 6 't 4.4 0.0 4.4 0:9 4.4 3.8L1 Rt 4.0 1 4.391' L 639 4. 4.9 9.0 9.4 4.4 tot 3.434 fat 4.0 4.949 9.440 6.4 4.8 4.0 9.4 0 4.4 0.191 9.144 0,4 0.4 4.0 9.Lf1 0,0 0.4 0.9 4.4 0.4 4.Jed 838 4.4 4.144 .449 6.4 4.9 d.4 9.0 9.999 4.699 0.4 4.6 9.191 at 4.0 4.9 4.6 0.4 4.0 0.0 444 0 191 888 4.4 9.494 , 4.491 4.4 4.4 4.4 4.4 4.4 4.9 45344 8 4.4 *.399 0.443 4.449 4.4 0.8 6.4 4.4 0.4 4.941 Stu 6.0 e.049 4.941 4.499 4.4 0.4 9.4 Sw 4.e 0.049 4,140 4.303 9.4 4.4 4.4 L. Lit 4.0 0.4 9.9 4.9 4.J47 vtw 4.4 4.8 9,699 00 0.9 4.0 0.0 9.4 0.4 0.499 w 4.4 0.0 0.0 4.4 4,4 4.4 0.0 9.9 4.4 4.0 www 4.4 4.949 0.0 0.4 4.0 rw 4.5 4,0 4.4 9.4 9.449 t.4 4.0 4.049 0.3 0.0 4.4 e,4 6.4 4.6 9.449 Ntw ' 4. 0 0. 4 - 4.449 0.0 4.4 4.4 4.8 4.4 9.9 4.449 SUBTOTAL 9,6 1.814 1.23d 3.439 0,0 g.g 8,3 g.4 g.g gg,ggg 19f AL SOUS$ OF TAtt0 STAstLITT GOttatAficas 1831 TOTAL 80Va8 or STAstLITT (LA38 4 let =
TOTAL 54U18 0F TALID wts0 SIR 8 CT10N=4tNU $PE 80*$TA81LITT CLAJ S 4 let TOTAb 20VR4 (* TAL10 visa etR8CT198-wist 8PSID*tTA81LITT 0488RVAf tees 3938 etAL 49VB3 CA4JL ~
t 4
SQN Rad Impact Jan-Dec 1990 Page 23 of 39 TABLE 2 (page 1 of 4) 1 SEQUOYAH NUCLEAR PLANT METECROLOGICAL DATA SECOND QUARTER 1990 JOINT FREQUENCY DISTRIBUTION IN PERCENT 9 FOR GROUND-LEVEL RELEASES k
Jotut visetw?Act Ft.*stretts at wtwo 19 tp ST wist 9tatcTfor Pen 8tA42LtTT class A (DELTA Tae-l.9 t/tte al at9901AA EUCLEAR PLAAT APR %. 94 . JVW 34 It WlR0 due sptgegnts; m OtttCtten C Avi 1.4.t,4 t,$.).e 3.$.S.g 1.p.1.4 1.3.g3.4 13.6.gg.4 go,$.34.4 soli j TOTA 4 R t.4 4.0 9.641 0.093 4.493 4.0 6.0 4.0 4.0 6.333
- t 6.0 4.0 0.484 8.434 0.194 0.419 4.641 4.0 4.4 3.349 R8 4.4 9 F 4.333 4.484 0.805 0.993 4.0 9.4 4.0 n.4tl L tot 4.4 '.9 4.233 0.4Lt 4.041 4.6 0.0 0.6 0.0 4. Ele 4 4.4 8.4 4.319 4.444 4.0 4.0 4.4 4.0
- 8.6 4.449 188 :4.4 4.9 0.491 4.441 4.6 0.0 9.4 4.4 8.4 0.lte SS 4.3 4.8 0.144 4,041 4.8 0,4 f4 4.4 8.0 0.144 Sat 4.4 4.6 9.941 ' 4.144 0.893 0,140 4.5 6.4 4.0 8.449 8 4.0 4.0 9.441 6.313 0.136 9.444 4.8 tot 4.0 1.439 ISW 4,0 4.4 4.313 4.8L$ 1.443 0.319 0.641 0.1 9.0 3.955 SW 4.0 0.4 4.333 1.181 1.414 9.419 4.4 0.8 4.9 3.984 Wsw 4.8 9.4 4.641 4.493 0.333 0.333 0.0 0.3 0.4 4.dll 4 0.4 9.4 4.4 4.941 4.319 4.233 4.9 0.0 4.0 9.854 www 4.0 4.0 4.0 8.441 4.319 4.441 4.0 4.0 , 4.6 9 313 rw 4.0 4.0 4.4 4.4 4.4 0.144 0.0 4.4 6.8 0.444 spw 't.4 4.4 9.4 4.6 4.441 4.313 4.4 4.6 4.0 0.449 80tTOTAL O.0 4.4 1,814 1.184 S.34$ 3.331 4.433 4.4 4.8 Lt.111 TOTAL e4WAS OF TAL10 JT&8tL1T1 etEIRTATIONS 38$$
. COTAL NOURS OF STAttLITT CLA88 A 344 TOT AL 80183 0F TAkt0 W180 918tCTies.w!NO SPSVD.0fA81LITT C LA8 3 A 383 l ftTAL 20U18 et TALID WIBO 8888CT10N+wt3D BPttD*STAetL2TT 94583?AfteNS 3449 TOTAL A0488 CA LM 6 k
JotPT PtacTNT Aos Patoutsetts or wtwo sttto at wine otR8ett09 Pet 31A48&ITT CLAJS 4 {.L.St DELTA.fte=L.1 C/140 Al st0Uetka IUCLEAA PLAST APS 1. 90 = JUW at. 90 w1WO dse 87880tMPtt ots CTron .S m e.s.t.$ .s.t., i.s.t.4 5.s.v.e 1.3-il.a ti.s.is.e La S.le.4 . 34.s Te h t, W 4.8 8.8 4.4' O.331 4.233 6 144 0.0 9.4 8.4 4.409 seg 4.4 6.4 4.s93 0.149 9.144 4.047 4.4 0.0 4.4 0.419
. At 0.6 4.8 8.493 4.89) 4.441 6.4 tot 3.4 9.4 8.333 IN4 4.0 0.4 4.449 4.0 9.9 4.9 4.9 4.6 4.8 3.144 8 4.0 4.0 0.0 0.4 0.0 4.4 4.4 4.4 4.4 3.4 858 4.0 4.3 4.4 4.0 4.0 4.4 4.4 4.4 0.3 0.0 88 9.9 8.4 0.1 0.1to 98 4.5 0.0 4.0 4.8 4.164 sat 4.6 0.0 4.9 4.0 9.144 0.0 4.0 9.1 0.8 4.144 8 9.4 4.8 0.4 9.893 9.493 0.14e 4.4 6.4 0.0 4.338 ssw 4.4 9.4 9.333 1.163 . 4.336 9.333 0.0 6.8 0.0 1.314 sw 4.6 4.4 6.441 4.434 4.106 4.441 0.0 f.6 9.4 1..;?
vtw g.4 9.g 9.441 4.941 c.341 4.e41 4,0 e.4 4.3 8.444 e 4.9 4.6 9.4 4.4 0.0 0.841 4.6 6.6 4.4 4.34?
