ML20056F644
| ML20056F644 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/30/1993 |
| From: | Spedl G COMMONWEALTH EDISON CO. |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 93-0050, 93-50, NUDOCS 9308300212 | |
| Download: ML20056F644 (69) | |
Text
_. _ _.. _.
i Comrnonwealth Edison O
Dresden Nuclear Power Station J
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Q-R.R. 41 l
Morris, Illinois 60450 Telephone B15/942-2920 l
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August 19, 1993 GPS PMLTR #:
93-00E0 l
Mr. John B. Martin Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
[
Subject:
Dresden Nuclear Power Station
[
Radioactive Effluent Report i
I NRC Dockets 50-10, 50-237. 50-249 Enclosed is the Radioactive Effluent Report for January through j
June, 1993 1'or Dresden Nuclear Power Station.
t A copy of this report will be furnished to the. NRC Resident Inspector.
Sincerely Yours, A
br $?b99 Gary F.
Spedl Station Manager i
Dresden Nuclear Power Station i
GFS:MG:kls
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Enclosure l
cc:
M. Gagnon File /NRC File /Nuracrical Attached Distribution. List
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930830021F-930630 3
ADOCi 05000010 I?
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T Semi Annual Report DiEtribution All Stations Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Station Pl-137 Washington D.C. 20555 (Original plus one copy)
- or -
One White Flint North
- 11555 Rockville Pike Rockville, MD 20852 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, IL 62704 ANI Town Center, Suite 300S 29 South Main Street West Hartford, CT 06107-2445 American Electric Power Service Corp.
Nuclear Operations Division 1 Riverside Plaza Columbus, Ohio 43216 (2 copies)
U.S. Environmental Protection Agency Air and Radiation Branch, Region V Health Physicist 230 S. Dearborn St.
Chicago, IL 60606 Illinois Environmental Protection Agency Mr. Ed Harek, Acting Manager Maywood Regional Office l
1701 First Avenue Maywood, IL 60153 Illinois Environmental Protection Agency Division of Water Pollution Control
(
Environmental Protection Specialist 2200 Churchill Rd l
Springfield, IL 62706 If delivered by private carrier (i.e. Federal Express) direct carrier to the lower back area of the I
One White Flint North Bldg, Mail Station Pl-137
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l Semi Annual Report Distribution l
All Stations (Cont'd) i Murray & Trettel, Inc l
Environmental Meteorologist j
414 West Frontage Rd Northfield, IL 600'4
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i Teledyne Isotopes Midwest Laboratory l
General Manager i
700 Landwehr Rd Northbrook, IL 60062 Chemistry Support E;
Chemistry Support Supervisor Eighth Floor j
Downers Grove l
Emergency Preparedness Director j
Downers Grove Nuclear Quality Programs and Assessments l
General Manager Suite 650 Downers Grove 1
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s Semi Annual Report Distribution Dresden Station Manager i
Dresden Health Physics Services Supervisor Dresden i
NRC Senior Resident Inspector t
Dresden j
i U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Rd.
i Glen Ellyn, IL 60137 i
4 (Two Copies)
Quality verification Superintendent Dresden j
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i DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 1
REGULATORY LIMITS Gaseous Effluents - Dose This Specification is provided to ensure that the dose at the unrestricted area boundary from gaseous ef fluents from the units on site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas.
The l
annual dose limits are the doses associated with the concentrations of 10 J
CFR Part 20, Appendix B,
Table II.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CTR Part 20.106(b)). The specified release rate lindts restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the unrestricted area boundary to lesh than or equal to 500 mrem / year to the total body or to l
less than or equal to 3000 mrem / year to the skin.
These release rate i
limits also restrict, at all times, the corresponding thyroid dose rate j
above background to a child via the inhalation pathway to less than or j
equal to 1500 mrem / year. For purposes of calculating doses resulting from l
airborne releases, the main chimney is considered to be an elevated release point and the reactor building vent stack is considered to be a mixed mode t
release point.
j Dose, Nob e Gases f
This Specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I,
The Limiting j
conditions For Operation implement the guides set forth in Section II.3 of p
Appendix I.