www tot 4.4 0.0 8.8 0.113 4.4 4.0 0.4 , 4.4 8.461 rw 4.8 0.0 3.4 8.3 6.4 4.493 4.9 0.4 6.4 4.393 Rvw 4.9 9.0 4.041 4.0 4.4 9.333 4.0 9.8 6.4 6 . .U a
SU OT OT A L 4.0 4.4 4.494 3.143 1.343 1.e34 4.0 9.3 4,g 3.??4 T1TAL E0433 of TAtle sTA8tttTT oestavhTIOR8 1854 TOTAL $5014 4F iTA88LITT CLAJS 0 130 TOT AL E0418 0F T AL19 Wtst Ot t CTtos.w150 S PEED-8?A8 tLITY C'AJS . 4 134 70tAL 80913 of T alt 3 wt#9 tts tCT198=W1R0 f f TID tTA48L2TT J&IERTA110N$ IL49 ft?AL IOUt3 CA1A 6 t
l SQN Rad Impact Jan-Dec 1990 Page 24 of 39 TABLE 2 page 2 of A)
SEQUOYAH NUCLEAR PLANT METEOROLOGICAL DATA SECOND QUARTER 1990 JOINT FREOUENCY DISTRIBUTION T,N PERCENT FOR GROUND-LEVEL RELEASES JotwT pflet9tatt tattUttCitt er vfRD SPtt0 et vtpe 9tsteitos Fet sTA43L3ft CLAJS C t-L.14 etLTA.T4 mat.) C/tte al seqU0taa SUCLEAA PLANT APA 4, 94 - JUN 30 90 v199 d?W9 SpttSIMPRI
$ 5CTION CALM t.s.t.4 1.1 1.4 1.5 1.4 1,3 1.4 1.3.g3,4 g3,3.gg.4 30,$.14.4 p.34.$ T*TAL
- t.4 4.4 4.041 0.148 4,441 0.09) 4.0 4.4 4.8 6.334 888 0.0 4.4 c.144 9.140 0.0 4,4 0.841 0.0 0.4 4.380 s #8 P.4 4. 4' 4.465 0. 0 , 0.0 4.4 4.5 0.0 0.4 4.445
> tRB 4.9 4.0 0.093 4.0 9.4 6.9 4.0 4,0 9.6 8.491 8 f.4 9.8 4.444 4.4 44 4.4 0.0 4.8 8.4 0.14e C48 't.4 4.4 4.641 0.0 4.0 0,0 4.4 4.0 0.4 9.441 88 0,4 9.4 9.6 0-841 0,4 4.4 4.0 0.6 0.s 6.441 Sit 4.0 9.4 4.6 6.493 0.0 4.4 4.4 4.9 0.4 4.093 4 4.4 8.8 9.4 4.144 4.091 4.041 0.0 tot 4.0 9.336 SSW 3.4 0.0 4. net 4.411 j t.149 0.219 0.0 0.0 6.0 1.834 8W 4.4 4.4 4.393 8.449 9.441 4.641 9.4 4.0 4.0 9.441 v5W 4.9 0.0 0.841 4.493 4.4 0.041 0.0 0.0 6.3 0.444 W 4,4 8.8 8.4 8.393 6.441 0.144 4.0 4.4 4.0 9.319 www 4.0 4.9 9.4 9.4 4.493 0.091 9.4 0.4 0.0 9.144 sw 4.4 4.4 4.4 0.941 4.493 4.041 tot 4.4 4.8 0.144 Erv 't.4 4.4 0.0 4.4 f.188 4.tue 4.0 0.8 8.4 4.313 1 SUlTOTAL .,, 4.0. 0.8 L.454 1.415 4.145 4.911 6.447 6.4 0.4 4.194 ft?AL 80013 0F TAtt0 ATA8tL371 00881 TAT 1058 Ille TOTAL taORS OF ST A8 tt TT CLASS C 10%
1 TOTAL Routs OF TAbit wiss DIRECTttaawlat $9880-tTAttLITT Cf.AJB C 191 TOTAL E0013 of TA' .1 WINF St20CTt0E* WIND SfttD=$tA8tLITY 058tATAfteR$ 3149 TOTAL BOVES CALA 4 Jets? TttCtNTA61 ftt0VINCitS OF VfBO 47tt0 GT WTyp OtttcTttW Pet STA5tLITY CLAJs 0 (*L.54 4tLTA*T4**4.) C/194 Ml SEQUTTAE SOCLEAA PLANT APR 1. 90
- JVN lt. to ;
W'I n s utt0 99880tRft)
OtStCTtot _(ALn 9,0 1.4 L.$ 1,4 1.1-l.4 1.5-1.4 1.5-12.4 j,J,;9 - L t . 4 18.1-14 4 Hli S TOTAL a 4.8 4.4 4.313 4.911 0,331 9.St3 f.8 9.9 1.8 3.133, But 4.0 0.04? 8.044 4.745 0.333 0.454 4.4 0.0 4.3 3.599 s 23 6.4 4.041 6.694 9.104 6.0 6.0 9.4 9.3 4.4 0.931 int , 9.4 4.4 4.484 4.441 4.4 4.9 4.4 0.6 9.3 4.333 8 4.0- 4.9 0.144 4.0 9.441 i 4.8 3.4 4.4 4.4 9.484 tal 9.0 9,6 0.041 4.4 4.4 0.0 9.4 tot 4.4 9.441 88 9;4 tot 0.693 4.8 f.4 0.0 e.4 9.4 8.4 4.493 att 4.9 4.441 6.441 .c.140 9.441 0.041 4.0 0.3 tot 0.324 8 6.4 0.441 4. 6 SI-4.838 4.445 9.443 9.8 4.4 0.3 3.444 sgv 4,9 0,0 g.143 3,14L g.534 4.841 0.9 0.0 9.4 S.444 Sw t.0 9.841 1.834 1.143 / 6.494 4.319 4.0 tot 4.0 3.035 vsw 4.0 9.441 0.333 4 149 9.149 8.093 9.4 0.0 0.8 8.411 w 9.3 3.9 4.393 0.444 4.14e 4.140 0.0 4.0 9.8 9.513 WWW t.4 0.841 4.941 0.093 0.341 0.444 9.4 4.0 0.0 0.373 rw 4.0 0.3 9.9 0.841 9.233 6.993 4.0 9.4 4.8 4.313 NNW 4.4 4,493 0.144 8.313 %.016 0.44$ t9 4.4 0.4 2.141 setTOTAL 6.4 4.44f 5.811 1.031 5.544 1.499 0.9 4.4 4.8 33*339 TOTAL GOURS Of T ALIO STha!LtTT Ott t1T&t!O48 1134 TOTAL 20 Val of STAstLITT CLAs8 0 les f
' l TOTAL AQUS$ OF TAL30 wtst SInscTtts.vtsD IPt4D STA8tL3fT CLAJs e 4to '
ftTAL Novas GF T A< W159 OIR8CT3te= WINO 0F880-0 tat!LITT 000 EAT &TIONS 1149 4
TOT AL 40013 ULJ4
-SQN Rad Impact Jan-Dec 1990--
PaSe 25 of 39 TABLE 2 (page 3 of 4) -
i SEQUOYAH NUCLEAR PLANT METEOROLOGICAL DATA ;
SECOND OUARTER 1990 JOINT TREOUENCY.. DISTRIBUTION IN PERCENT V
FOR GROUND.-LEVEL RELEASES J#fWT Pit *tWTA48 f tttutstits er Wt3D gitte $Y wt99 OfttCT198 709 8?Astt;3ff CLAJ8 8 (*4.84 etLTA* Tee 1.5 C/194 at ,
084 Vet $N#UCLSAR PLANT
' All 1. 30
- JWe St.to.
v130 das sptgatapt) etstetter ' CALM 4.4=1,4 .1 5.l.4 3,$.9.4 1.1 1,4 1,$.11.4 13,9-18.4 14,$.te.4 s=44.9 Etg a' 4.439 - - 4.489 3.094 1.534 0,319 - 4.041 6.6 4.4 0,0 4.413-set - 0.336 3.ett 6.311 0.941 4 . 4 .- se e 4.4 4.4 3.434
- ~ st .'t.831 6.494 - 0.188 c .3 3 8 4.441 4.0 4.0 4.0 9.4 4.0 4.844
= tat 8.591 - 4.233 0.146 ' t.041 4,4 4.0 4.0 4.0 0.8 4.413 4 *4.441 0.0 4.493 4.9 4.0 9.6 4.0 6.4 4.4 0.095 '
.tal' 4.449 4.144 4.144 4.4 4.4 4.e 9.4 4.4 4.6 -4.331
. 6.044 4.333 4.441' 4.0 - e.4 4.4 4.4 4.0 4.9 4.384
'588 - .4.444 0.184 4.441 - 9.441 0.4 4.140 4.0 0.0 9.8 4.413 8 4.419 .4.419 .4.191 *9.138 4.319 4,333. 4.441 6.4 0.0 3,439
. ssw J -9.094 9.441 3.039 1.144 testl 6.tes 6.4 c.4 4.4 4.393 SW 4.686 - 9.443. 3.114 1.443 4 44$ 4.144 4.4 4.0 '4.4 S.133 vsw t,014 =4,319 4,145- 4.491 4,333 t,441 4,4 4.4 4.0 1 #34
-w'.. 4.441 : .0.493 4.313 0.319 9.041 4.641 s.0 4.0 4.4 4.441 www -4.404 4.144 - 4.146 0 733 4.941 tot G.4 4. 0 , 0.0 4.843 rw 4.643 4.0 4.140 9.336 4.441 4.993 4.4 4.4 4.6 4.491 WNw 't.411 -4.333 6.445 0.691 4.319 4.441 4.0 e.4 9.8 -1.444 89tTOTAL 4.311 -4.444 13.114 4.101 3.331 1.434 4.e41 4.4 4.4 34.333
'TCTAL mound 0F WAL39 STA81LITT elatRTAT1088 3154 TOTAL 80919 er STA38LITT CLAJS 4 . .
454
. TOTAL Beets of T ALIO W190 8838CT10N=4139 $ Pt 89*$TAltLITT CLAS S 8' . $l1 79fAL BOUta 0F TALIS wtNe StASCTrosevist 578 89*4TA43&tTT e68 85T AT3089 '3149
. TOTAL 20908 CAIA r 4
[ i
, J0 TNT PSRCBNTA43 F140943C183 ef wtst 4 Pit 0 BT w1WO 9titCTiet F98 STAalLITT CLAJs f i 1.$4 6tLTA*T4= 4.4 C/tte m)
St000TAE SUCLEAA PLANT .
Aft. 1, le b JVW 34. 94 wta0- . 48tNO sittetnps) - -
'DitteT10N .
CALA 4. 4-l . 4 - 1.5-3.4 -I.S.S.4- 1.1 1.4 .-1.5 43.4 11.l-l g 18.l 44 4. >a14.1 E (-
- A 4.449 - 4.344 -1.144 - 4.333 4 . 4 -- 4.4 0.0 0.8 4.4 3.?33
- est - 't.133 4.111 - 4.314 0.093 4.0 4 4 4.0 . e.0 4.0 ,1,333 l- a -~ 88' t.838 9.488 0.491 0.8 p 4.4 44- 4.4 4.4 0.4 1.144
- IRE 9.005 4.146 - 4.941 0.8 e. 4.8 43 4.s -0.0 4.181 4< '
0.444 ; 4.993- 9.941 - 9. 8 - e.t tet 4.0- 0.0 4.8- 4.143' lat 4.401 4.319 4.8 0.8 4.6 0.0 4.4 4.0 i 4.0 4.384--
- - 8 8 - .. title 4.33 3 < 0.893 . 4.8 8.4 4.0 e.4 4.4 9.8 0.334 *
'884' ' t . 411 - - 4.333 - 6 186 ' t.691 c.s 4.4 9.4- 4.0 0.0 . 4.531 t- -4.911
- 4.233 4.413 ca .e. , s.4 6.0 9.4 e.4 4.4 - cf.113
~asw 4.494' 4.14 4 = -1.148 4.441 0,0- 4.4 0.0 e.1 4.8 3.811
-sw _e 034 't.041 4.911 ~ 4. 0 41 ,p 4.4 4. 0 - 0.0 4.4 4.0' 1.494
' vsw - 4.001 0.941 0.333 ' 4.140 - 4.0. 4.441 9.9 9.4 ' O.9 3.413 w- . 4.041 4.5 0 319 0.093 0.0 4.0 4.4 4.0 9.9 9.319 www 0.004- 6.0 0.333 4.e41 4.0 0.0 4.4 tot, . 0.9 4.309 -
rw - -4.046 4.8 6.333 3.144 4.4 e.0 4.0 0.0 9.4 4.438 aru - 't.411 4.333 0.144- 4.841 4.0 9.4 [ 4.4 9.4 ' 4.4 1.478
-. 89tTOT AL 4.313 3.518 11.494 1.814 9.4 4.441 4.4 4.4 4.0 18433 TOTAL.sevas of TALis sTAatt.!TT S$$8STAtt0NS 3134 TOTAL '!O988 4F STA4tLITT CLASS P 349 TOTAL seats of TALJO wtso etasCTIos.wtne state sTAtlttTT class F 346 TOTAL towas or TALze wise 9114cT30s-wise artse sTAatt371 esstaTAT!4as 2149 T@TAL 80Vt3 CAIA 4 I
t.
SQN Rad Impact Jan-Dec 1990 Page 26 of 39 TABLE 2 (page 4 of 4)
SE000YAH NUCLEAR PLANT METEOP.0 LOGICAL DATA SECOND QUARTER 1990 JOINT FREQUENCY DISTRIBUTION IN PERCENT '
FOR GROUND-LEVEL RELEASES Jetzt tractNTAat rateutsetts of wind 8?Itp 6t wine Otattitos rea 8TA83LITT CLASS 4 IDELTA T & 4.6 C/194 al 8tQvotna SUCLtAs Pt.AKT Aft 4. 96
- JUN St. 90 1130 4330 SPtt0lM94)
OttsCTrew CALM 9.6-l.4 1.l.1.4 1.5-9.4 1.S.1,4 1.l-12.4 11.5-10.4 If.l-It.6 1 14.3 Totab t.
3 . 4.081 - tot 9.991 4.0 0.4 9.9 4.6 0.0 6.9 f.410 888 4.468 4.Sk1. 4.138 4.0 9.4 0.4 4.4 4.8 0.0 0 390 et 4.835 9.498 d.32s 4. 4 . 0.4 4.4 0.9 0.4 4.s 4.331
=> CNE 4.0 g.4 4.0 4.0 4.4 4.g 4,0 g.3 4,3 0,4 I 0.005 0.941 4.447 0.0 44 ese 4.4 0.0 0.0 0.494 888 4.841 0.09) 0.04? Gee 0.4 4,0 0.4 9.4 6.4 0.164
$$ t.848 . 9.493 4.4 4.4 8.4 4.4 0.0 0.0 0.4 4.494 888 4.436 4.311 4.447 - f.e 8.6 0.0 4.4 4.0 e.4 4.439 8 4.41s e.all 4.196
- 0.6 6.0 0.4 0.0 4.0 9.4 4.391 esw 4.431 0.0 4,394 4.0 4.4 4.6 9.4 4.4 4.8 4.548 Sw t,049 8.441 4.446 0.4 4.0 9.4 4.4 4.6 4.8 4. aft w8W 4.994 4.4 4.641 0.0 4.0 9.6 4.4 4.0 4.0 0.049 W 9.6 4.0 0.0 4,4 6.4 4,4 4.4 4.9 4.4 4e www t,045 4.4 9.493 4.4 4.0 4.4 4.4 6.4 e.4 3.394 sw 4.0 4,4 8.4 4.4 0.4 4.4 4.0 0.4 0.4 3.3 0.4 g NRW 't 0 0.4, 0.4 9.4 6.4 1 4.0 0.4 4.4 e.4 SV8 TOTAL 4.140 4.f71 6.944 9.4 4.4 0,4 8.4 4.4 9.4 3.421 TOT AL BOUA3 of T AL10 ST A4tLITT 808tST Af t028 lill TOTAL EDURJ OF JTAethtTT CLA88 6 46 TOTAL #0013 of TAL80 W150 SIRCCTlas wind SP880*STA88bitt class 4 69 TeTAL ROURS Of TALIO WINO 0$ ACCT 10s-WIND SFtdD-stastLITT e8staTAf test lidt i TOTAL E0014 CALM 3 ,
.(.
f
, . . . .- -.- - - - - . . . . _ - . - . _.~ . . - . - - - . . _ - - - - -
SQN Rad Impact Jan-Dec 1990-Page 27 of 39
-TABLE-3 (page 1 of.4) i SE0VOYAH NUCLEAR PLANT METEOROLOGICAL DATA THIRD OUARTER 1990 g . JOINT FREQUENCY DISTRIBUTION IN PERCENT FOR GROUND-LEVEL RELEASES ~
70 twt tractwf aat ett00tucits er wine spite Of wts6 4tatettom ros 8tA4fL3TT CLAS$ A (9EktA 4ts*4,9 t/tte R$
st4U41AN sVCL8AA plast 3VL' 1. to .
Stf 34 DO ,
w
'w!NO: WIND $Pt20(MSN!
L
'StatCTt0W _fALM $ dal.4 1.$=1.4 3 l+1.4 9.l*T.4 'T 9+1),4 l1 S=14 4 14<$*14.4 to)4.9 total u- . = 0,4 .6,0: 24.444 0.139 't.319 ,4.448 0.4 set 8,4 4.44 4.318 4.4 4.8 4.811
, 1.348 '1.489 9.439 4.4 4.4 4.4 4,934 s
--at.. - 4.4 4.8 l.433 3.ett 4.443 e.13e e.0 e.e 4.s 4. tat int- 4.4 4.0 4.313 0.851 6.4 4.4 4,8 4,4 4.4 L.433 8 4.4 4.4 6.319 6.279 4.0 4.4. 4,4 4.0 4.J 9.354 tst ' 6.4 4.s 4.333 4.nas 4.444 e.4 4.s 4.s 4.s 4. 4s -
84 -4.4' 4.4- _0.091 4.111 4.4 4.4 't.4 0,4 4.8 6.373
- i i 388 4.0 4.6 4.448 .4.114 4,493 4.444 0.0 6.5 4.0 4.313 3 4.4 - 4. 0 - -0.4 4.854 4.493 0.146 4.e 4.e- 4.4 e.sts e.4
~
1 38W ' 6. 4 - 9,448' L.lEl 1.348 4.139 4.4 4.4 4.0 3.839 sw -0.4 . 0.4 4.493 1.049 4.819 4.648 tot 6.4 4.0 4.414 vsw 4.4 c.4 4.4 4.431 4.443 4.493 4.4 4.0 w 4.0 4.4 0.335
.4.4 - 4,4 0.4 4.493 4.0 4.8 4.4 4.4 4.493 www 8.4 - 4.4 4.4 4.446 4.4 .4.4
- 6. 4 4.4 4.4 4.044 rw 4. 0 - 4.4 0.4 ' 4.044 4.4 0,4 4.4 4.4 4.e.
4.4 4.444
- mew . 4 4.0 -4.846 .4 493 4.413 0.339 4.4 4.0 tit. 0.314 !,
= SUt?4TAL 4,4 L 4.4 3.146, 0.3ts 3.419 4.914 4.0 4,4 4.4 47.4e4 TOTAL seuts GF WAL18 4tA4'LITT t testaVAftes8 ' 1853
. fetal 50U13 Of $TAttL!ti CLASS A 344 TOTAL ROU13 0F TALIB wtES SISECTION.Wist SPS8D*STAa!L3tf CLAJS A 364
" TOTA & 80U18 0F ' VAL 30 w139 St8ttt10#*w130 SPt3Datf AetLit? 08488TAf tout Ill!'
- .,4 TOTAL.ROURS 4l ALM . 4 x3;
.JotwT PtRetaTAet Patoutsetts 0F wtWe 99280 et wtwo ottsCttes P L
-STAettiti tLAas 4 t.L.14 atLTAatteet.1 4/146 nl.
484V0f As avCLSAA plast JUL . 4. 94 - $tt 34. 94 WIND - .
Ott t!T t 0W i CALM-_. 4.4=t;4 'l 1 3.4 .. w!ND 3.1-4.4$ Pit 3(MP4)
_$ 1-9.4 1.5=tt.4 11.5-16.4 -10.1 14 4 sete.1 TOTAL-
. >4.4-. 4.4 6.139 ' 14.134' 4.093 4.844 4.4 0. 3 ' 4.4 4.414 aus. ;4.4- 6.3 4.319 4.lle : 4.993 -4.846 4.0 0.4' 4.4 6.:514 '
- 4. 0 - 0.0 0.651 4.594 ' 4.493 .4.0 4.9 0.4 4.4 4.34L.
e tutt '-.- _4.4 _ 0.4 4.338 4.444 . 4.4 .4.4 4.4 4.4. 4.4 4.313 .