The statements provide the required operating flexibility and e
at the same time implement the guides set forth in Section IV. A of Appendix j.
I to assure that the releases of radioactive material in gaseous effluents l
will be kept "as low as is reasonably achievable."
The Surveillance Requirements implement the requirements in Section III. A of Appendix I that i
conformance with the guides of Appendix I is to be shown by calculational-l procedures based on models and data such that the actual exposure of an_
individual through the appropriate pathways is unlikely to be substantially j
underestimated.
The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous ef fluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with j
10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide
[
1.111,
" Methods for Estimating Atmospheric Transport and Dispersion' of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,*
Revision 1, July 1977-.
The ODCM equations provide for determining the air l
doces at the unrestricted boundary based upon the historical average atmospheric conditions. NUREG-0133 provides methods for doce calculations consistent with Regulatory Guides 1.109 and 1.111.
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DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 5
Dose, Radiciodines, Radioactive Material in Particulate Form and Radionuclides
+
Other than Noble Gases This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I,
The Limiting conditions for Operation are the guides set forth in Section II.C of Appendix I.
The statements j
provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of j
radioactive materials in gaseous effluents will be kept "as low as reasonably-i achievable."
The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix 1 that l
l~
conformance with the guides of Appendix I be shown by calculational procedures l
based on models and data such that the actual exposure of an individual through l
appropriate pathways is unlikely to be substantially underestimated. The CDCM l
calculational methods approved by NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the
{
l methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating i
l Compliance with 10 CFR Part 50, Appendix I",
Revision 1,
October 1977 and Regulatory Guide 1.111,
" Methods for Estimating Atmospheric Transport and l
Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining j
the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radiciodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these specifications were:
- 1) individual l
inhalation of airborne radionuclides, 2) deposition of radionuclides onto green l
leafy vegetation with subsequent consumption by man and 3) deposition onto grassy j
areas where milk animals graze with consumption of the milk by man.
Gaseous Waste Treatment l
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The OPERABILITY of the gaseous waste treatment which reduces amounts or concentrations of radioactivs materials ensures that the system will be available l
for use whenever gaseous effluents require treatment prior to release to the j
environment.
The requirement that the appropriate portions of this system be operable when specified provides reasonable assurance that the releases of radioactive materials in gasecus ef fluents will be kept "as low as reasonably achievable".
This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design
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objective Section II.D of Appendix I to 10 CFR Part 50.
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DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 j
l LIOUID EFFLUENTS i
t Concentration This specification is provided to ensure the concentration of radioactive materials released in liquid waste ef fluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix i
B, Table II, Column 2.
The concentration limit for noble gases, MPC in air (submersion), was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Publication 2.
Dose This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I,
The Limiting condition for Operation implements the guides set forth in Section II.A of Appendix I.
The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable".
The dose calculations in the ODCM implement the i
requirements in Section III.A of Appendix I that conformance with the guides of f
Appendix I be shown by calculational procedures based on models and data such i
that the actual exposure of an individual through appropriate pathways is
'l unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided i
in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I",
Revision 1, October 1977 and Regulatory Guide 1.113,
" Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I",
April 1977.
NUREG-Oll3 1
provides.iethods for dose calculations with Reg Guide 1.109 and 1.113.
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Liquid Waste Treatment The operability of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.
The requirement that the appropriate portions of-this system be used when specified provides assurance that the releases of
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radioactive materials in liquid effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR Part 50 and design objective Section II.D of Appendix I to 10 CFR Dart 50.
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DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) l I
I The concentration of radioactive materials released in gaseous and liquid i
effluents from the site to unrestricted areas will be less than the concentration j
levels specified in 10 CFR Part 20, Appendix B, Table II, Columno 1 and 2.
The concentration limit for noble gases, MPC in air (submersion), was converted to an equivalent concentration in water using the International commission on j
Radiological Protection (ICRP) Publication 2.
MAXIMUM PERMISSIBLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE l
I i
NUCLIDE MPCfuci/ml)*
l Kr-85m 2.OE-04 4
Kr-85 5.0E-04 i
Kr-87 4.OE-05
)
Kr-88 9.OE-05 i
Ar-41 7.0E-05 I
l Xe-131m 7.OE-04 Xe-133m 5.OE-04 j
Xe-133 6.OE-04 Xe-135m 2.0E-04 l
Xe-135 2.OE-04 l
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- Computed from Equation 20 of ICRP Publication 2 (1959),
i adjusted for infinite cloud submersion in water, and i
a R = 0.01 rem / week, density = 1.0 g/cc and Pw/Pt = 1.0.
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DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 i
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AVERAGE ENERGY l
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The average energy of fission and activation gases was calculated for the l
gaseous effluents released frcm the site. The average energy is based on the percentage of each fission gas nuclide present and its average energy i
per disintegration (E in MeV/ dis) f or gamma and beta emissions separately.
t l
Ea = 3.37E-01 MeV/ dis j
t En = 4.80E-01 MeV/ dis f
EOUIPMENT OUT-OF-SERVICE:
The Unit 1 Chimney SPING was out of service from June 30, 1992 to March 9, 1993.
This was due to repairs and calibration of the monitor.
The SPING was again out of service from March 9,1993 to June 11, 1993 and June 18, 1993 to past June 30, 1993 for further repair work.
The backup l
air sampler was used during this period.
l The Unit 2 Service Water Monitor was out of service from January 13, 1993
]
to February 18, 1993 due to cleaning trapped sediment in the pipe work.
l Unit 2 Service Water Monitor was out of service f rom February 24, 1993 to l
June 8, 1993 and the Unit 3 Service Water Monitor was out of service from February 24, 1993 to May 20, 1993. The station modified the pipe work and 4
pumps during this time in order to increase sample flow.
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The Unit 2 Service Water Monitor was out of service from June 15, 1993 to i
July 9, 1993 for cleaning.
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The Unit 3 SLrvice Water Monitor was taken out of service on May 26, 1993 i
and remained out of service past June 30, 1993 for calibration constant i
adjustments and monitor repairs.
4 The Unit 2/3 Reactor Building Ventilation SPING was out of service from March 18, 1993 to July 9,
1993 because of calibration, detector l
replacement, sample pump problems and input / output circuit malfunction.
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DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 MEASUREMENTS AND APPROXIMATIONS A.
Fission and activation gases:
The D-1. Chimney, D2/3 Chimney, and D2/3 Reactor Building Vent are sampled weekly via a grab sample. The samples are analyzed for specific isotopes present in the release using a Hyper-Pure Germanium (HP Ge)
Spectrometry System.
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Tritium is sampled monthly via a grab sample on the D-1 l
Chimney, D2/3 Chimney, and D2/3 Reactor Building Vent and
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l analyzed using a
Liquid Scintillation
- Counter, j
Krypton-85 is estimated in the D2/3 Chimney using a i
i recoil or non-recoil calculation using the fission per j
second plot and the sum of Kr-85m, Kr-87, Kr-88, Xe-133, 1
1 Xe-135, and Xe 138 activities present in Reactor Of f-Gas.
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B.
Iodine and Particulate:
Iodine and particulate samples I
from the D-1 Chimney, D2/3 Chimney and the D2/3 Reactor Building Vent are collected for a maximum seven day l
period. These samples are analyzed for specific nuclides present in the release using a HP Ge spectrometry system.
When iodine or particulate samples are not used for j
reporting the release rate due to management decision i
l that the sample may not be representative, an average of i
i the preceding sample and the following sample is used to l
l calculate the release.
A monthly composite of the l
particulate samples is sent to a vendor to be analyzed
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l for Fe-55, Sr-89, Sr-90, and Gross Alpha activity.
l C.
Liquid Effluents: Analyzed for specific isotopes present in the release using a HP Ge spectrometry system.
A j
composite of all batches for the month is sent to a l
vendor to be analyzed for Sr-89, Sr-90, Fe-55, H-3, and
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Gross Alpha activity.