8- . 4.0 -4.4 4.444 4.446- 4.4 4.8 4.4- 4.4 4.4- 4.893 848. 4.4 4.0- - e.135' 4.134 4.4 4.8_ 4.s 4.3 4.s 4.119 st 0.4 4.4= 0.139 0.139 4.0 4.4 '4.4 4.4 4.4 4.119 888 - 4.0 9.4 4.4 0.331. 4.493 4.4 4.4 _ 6. 4 4.9 - 4.315 8 4.4 4.4 - : 4.443 4.333 4.644 - 4.4 4.0 4.4 0,4 - 4,313 saw - . _4.4- 4.0 4.319 ~4.3431 4.311 4.4 4. 0 ' 4.4 4.4 '&.394 8W '. 't.0 04 4.833 4.444 6,444 4.0 4.0 9.4 4.0 0.743
. wsw - 4.4 - 4.4 -0.493 4.493 4. 4 . 4.4 4.0 4.4 3. 4 - 4.184 w: 4. 4 - 4.4 0.444 0.0 4.0 9. 4 ' O.4 4.8 4.0 4.844 www - 4.4 8.4 0.0 0.893 4.4 4.0 ' 4. 4 0.4 4.4 -0.493
-tw . 4.4 4.4 4.0 '6.844 e 448 A.0 4.0 4.4 4,4 4.493 '
srw 4.0 - 4.4 -4.4 4.844 4.139 4.948 4.8 4.4 0.4 4.333 SvetetAL ' 4.4 ' 4.0 / 3.333 3.111 1.433 : 4.439 4.4 e.s 4.s 1.343 TOTAN s00as 07 TAtle staatLITY OestaTAT!sas 3132 TOTAL SOURS Of $fASILItf CLAJS 4- .
- LS5
' TOTAL 80U13 0F TAL!S wtN9 OIRECTION=wtNO 178tD=4TASILITY CLAJS 8 133 TOTAL 80Vt3 OP-VALSO v130 4t18CTIos w180 SPt D-4118tLITT 088tATAf test 1453
- TOTAL BOURS CA&M, e q'.
, _ . . . - - , . . - - , . r., . . - . ._ . . - . - _ . - _ . _ _ . _ _ _ _ __ , _ _ . _ - - _
SQN Rad Impact Jan-Dec 1990-Page 28 of 39 TABLE 3 (page 2 of 4)
SEQUOYAH NUCLEAR PLANT METEOROLOGICAL DATA THIRD OUARTER 1990
.; JOINT FREQUENCY DISTRIBUTION IN PERCENT FOR GROUND-LEVEL RELEASES tots? ptRCtNTA45 'iE0Vt#Ctts ve wtaD $7589 6f vtmo ettletten Pot BTA8tL2TT CLAIS 6 1*l.14 OtLTA.T4e.l.5 t/194 Ne i 8 80t'OT AE WUCL8A8 PLANT JUL 4, te + 8tt 30 te wt3D wt3D SftsatNPut L.S.),4 S,l.1.4 nje l stafetton CALM e 4*L.4 3.l.1.4 1.1 17.* 31 1-L4 4 1 6-14.4 e Lef,A3, s 4.0 0.0 4.493 0.184 4.0 0.6 4.4 4.4 4.0 9.379 set 4.4 4.4 4.186 6.311 4.186 0.0 e.4 4,4 9.0 4.143 54 0.4 0.0 0.489 4.493 4.493 4.0 6.8 4.8 0.0 4.454 438 0.4 4.4 8.139 6.444 0.4 4.8 4.6 0.4 4.9 4.184 8 0.4 0.4 4.093 4.4 4.8 4.0 4.8 4.4 4.8 0.4e3 898 4.0 4.6 4.129 4.4 0.0 0.4 9.4 0.0 4.4 4.439 88 6.9 0.0 4.493 4.093 4.9 0.4 't . e 4.4 4.4 0.184
$$8 f.8 4.4 0.139 4.046 4.0 4.4 4.4 4.4 0.4 C.144 3 4.0 4.4 4.104 4.439 4.0 0.4 8.6 4.4 0.4 4.315 S8W 4.3 4.4 4,4 .
4.404 0.139 0,4 4.4 0.0 4.0 4.143 aw 4.0 9.4 0.134 4.858 0.444 4.4 4.4 4.6 8. 4 - c.141 W8w 4.6 4.4 4,044 8.493 4 6 0.0 9.4 4.8 4.4 0.419 w 4.0 4.4 4,493 6.493 0.648 6.5 4.4 4.4 4.4 4.233 wmW 6.0 0.0 4.9 6.844 4.0 4.0
- 4. 4 4,4 4,4 4.044 Ww 4.4 0.044. 4.444 4.444 0.4 4.a 4.6 4.4 0.3' 4.439 srw 4.0 0.4 6.9 4.4. 4.046 4.441 4.4 4.9 4.4 4.493 SU8 TOTAL 4.6 4.444 1.489 1.414 4 lle 6.448 4.4 4.8 4.4 4.934 TOTAL 50414 0F TAL30 ST A8tLITT Destav&TIONS 2193 TOTAL 50ERS Of Staa tLITT CLAJS C 104 TOTAL E0W84 0F 91LIO wtWS 8t RICT30s WtE0 S f 880= STA8 t LITT CLAJ S C - Ltd ,
TOTAL BuUSS OF WAkt0 wtte OttACT10W-wtND 8PtItadTAAILITY 048taVAT30s3 Illa TOTAL SOUSS CALA. 4 yJ WT Pt9CTNTA$t Ptt4UtWC1tl Of w199 9Ptto 4T wtWS 6titCT!@# F94 _
STA4344TT CLAJI 9 4 L.54 OtLTA-T4* 4.5 C/100 ml 88000fAA svCL8AA PLAaf JUL 1 96
- SEP 14 90 wtS9 wlNO 59810(R$5l OtateT16N C A LM 9,4=l,4 1 5-1.4 3.1 9.4 1 1 1.4 1 5 13,4 13.1 10,4 14 1 14.4 se34.9 TOTAL s 4.6 8.044 L.833 4.111 0.144 4.003 4.s 4.4 4.0 1.119 Wat 3.6 4.L44 1.394 L.304 4.114 e.431 4.4 . 4. 6 8.5 3.333 at 9.4 0.444 8.491 4.328 4.333 0.0 6.0 9.4 4.4 1.34L
$N8- 4.4 0.0 4.139 4.493 4.e44 4.0 4.6 0.3 8.4 1.119 8.944 4.335 0.993 0.0 0.4 6.4 4,445 0 6.4 9.4 0.0 838 4.6 44444 8 488 4.0 0.844 4.0 4.0 0.0 0.4 4.119 38 d.3 4.139 0.211 4.311 4.093 4.0 0.4 4.4 0.0 4.194 tat 4.0 4-493
. 6.445 4.444 4.093 0.044 9.4 0.0 9.4 4.803 8 4. 4 ' O.4 0.194 3.361 0.2?9 0.0 4.0 9.0 4.8 3.314 '
88w 4.4 4,493 1.909 1.184 4.404 v.444 0.4 4.4 0.4 4.433 e sw - 4.6 0.184 1.395 0.919 4.219 4.044 4.6 4.4 4.4 3.499 stw 4.0 4.044 4.aea 8.4 4.6 4.444 4.4 4.3 4.4 4.319 w 4.6 0.4 0.139 4.319 4.091 4.4 6.4 4.8 6.4 8.511 www 4.4 0.444 4.993 4.493 4.044 0.4 4.4 0.4 4.4 4.319 sw 4.4 4,6 0.331 4.9 4.4 4.4 9.0 e.0 0.0 4.233 asw 4.4 4.0 0.211 4.139 e.144 s.044 4.s e.4 4.4
- e.ast SUGTOTAL 1.4 4.816 9.387 1.$14 1.809 9.485 4.s 0.6 0.0 11.491 l
TOTAL 40033 0F fnL30 STA88L3ff 08384 VAT 10mf 3151 TOTAL 80913 0F STA4!LITT CLAJ8 0 454 TOTAL EDURA 0F T ALJO wtNO DIR8CTsos.wTs0 settD=sT Aa!L2TT CLASS 9 414 TOTAL 00U18 0F TAL10 wta0 atS8cTt4Wawls0 SPEID=9f Aa!LITT 068 TAT AT10S$ 3453 TOTAJ. 34413 CALM 0
SQN had Impact Jan-Dec 1990 Page 29 of 39 TABLE 3 (page 3 of 4)
SEQUOYAH NUCLEAR PLANT METEOROLOGICAL DATA THIRD 00ARTER 1990
, JOINT FREQUENCY DISTRIBUTION IN PERCENT FOR' GROUND-LEVEL RELEASES 40tet ettervinot Pt400tuetts of wtwo SPtt0 Of wtwo ofstetten 70s i
, stAttttti Ct.AA8 8 (*4.44 DELTAatte L ! </tte ni st0U0 tau evCLSAA PLANT JUL 4. 99
- Stt 30 to wtan vtwo sptt0(nPS) etttettog etLM 4.5-1.4 1.1-1 4 3.l.1.4 1 l*3.4 1.5-13.4 13.5-14,4 la 9-l4 4 6elt.$ total a 2.044 4.444 4.833 4.843 0.339 4.846 4.4 4.4 4.0 4.494 WNE 8.041 L.143 l 398 e.all s.319 4.s 4.4 4.4 0s 1.549 et 3.414 3.334 4.414 4.139 4.4 4.0 e.0 4,4 0.0 4,135 t#t 7.409 4.313 0.003 0.0 4.4 8.4 4.8 4.8 4,4 4.449 4 f.448 4.333 4.433 4.0 S.8 0.0 4.4 4.0 0.0 6.449 484 4.481 4.493 s.044 8.8 4.0 0.4 4.4 0.0 4.4 4.441 88 0.083 4.146 4.338 4.0 tot 4.8 4.0 4.0 4.0 8.316 sat 4.341 4.319 0.333 4.044 0.0 0.4 4.0 0.0 0.0 0.343 8 6.349 0.454 1.418 0.446 4.493 4.4 9.4 0.4 0.6 1.933 38w 4.834 4.414 3.443 0.311 f.13s 4.844 4.8 4.0 0.4 3.149 sw 4.013 0.333 1.948 4.4sl 4.st) 4.4 6.4 4.0 4.0 3.111 wtw 4 451 4.313 4.L44 4.144 4 . 4' O.4 4,6 4.0 0.4 4.135 w 4.004 4 333 .4.494 4.093 4.all 4.139 4.0 p.4 4.4 4.381 www 4. p t e.144 4.335 0.093 4.044 4.4
- 3. 0 4.4 4.4 4.484 rw 4 .. t ? 4.139 4.lle 4.439 8.444 0.0 4.0 48 4.4 0.a90 nrw 4.811 4.186 4.441 4.311 0.093 9.4 4.4 4.4 4.4 3.394 sUttetAL 0 379 S.stl 3L.383 3.184 4.304 4.333 4.4 4.4 4.4 33.434 tot AL 20Ut3 0F T AL20 at ASIL!tt 44884W Atteus 3153 total EQUte of STAatLITT CLASA 4 .
143 tot AL B0088 0 F W AL10 wtWe GI Attfles-wtat 3 7t tD+3tASILlt? CLA38 8 103 .
- Tota 4 a0U53 0F YA&!D w!pp 9thtettese wtWe $PSID-stietLIt? 04sttVAtt0B3 3183 total 80U1J CA tJL . 8 I
e J0 twt Pitetstaat PttoutyCTtt GP wtNS 17tt0 SF wisD O!stettop FO L stAetLIt? CLAS$ F { 1 $4 GBLTAatte 4.4 C/404 R)
SE1401AN NUCLCAS PLA37 JVL 1. 90
- Ist 30, to wtIO w!30 SPEtatnPat 010Ettt04 , CALM 0.6 l.4 1.1 1.4 1.1 1.4 1.5-1 4 ' S-13 4 13.5-Lt.4 14,$-14.4 sett.1 total s 4.011 0.139 3.J40 0.133 4.0 e.8 e.0 0.0 8.4 3.138 set 0.039 1.344 S.314 0.993 4.3 0.0 4.4 0.0 4.8 4.344 35 4.404 4.691 4.891 0.0 0.0 4.4 4.4 0.9 4.4 1.483' tot 4.004- e.139 4.493 9.4 4.4 444 4.4 4.0 4.4 0.334 8 6.481 0.139 6.844 0.0 4.4 4.4 4.0 9.4 0.0 9.L41 t$t 4.800 0.444 0.0 4.3 0.4 6.4 4.4 0,0 4.3 4.041 38 4.343 0.33S 4.993 9.4 0.4 4.4 4.4 0.4 0.0 4.434 Ist 4.441 4.114 0.444 4.0 4.4 4.0 0.4 4.4 4.0 9.334 8 .4.004 4.313 0.319 0.0 8.8 4.4 4.4 4.4 0.4 4.454 33v 4.844 0.393 6.5tt 4.4 4.8 4.4 0.0 4.4 4.4 4.844 Sw 4.944 4.444 4.ll8 9.4 4.4 0.4 4.8 0.0 4.0 4.604 Wsw 4.403 6.448 6,44$ 0.4 9.8 0.4 0,0 0.0 4,4 4.514 w 0.441 4.448 4.444 4.0 6.0 4.0 4.3 0.0 4.0 4.493 www 4.841 4.4 0.693 0.0 4.0 8.0 4.4. 0.4 0.4 4.093 rw 4.391 0,848 4.444 4.139 4.3 4.8 9.4 e.4 4.0 e.313 4 FFw 9.441 4.3 4.333 4.233 4.4 0.4 0.0 9.e a,4 e.tse S u t t'at AL 4.493 3.333 11.494 0.497 0.0 0.8 0.0 6.0 4.4 18.117 tota 4 54418 Of V ALIO ST A4 tLitt etS#1 TAT!0st till total 30U33 0F ST A$ t L!f t CLAJS P 349
- 0TAL EOU18 0F S ALIO wtNO 9titCttes* WING S f tt0= $TA$ t L3tt C LA3 8 F 349 TOTAL 80f'4 OF SAL 23 wiu0 Otttttles wtNG Sit 40-8tASILift 08888vAtt0N8 11$3 tetAL 30CaJ CAZJ4 3
SQN Rad Impact Jan-Dec 1990 Page 30 of 39 TABLE 3 (page 4 of 4)
SEQUOYAH NUCLEAR PLANT METEOROLOGICAL DATA THIRD OUARTER 1990 JOINT FREQUENCY DISTRIBUTION IN PERCENT FOR GROUND-LEVEL RELEASES JotwT estespTAo? Patovtuetti or wwpp sette er wtyp otalCTt9s P93, 8tA446171'CLAan 4 letLTA 1a 4.0 C/let ni stevetAN svCLIAA PLAmt
.'Y L 4. le - Sif 24. 14 WIND M330 8Ptte(MPup DittCT10N C A L '8 8.4 1 4 l l< 1. 4 1.1=1 4 1 l=1 4 1 1-11 4 13,1.t4.4 ll.latt 4 g3M total s 4.443 4.048 4.4 4.4 4.0 4.4 4.4 4,4 4.4 6.454 Wat 4.053 4.4' 4.444 4.4 4.4 4.4 6.4 4.0 4.4 0.084 as - 4.049 4.418 4.444 0.0 0.8 4.6 4.4 4.4 4.4 4.149 438 4.4 0.0 0.0 4.4 4.4 4.0 P.9 0.0 4.0 40 t 4.4 0.4 6.4 4.4 4.4 4.4 4.0 4.4 4.4 4.4 184 4.4 0.0 8.4 4.4 4.4 0.4 4.4 4.4 4.0 4.4 at 4.044 4.893 4.8 4.0 S.4 4.4 '4.4 4.4 4.4 0,499 sat 4.4 4.6 4.4 4.4 4.4 44 4.4 4.4 4.4 4.0 8 4.409 4.413 4.468 4.4 4 4.4 4.4 4.6 4.4 4.149 faw 4.046 0.0 4.491 4.4 o4 0.6 0.0 4.4 4.4 4.444 AW 4.04) 4.4 4.444 4.4 8.4 4.4 0.0 4,4 4.4 t,gle F4W - 4.40) 4.4 4.448 4.4 4.4 9.4 4.4 0.4 0.0 4.499 4 4.4 4.4 4.0 0.0 4.4 4.0 4.4 4.0 0.4 4.4 4tw 4.4 4.4 0.0 0.6 4.4 4.0 ' 4.4 6,4 4.0 9.4 rw 4.443 6.4 4.444 4.093 4.4 4.0 4.4 4.4 4.4 4.148 saw 4.4 4.4 4.s 4.4 4.0 9.6 4.4 tot 4.4 4.4 8W970TAL 4.444 4.335 4.333 4.493 6.4 4.9 44 0.0 0.4 4.444 70TAL 50958 of VAtla $TAalk!T100888VAf!0Nt til3 70?AL E0Vit GF STatttt?T CLASS 6 le 74*%L MOURS OP V ALIO wtaB OISICT!4N= WING 8 7ttD*STA4 t LITT CLAJ S e le it*AL MOUR* 1* 7 AL30 uts0 atB8CT80M wtE0 af t8Daff attLITT ca888tht40NS 2112 TetAL Nevi $ TAM ,
(
l i
1 l
- l l
SQN Rad Impact Jan-Dec 1990 Page 31 of 39 TABLE 4 (page 1 of 4)
SEOUOYAH NUCLEAR PLANT HETEOROLOGICAL DATA FOURTH OUARTER 1990
-1 JOINT FREQUENCY DISTRIBUTION IN PERCENT FOR CROUND.-LEVEL RELEASES JetNT PtactNTAet rativtsetts OP vtuo 99tt0 pf wit 0 statetton toa e
StattLtti CLAas A teattA 14een.S C/199 si SEQUOTAM NUCLEAR PLAE'
- OCT L. 14
- Ott 'A. 94 wts0- WINO SfttstaPel 918tCtt+t CALM 6 6-1.4 l.l.).4 1.1 4 4 9.9 1 4 4 S nl 4 11 l.it 4 )4 1 1 j4 ve14 i fotat p 4.e 0.8 444 4.4 0.3 p.elt 4.8 0.0 0 0 4.t*4 est 4.4 4.9 4. ell 4.344 0.111 6.411 8.058 a.6 8.0 4.64L st 4.8 4.9 4.354 4.13) 4.111 4,341 4.3 0.0 6.9 1.141 INE 4.4 4.0 4.463 4.L4) 4.4 4.4 4.6 est 9,0 0 All 8 4.0 4.4 4,4 9.454 4.0 9.9 9.4 4 4 0.4 0.433 Ett 6.4 94 4.0 4.0 4.4 4.4 0.e 0.4 a.4 4.4 58 4.4 4.0 6.0 9.4 4.0 4.4 4.5 4.4 4.S 4.4 888 0.4 4.4 4.0 4.4 0.4 4.6 4.3 0.0 0.0 0.4 8 0.8 0.4 4.0 4.851 4.013 4,til 4.0 4.4 4.4 0.314 SSW 9.4 4.6 4.053 0.0 4.494 0.0 4.9 4.4 4.9 4.191 Sw 0,0 4.0 0.0 0.154 4. ell 4.0 4.4 4.8 0.0 4. Int WSW 0.4 4.9 4.4 8.453 4.4 4.4 4.4 0.3 4.0 0.elJ v 4.4 4.4 4.4 4.4 4.4 0.3 0.4 6.5 i 1 4.4 www 4.9 4.8 8.6 8.0 4.4 8.9 4.3 4.s 6.4 4.4 rw 0.0 0.4 4.4 4.0 9.0 0.341 0.9 0.0 0.4 4.341 arw 0.4 4.4 0.0 4.4 a9 0.052 0.0 0.4 4.0 4.all
$UntetAL 4.4 f.9 4.4t3 1.lle n. net L.341 4.613 4.0 0.6 4.141 tot &L sout$ 0F Takte STAttttti etsteTAtt0Na alti TOTAb 00U15 0F STAptLITT CLAJS A 11 total 30Ull er T AL10 WIND Sit tCit es.w!NO S Pt te-ST A$1Llt? CLAS $ A 00 total A0Vas GF WALIO wtNO OtASCt10s.wtuD 89tte-stAttLitt Onstavatt0NS 1936 total Wovas CALM 0 i
Jetzt etactnThef totqvtsetts Or wind sptio St wtwo otstetten sea STA8tL3tt CLA38 8 lat.lt OBLTA+tteal.1 C>tte al 880U0tha avCLSAR PLAmt OCT 4. 30 . DEC 34. De uts0 UtW9 SittDtMPtl utstCTt04 CALM 4 6-t.4 1.5 1.4 3.%-4.4 5.l.1 4 1 1-13 4 12.5-1B 4 n1.4-34.4 **44 1 T o t a l.