A sample of each Containment i
Cooling Service Water (CCSW) system is analyzed each I
month for specific isotopes present in the release using i
a HP Ge spectrometry system.
A sample of each CCSW system is sent each month to a vendor to be analyzed for Sr-89, Sr-90, Fe-55, H-3, and Gross Alpha activity.
D.
Estimation of Overall Errors:
The methods used for i
estimating overall errors associated with radicactivity measurements vary with discharge path and-form of isotopes.
Factors that contribute to the error include such items as calibration of counting equipment, counting statistics, sampling error, discharge volume, and flow rate monitors.
E.
Estimation of Vendor Analyzed Information:
The vendor analyzed data for Sr-89, Sr-90, Fe-55, H-3 and Gross Alpha was projected, where applicable, for the months of April through June using March data.
A corrected Effluent Report will be submitted with the next Semi-Annual Effluent Report.
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l DRESDEN NUCLEAR POWER STATION UNITS 1,2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1
January Through June 1993 GASEOUS EFFLUENTS Decket Numbers: 50-10 l
50-237 J
SUMMATION OF ALL RELEASES 50-249 l
EST. TOTAL TYPE OF RELEASE UNITS let QUARTER 2nd QUARTER ERROR,%
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FISSION AND ACTIVATION GASES 1.
Total Release l
Ci
- i. 1.03+00 l 7.32E+00 7.31 l
2.
Average Release Rate for Period uCi/sec l 1.32E-01 l 9.31E-01 i
9 j
l 3.
Percent of Technical Specification Limit i
l B.
IODINES i
l 1.
Total Iodine-131 l
Ci j 3.44E-04 j 1.32E-04 1 21.6 2.
Average Release Rate of I-131 for Period i uCi/sec j 4.42E-05 l1.68E-05 3
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Percent of Technical Specification Limit t
4.
Total Iodine-131, Iodine-133,and Iodine-135 Ci j 3.17E-03 [ 1.07E-03 C.
PARTICULATES i
I j
1.
Particulates with half-lives > 8 days l
Ci l
1.45E-02 2.41E-02 l 34.1 2.
Average Release Rate for Period l uCi/sec 1.86E-03 3.06E-03 )
i 3.
Percent of Technical Specification Limit 4.
Gross Alpha Radioactivity Ci l 5.20E-06 l 8.12E-07 D.
TRITIUM l
1.
Total Release j
Ci l 2.04F+00 i 1.51E+00 l 7.89 t
2.
Average Release Rate for Period j uCi/see 2.62E-01 l 1.93E-01 j-3.
Percent of Technical Specification SiEtt l
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- The information is contained in the Radiological Impact on Man section of the report.
Total airborne release data is provided which includes fission and l
activation gases, iodines, particulates, and tritium.
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i DRESDEN NUCLEAR POWER STATION UNITS 1,2, AND 3
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1993
]
GASEOUS EFFLUENTS Docket Numbers: 50-10 50-237 SUMMATION OF ALL RELEASES 50-249 i
LLD (uCi/ce) l i
1.
FISSION GASES j
Xe-138 1.60E-07 l
Xe-135m 9.90E-08 i
Kr-87 4.40E-08 l
Kr-88 5.40E-08
{
Kr-85m 1.80E-08 i
)
Kr-85 5.10E-06 j
Xe-135 1.60E-08 i
Xe-133 4.40E-08 l
Ar-41 2.50E-08 I
Xe-133m 1.50E-07 i
2.
IODINES l
I-131 7.90E-13 l
)
I-133 3.40E-12 l
I-135 4.70E-10 l
i 3.
PARTICULATES Sr-39 6.00E-14
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Sr-90 3.00E-15 Cr-51 5.40E-12 Mn-54 6.80E-13 i
Co-58 8.00E-13 Fe-55 1.00E-14 Fe-59 1.60E-12 Co-60 1.40E-12 1
I Zr-95 1.40E-12 Nb-95 7.10E-13 Mo-99 7.40E-13 Ru-103 7.20E-13
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Aa-110m 6.30E-13 Sb-124 5.70E-13 I-131 7.70E-13 Ce-134 6.80E-13 i
Ce-136 7.30E-13 i
3 Cs 137 7.60E-13 Ba-140 3.30E-12 La-140 1.10E-12 i
Ce-141 9.99E-13 i
i Ce-144 3.80E-12 In-65 1.70E-12 Ba-133 7.20E-13 l
Sb-125 1.90E !