3 0.0 4.0 e.4 6.101 8.493 0.355 0.4 0.4 6.4 4.stl 558 4.0 9.4 4.101 4.445 0.116 0.011 9.4 4.0 0.0 4.930 at 4.4 4.4 6.46$ 0.301 8.143 0.053 6.4 8.6 4.4 3.836 Est 4.0 4.0 0.314 4.454 4.0 0.0 4.0 4.4 9.4 4.J63 5 4.4 0.4 4.101 6.9 6. ell 4.8 0.0 0.0 0.0 4.tll tat 4.0 0.0 4.953 8.0 4.0 4.0 0.0 4.0 4.0 4.053 st 6.3 4.9 4.8 4.4 0,4 4.4 9.3 0.0 0.0 4.0 att 4.4 0.0 0.084 4.4 4.443 4.103 0.0 e4 6.4 4.258 8 4.9 4.0 4.0 4.451 0.413 6.851 0.4 4.4 4.0 0.139 saw 0.6 4.9 0.0 0.093 0.389 4.4 9.4 0.2 a.4 4.363 SW 4.0 0.0 0.143 0.201 6. ell 0.0 4.0 0.0 4.4 0.353 wtw 6.0 4.0 8.0 9.9 0.4 4.4 4.0 4.6 0.0 4.3 w 8.4 0,8 4.4 4.4 4.3 0.0 0.4 0.0 0.4 4.0 www 6.4 0.0 0.0 4.9 4.4 4. ell .e.0 9.4 4.0 8.413 tw 4.0 0.4 4.9 4.4 4.012 0.181 4.0 0.0 9.4 4.151 erv 4.4 4.4 4.0 4.8 4.103 e.to) 6.4 04. 0.0 0.361 SuttetAL 4.4 0.4 1.148 1.134 1.184 e.115 c.e 4.4 e.0 4.Jat TETAL E0Vai of TAL50 STA8tatti etsttT*
- togs 2143 701AL EOUll 0F ST At t Ltti CLA83 5 El total 10USS OF TALIO WING OttBCitosawtu0 SPEE0*SthatLitt C LAS S 5 el TOTAL 40U48 0F T ALIO wta0 S tatCTIO8-w1E D Sitte-stAttttti testaTAttens 1934 tot AL 50083 CALM 4
I l
l-SQN Rad Impact ..
Jan-Dec 1990 Page 32 of 39 TABLE 4 (page 2 of 4)
SEQUOYAH NUCLEAR PLANT METEOROLOGICAL DATA FOURTH OUARTER 1990 JOINT FREQUENCY DISTRIBUTION IN PERCENT FOR GROUND-LEVEL RELEASES Jetzt pesetNTast P g Utwetts 0F wtWe 49tt0 ft wtwo OtttCTtos Poe STAttLitt CLASS C !.l.14 StLTA-tse.l.$ C/tte N)t ,
880V0The #UCLEAA plast OCT l. 94 . ett 34. 14 W139 w!ND 8PttOlMPRI MC,T,,QW CALM 4 4 4.4 I l-1.4 4.l.1 4 1.5 1 4 1.1.(1.4 13 , l. g 4 . 4_ ge 1 34 e 3 34.1 g g
a 4.8 4.4 4.4 4.441 8.413 9.493 4.8 4.4 6.4 0,381 Nut 4.0 4.4, 4.301 9.341 4.413 4.451 6.4 0.9 4.0 1.4s1
- 8 4.4 0.4 444tl 4.14) 6. ell 6.4 4.4 e.6 0.4 4.844 Vat 4.4 4.4 4.494 4.014 4.4 4.4 4,0 0.4 9.4 6 443 8 4.4 8.4 4.459 0.0 9.4 4.6 4.4 4.4 4.4 4.nll 888 4.0 0.4 6.4 6.4 0.9 8.6 0.0 4,4 0.0 4.0 SL 6.4 4.4 4.4 4.0 9.4 6.4 0.0 4.8 4.4 0.0 888- 0.4 0.4 4.4 4.4 8.413 0.013 0.0 0.0 4.4 0.143 8 4.4 6.0 4.4 4.463 4s4 4.171 4.0 6.0 64 6.11%
88W 0.0- 4.4 0.103 6.nll 4.063 4.993 9.4 0.0 4.0 4.344 Su ~ e., e.? 4.0 4.458 s.elt 4.4 4.a 4.6 0.0 4.447 W8w - 4. 4 . 4.413 4.8 0.033 4. 0 - 8.0 8.0 ese 4.4 0.183 W 4.9 0.0 4.4 4.0 0.4 4.441 4.0 6.5 0,e 4.103 www 4.4 4.5 4.4 4.0 0.4 0.0 4.0 0.9 0.0 4.4 rw t.4 4.0 4.4 4.4 4.163 0.013 4.4 9.4 0.4 0.431 sww e.9 c.s 6.4 4.0 9.483 4.341 e.6 f.4 4.4 4.314 SUS?0TAL 't.4. 4.433 4.934 1.144 6.834 9.41% 4,9 4.6 0.0 3.641 tofAL seuls 0F T ALIO 4tAalLITT 0888 Avattoss litt TOTAL Eout8 OF 8%A8tkiTT CLASS C 14 TOTAL 80US$ OP.TALID WINO 0!S8CTies-wtB0 SftID=8114tLitt C LAS S C 18
=fotA4 50US$ OF VAL 30 WIND 4tR8 Cites-WIRO 8F880*STA8tkITT testavattost 1934 TOTAL ROURS CAlJI 4 0
30 TWT tracteTAot Fotturweitt or v1ND speto 97 wtwo OttICTtos Poe 6tAttLITT CLASS 4 I L.St OSLTA=Tte-4.5 C/14e n)
StquotAs NUCt4AA I t.As1 OCT L. it = DEC 31, 99 wtsp WIND Spit 0!MPul Stutetfou CALM -0.4=l.4 8.l-l 4 3.5-1.4 til-1,4 f . la l L _4 13.5-18.4 18.1-14.4 tail l TOTAk u 4.4 4.485 0.319 1.343 n.494 1.tal 4.4 4.0 0.4 S. ele sat 4.4 4.843 .1.184 1.lle 1.340 4.94n 4.4 4.4 0.0 1.443 st e.e 4.443 1.484 9.544 4.4 4.6 4.0 0.4 4.4 1.684 838 0,0 0.0 6.380 4.0 0.4 4.8 0.4 9.4 4.4 4.354 1 9.4 4.0 9.138 4.4 0.0 0.4 4.0 ".4 4.0 4.155 858 . 4.0 6.9 ' 4,45$ 4.8 0.0 4.4 4.0 9.4 4.4 0 111 88 0. 4 - 4.4 4.154 4.453 4.4 4.4 4.9 4.4 4.4 6.'ca Set - 4.4 4.0 9.344 4.lt! 4.013 0.15% 0.4 4.4 6.4 4.414 8 1.4 6.413 1.134 4.381 4.354 6.911 9.4 4.4 0.0 3.149 88u 4.4 4.4 1.445 't.134 4.140 9.434 4. ell 9,4 0.4 4.390
- Sv t.9 9.114 L.345 1.343 4.443 4.0 4.6 4.0 0.4 1.449 wsw 4.4 4.464 4.363 4.0 e.463 9.493 e.t 4.s 4.0 6.119 W e.4 4.451 4.141 4.15% 4.341 4.053 0.0 0.4 e.4 4.41%
wuV 0.0 4.115 9.108 4.9 0.155 0.991 9.4 4.4 tie 4.641 tw 9.6 6.443 4.453 e.301 0.394 4 013 .e.4 4.4 4.4 4.411 a ru - 6.4 0.183 0.394 0.511 4.411 4.J19 e.tlJ 0.0 4.4 4.111 SysfotAL 4.0 1.494 f.441 1.144 4.991 4.133 4.143 4.4 4.8 34.131
- t0TAL 80Uta of WALIO 8tA48Liff 648t AW AT10el att3 TOTAE AOU A8 et STASILITT C LA8 0 0 (St tetAL 84U18 Of TALIO W150 StitCT198**ft3D $PRID*STAOILITT CLAJS 0 til TOTAL ueWAS Of VAkt B **tNO 08 28CTtee+wleu S t4 80=$ Tat t Lif t 0$$ltVAf!053 1914 TOTAL M0088 CALM 4 1
SQN Red Impcet Jan-Dec 1990 Page 33 of 39 TABLE 4 (page 3 of A)
SEQUOYAH NUCLEAR PLANT METEOROLOGICAL DATA FOURTH OUARTER 1990 JOINT FREQUENCY DISTRIBUTION IN PERCENT FOR GROUND-LEVEL RELEASES J0 twt 9ttetsThet F9tQVtWCit$ 4P WIND 19840 GT vfE0 9titC?t0# 708 STAttL3ff CLAS8 8 4-4.le 6tLTA-74e 1.1 C/140 Mt St4VOTAR RVCLIAA PLANT OCT 1. 90= Osc 31. 95 wtRD wtNo 878801MPR)
OtttC?t0N CALM 4 dal.4 1.$ 1.4 3.$ S.4 1.l.1 4 1.5.t7.4 13 5 44 4 14 % 34 4 telt ! TOTAL 5 4.044 0.414 3.419 L.943 1.395 4.nll 4.4 0.0 0.8 4.1L4 WNt 4.448 4.$40 3.440 4.938 4.34) 8.4 0.4 4.8 4.6 4.405 WE 4.010 9.436 0.133 4.391 0.4 0.4 0.0 4.0 4.8 1.541 Sat 0.048 4.3Se 4.103 0.0 0.0 3.4 0.4 0.0 0.8 9.384 8 4.403 4.1$$ 4.0 90 4.4 0.4 4.0 4.0 0.0 4.151 884 4.045 9.314 4.053 6.4 4.4 0.9 0.0 0.0 9.6 4. 3t -
St 0.403 0.199 4.143 0.0 4.0 0.0 0.4 0.0 4.5 0.344 sat 6.044 4.544 4.111 4.103 4.115 0.143 4.403 4.0 4.0 1.144 8 0.134 4.814 4.930 4.Sh1 0.310 e.430 0.143 0.0 0.0 3.346 88w 4,431 4.384 3.141 1.441 0.614 0.155 4.4 4.4 4.0 1.448 Sw 0.430 0.311 1.441 1.144 0.115 0.163 4.3 S.6 e.e 3.593 wSw 4.401 8.301 0.383 0.013 4.454 0.18$ t.4 4.0 0.0 4.814 w 4.444 6.341 4.143 0.1$1 0.103 0.4 4.6 4.8 6.4 6.$13 w ww a.044 0.0 4 310 0.155 4.953 0.0 0.0 0.0 0.4 4.531 Nw . 048 4.314 0.133 4.413 0.1$$ 4.4 4.4 4.0 4.0 0.935 urw 0.414 4.nll L.401 4.434 4.301 0.443 4.4 0.0 0.1 3.393 SUBTOTAL 4.355 3.993 13.834 4.109 3.841 1.395 4.341 4.0 e.0 33.364 Tot AL s0UR$ OF W ALIO ST ASILt?T el8817 Attout 3143 10TAL E0VSS OF STASILITT CLASS 8 159 FATAL ROURS OF TALL 0 vta0 Ot t$CT305.w1NO a tt t0. tT A81Lt ff CLAS S 8 444 total N00R3 0F 4 ALIS wtst 8 t tlCT105.wtWO S P 880.lT AllLITT 4 A4 8 8t ATION S 1936 TOTAL 50008 CALM S
(
10 twt PtterwTAst retoutgetts op wtwo stfro ST wtwo Otatettow Poe STAttLITY CLASS P I 1.94 DELTA.ite 4.0 C/100 14 )
StQU0tAE NUCLEAA PLANT OCT 1, 90 - Ott 3L. 94 wts0 w!ED Sftt0qMPat OtttCTION C A t.M 8 E.n.4 4.l-1.4 1.1 1.4 S.1 1.4 1.5.t2.4 Lt.l.it.1 It.$.34.4 tel4 t *otAL s 4.638 4.343 3.841 0.363 4.0 8.4 4.0 0.0 0.0 3.194 NMR 4.483 4. 8 '! 4 1. Sal 4.135 0.3 0.0 0.0 0.0 0.0 1.431 E3 0.033 1.346 t,lle 0.4 4.4 0.0 0.0 0.0 4.0 3.813 RNE 4.403 4.3$4 0.093 0.0 0.4 4.4 0.0 0.0 0.0 0.113 4 4.843 0.391 4.el3 S.0 4.4 4.1 0.0 0.0 0.0 S.344 ISE 0.004 4.343 4.163 0.8 4.4 4.4 4.4 0.0 0.4 0.445 84 8.444 4.384 4.103 0.4 4.4 0.4 4.0 4.0 4.0 0.449 888 4.40% 0.413 0.1$8 0.0 4.6 0.0 0.0 0.0 6.0 0.113 8 0.401 4.341 0.471 4.4 4.0 8.4 4.0 4.0 4.0 0.44$
$$w 0.304 0 ell 4.133 4.143 0.0 4.0 0.4 4.6 4.0 6.884 Sw 4.001 4.143 4.836 6.343 S.4 4.4 0.0 0.0 4.4 1.199 wtw 4.443 S.933 0.341 4.6 0. 0 . 6.0 9.4 4.0 0.6 6.360 W 4.409 4.353 4.4 0.151 0.0 0.0 0.0 4.0 4.0 0.391 WMW 4.444 0.0 6.053 4.4 9.4 4.0 0.0 0.0 0.4 6,093 rw 6.001 0.053 0.053 4.nel 4.4 6.0 4.0 0.0 4.0 9.391 Erw 4. ell 4.0 0.343 4.4 0.0 4.0 0 4 0.0 0.0 0.364 899T0TAL 4.tll 4.591 14.113 1.340 4.4 4.0 0.0 4.0 4.0 10.144 TOTAL 80Uns GF T ALID SThalLITT 043tATAf t048 Ital TOTAL $4U38 0F STASILITT CLAJS F til TOTAL EQUS$ OF T AL80 wt 20 9tRICT tosawtBO $P580-stAttLITT CLAS$ F 14 3 TOTAL E0Vt3 0F W ALE S W150 OIRE CT!05.wt30 Spito.5?ABILITT OestATATIONS L934 TOTAL SOURS CALA 3
SQN Rad Impact Jan-Dec 1990 Page 34 of 39 TABLE 4 (page 4 of 4)
SEOUOYAH NUCLEAR PLANT METEOROL,0GICAL DATA FOURTH OUARTER 1990 JOINT FREQUENCY DISTRIBUTION IN PERCENT FOR GROUND--LEVEL RELEA3ES 70 TNT Pt9CINTA4B Pitcutectts OP wtNO $ Pit 0 Of WING 9tttCty s Poa STASILITT CLA$$ 4 (Dtyta f a 4.0 C/100 Al 880VOTAN NUCLSAS P LA NT GCT 4. 80 . Ott 31 99 W180 vise attt0lMPul OtStCTf65 CALn 6.4 1.4 1.l.).4 1.1 5.4 5 t.1 4 9.5.tl.t 31.1 10 4 44.s.3,,4 ,.ge,g totat u 4.861 4.4 4.082 4.8 0,6 6.0 0.0 4.0 4.4 4.053 uut 4.401 0.316 0 844 4.4 4.0 4.0 8.4 e,4 4.0 0.481 Nr 4.404 4.24T 4.634 0.4 4.6 4.0 9.4 0.4 0,0 0.415 But 6.04) 0.384 4.492 0.0 0.0 4.8 4.0 0.0 0.4 0.343 l t - 4.404- 4.316 6.443 9.4 a.e 9.4 04 0.0 4.0 0.411 885 6.481 4.201 0.0 0.4 4.9 0.4 9.4 0.4 0.0 0.200 38 6.004 0.413 0.0 4.5 4.8 0.8 0.0 6.4 4.0 4.411 set 6.005 0.314 6.401 4.4 4.0 99 0.4 0.0 4.0 8.431 8 0.864 4.340 0.2$8 4.0 4.4 4.0 9.4 6.4 4.4 4.$14 82w 6.861 4.143 0.348 0.6 0.0 4.0 e.0 0.4 - 0. 0 0.414 sw 4.043 4.4 6.310 4.eSJ 6.6 e.4 .I . e 4.4 0.4 4. lit wsw 4.001 4.0 0.433 4.4 4.0 4.6 6.0 0.0 0.0 0.013 W 4.0 4.9 0.4 0.0 4.0 4.4 0.4 6,6 9.4 4.0 www 4.6 3.8 0.0 . 0. 4 0.0 4.4 4.4 0,0 0.6 0.0 rw - 4.6 4.0 6.4 6.8 0.0 3.6 0.4 0.0 0.0 4.4 srw 9.4 4.4 0.0 4.4 0.0 e.8 4.6 4.4 4.0 0.8 auttot&L 8.413 1.420 2.189 4.0$1 4.4 8.6 1.0 3.6 4.4 1.114 10thL soUns GF WA&ta STA8tLITT 08483YAt10NS 3141 tetAL soUta of 8thBIL2tf CLAJS 4 19) 19tAL NOUS $ Of VALIS W130 Ota8CT30s.vtse stE80*stA8ttttt CLAas 4 tel tot &L p0URS OF WAL1D Wis0 OIR8 Cites. WIND Sf f 8 6+5f A8 8 ttf t -08 8 88V Atteus 1934 10thL d4U$8 ChLM . L d
i
. -_ . . .. . - - . - - . - . . ~ . . - , . .- -
9 l
,. SQN Rad Impact l Jan-Dec 1990 Page 35 of 39 TABLE 5 SEQUOYAH NUCLEAR PLANT - RECEPTOR LOCATIONS
- Site Boundary-Locations (used for both all quarters)
Sector Distance (m) Sector . Distance (m)
Site Boundary N 950 Site Boundary S 1570 Site Boundary NNE 2260 Site Boundary SSW 1840
- Site Boundary NE 1910 Site Boundary -SW 2470 Site Boundary ENE 1680 Site Boundary WSW 910 Site Boundary E 1570 Site Boundary W 670 Site Boundary ESE 1460 Site Boundary WNW 660 Site Boundary SE 1460 Site Boundary WW 660 Site Boundary SSE 1550 Site Boundary NNW 130 Actual Receptor Locations (based on the Fall 1990 Land Use Survey)
Sector Distance-(m) Sector Distance (m) '
. Resident W 1353 Garden k 1829 Resident NNE 2400 Garden NNE 3048 Resident NE 2248 Garden NE 2324 Resident. ENE 2096 Garden ENE 2496
, Resident E 1619 Garden ESE 1791 Resident ESE 1638 Garden SE 3162 Resident SE 1562 Garden S 2362 Resident, Garden SSE 1943 Garden SSW 2686 Resident S 2286 Garden SW 3353-Resident- SSW 2019 Garden WSW 1524 Resident SW 2971 Garden W 1987
' Resident- WSW .1143 Garden WNW 1867
- Resident W 1010 Garden NW 1372 Resident WNW 1753 Garden NNW: 991 Resident NW 1448 Milk Cow Adult .N 4515.
Resident NNW 895 Milk cow Adult NE 8686 Milk Cow Adult- WNW- 2096 Milk Cow Adult NW 2134 I
SQN Rad Impact Jan-Dec 1990 pago 36 of 39 i TABLE 6
SUMMARY
OF OUARTERLY DOSES *
=
Air submersion Real Pathway Liquid Effluents Al t-Y _ Air-B Skin TB Max. Organ TB Max. Organ Year QTR (mead) (mrem) (mrem) (mrem) 1983 1 0.03 0.18 0.04 0.02 <.001 Bone 0.21 0.34 Bone i 2 0.12 0.48 0.21 0.10 0.02 GIT 0.15 0.23 Bone 3 0.07 0.40 0.11 0.05 0.03 Bone 0.09 0.20 Bone
- 4 0.07 0.41 0.09 0.04 0.003 Thyroid 0.11 0.14 Liver
- 1984 1 0.11 0.55 0.19 0.08 0.004 Thyroid 0.04 0.05 Liver 2 0.17 0.94 0.29 0.12 0.04 Bone 0.04 0.04 Liver 3 0.18 0.99 0.26 0.11 0.03 Thyroid 0.13 0.22 Bone 4 0.07 0.39 0.12 0.05 0.005 Thyroid 0.04 0.06 Liver 1985 1 0.12 0.65 0.18 0.09 0.18 Thyroid 0.03 0.04 Bone 2 0.10 0.63 0.18 0.07 0.003 Thyroid 0.14 0.21 Bone 3 0.05 0.32 0.08 0.03 0.015 Thyroid 0.17 0.43 Bone
" 4 c.001 0.001 0.0 0.0 0.018 Thyroid 0.02 0.02 Bone 1986 1 <.001 < 001 <.001 <.001 0.004 GIT 0.007 0.009 Liver I 2 <.001 <.001 <.001 <.001 0.014 Liver 0.018 0.021 Liver 3 <.001 <.001 0.0 0.0 0.010 GIT 0.038 0.044 Bone 4 <.001 < 001 0.0 0.0 0.010 GIT 0.011 0.012 Liver 1987 1 < 001 <.001 0.0 0.0 0.004 GIT 0.002 0.003 Liver EL 2 < 001 <.001 0.0 0.0 0.On6 GIT 0.017 0.021 Liver 3 <.001 <.001 0.0 0.0 0.008 GIT 0.084 0.095 Bone
. A <.001 <.001 0.0 0.0 0.006 GIT 0.034 0.039 Bone 1988 1 <.001 <.001 0.0 0.0 0.001 Liver 0.055 0.074 Liver 2 0.003 0.014 0.004 0.002 0.003 Thyroid 0.18 0.21 Bone 3 0.007 0.036 0.008 0.003 0.007 Bone 0.054 0.064 Bone 4 0.007 0.037 0.012 0.005 0.003 GIT 0.009 0.01 Liver 1989 1 0.02 0.02 0.01 0.02 0.007 Thyroid 0.001 0.002 Thyroid 2 0.03 0.06 0.02 0.03 0.003 Liver 0.002 0.002 Liver
- 3 0.07 0.17 0.04 0.08 0.03 Thyroid 0.001 0.001 Liver 4 0.22 0.61 0.15 0.34 0.009 Thyroid 0.005 0.006 Liver 1990 1 0.26 0.69 0.41 0.17 0.002 Liver <0.001 0.001 GI Tract 2 0.06 0.15 0.09 0.04 0.002 Thyroid 0.002 0.005 G1 Tract 3 0.10 0.27 0.17 0.07 0.002 Thyroid 0.002 0.003 GI Tract 0.008 0.02 0.02 0.006 0.002 Thyroid 0.003 0.002 Liver
) 4
- Note: All calculated doses are below limits specified in Appendix I to 10 CFR 50.
l SQN Rad Imract 1 Jan-Dec 1990 Pa5e 37 of 39 l
Figure 1 SON Airborne Effluents Fission Goses Released and Resulting Doses 1o000- 4.o Legend
,oon.
SON Releases
)' u Gamma Dose sooo- ;
?
r ,
l i, ,
3.o .... Beta Dose 5 "~ f ; !,
2 :
3 l !.
- "u n "'
~
l \ l \, n l ! ! '. b
= scoo- ! ,
I : ! , 2.o 5 l .l ', l i
g 1 \:
g l '; 3,3 3 :
8 "' ;
f j .
i.o 2000- ;
toco- ! ( / \ ;
/ - .
.Y < s:,
o . . , . . lo 80 81 82 83 84 85 86 il7 88 89 90 Year y,
- . - . - _ . _ _ . _ _ - . . . _ --. _ - -.-_ - . _ _ - . . . _ . - ~ _ . - - - . , .
SQN Rad tmpact Jan-Dec 1990 >
Page 38 of 39 Figure 2 SON Airborne Effluents i lodines and Porticulotes Released and Resulting Doses
.20 " " 20 Legend
.i s . -
. is SON Releeses -
Max Orgon Dose ;
.i t ' "
. 16
,r 5 o
N .14- . 14 r
j .i:- i .. i2 T ir v
t r 2 3 .t o - E . 10 I -
yo ,
- 8 S- [ 6 ag
% a. \
y:
a ,
E ,.
o
- M b
.04- l- .04
- i. _
.o2 - :- -
.o2 g ,l:-
_ Bl _ __ ,
80 81 82 83 84 85 86 87 88 89 90 Year een2 l
l
{ _. . . _ _ . . _ _ . _ _ . . ._ _. _ _ _ _. _ _ .. _ -_. . _
i SQN Rad Impact Jan-Dec 199o Pa t,e 39 of 39 Figure 3 1
I SON Liquid Effluents fission and Activation Products Released and Resulting Doses 10- ~ 3.0 !
Legend e- SON Releases 2.5 Totol Body Dose s.
j .... Max Orgon Dose 1 \
2 ; 2.0 b \ ;
~ .. :
' s
'* 4 T s. } .i.s 1 1, i, !
a i
34-b
.x i.0 i 3
2- -
\ .
, ., ,3
\ ',
,i .
1- / ' i 0 , i b b 0 82 83 84 85 86 87 88 89 90 Year g o
.-- .- . - - - _