Otherst i
Gross Alpha 6.00E-15 i
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DRESDEN NUCLEAR POWER STATION t
UNIT 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June
- 199_3, i
DI Chimney GASEOUS EFFLUENTS l
GROUND LEVEL RELEASES l
DocketNumber:
50-10 SEMI-ELEVATED RELEASES
(
XX ELEVATED RELEASES l
CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED ;
UNIT) 3rd QUARTER 4th QUARTER 3_rj QUARTER 4th QUARTER FISSION GASES j
Xe-138 Ci Xe-135m Ci
?
Kr-87 Ci I
Kr-88 Ci Kr-85m Ci t
Kr-85 Ci j
Xe-135 Ci Xe-133 Ci TOTAL Ci NONE l
NONE IODINES l
I-331 Ci I
f I-133
! Ci I-135 Ci e
TOTAL Ci NONE NONE I
PARTICULATES Sr-89 Ci 1.21E-06 1
Sr-90 Ci t 4.79E-07 5.67E-07 f
+
Cr-51 Ci !
i i
Mn-54 Ci Co-58 Ci Fe-59 Ci Co Ci 1.06E-05 1
Zr-95 Ci Nb-95 Ci Mo-99 Ci Ru-103 Ci Aa-110m Ci Sb-124 Ci 1
I-131 Ci a
l Cs-134 Ci a
Cs-336 Ci Cs-137 Ci 7.47E-05 I
Ba-140 Ci La-140 Ci !
3 Ce-141 C 3.
i_
Ce-144 Ci !
Zn-65 Ci Ba-133 Ci Sb-125 Ci a
Fe-55 Ci !
3.28E-05 TOTAL-C1 1.20E-04 5.67E-07 NONE t
NONE The activity of this nuclide is less than the LLD listed on the appropriate table.
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DRESDEN NUCLEAR POWER STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through March 1993 21 Chimney CASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Number: 50-10 SEMI-ELEVATED RELEASES XX ELEVATED RELEASES CONTINUOUS MODE NUCLIDES RELEASED l UNIT l JANUARY FEBRUARY l
MARCH l 1st QUARTER TOTAL FISSION GASES 1
Xe-138 Ci;.
t 1
Xe-135m Ci !
Kr-87 i ci !
i Kr-88
! Ci !
Kr-85m Ci !
t Kr-85 Ci !
t Xe-135 t Ci t
=
Xe-133 i Ci TOTAL Ci IODINES i
t I-131 Ci !
1 I-133 Ci !
I-135 Ci SOTAL Ci i
PARTICULATES t
1.04E-06 1.74E-07 1.21E-06 Sr-89 Ci Sr-90 Ci 2.24E-07 f
2.05E-07 4.29E-07 t
Cr-51 Ci 1 Mn-54 Ci !
1 Co-58 Ci t t
Fe-59 Ci 1.06E-05 1.06E-05 Co-60 Ci Zr-95 Ci f
Nb-95 Ci 1
t Mo-99 Ci Ru-103 Ci !
Aa-110m Ci i t
Sb-124 1 Ci t
I-131 i Ci Cs-134 f Ci t
Cs-136 f Ci 1 Cs-137 i Ci t 4.4CE-05 1
3.07E-05 7.47E-05 t
t Ba-140 Ci t
f La-140 Ci Ce-141 Ci !
Ce-144 Ci Zn-65 I Ci 1
Ba-133 Ci f
Sb-125 Ci Fe-55 Ci 4.81E-06 2.40E-05 3.96E-06 1
3.28E-05 TOTAL Ci 4.81E-06 7.99E-05 t
3.50E-05 1.20E-04 The activity of this nuclide is less than the LLD listed on the appropriate table.
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DRESDEN UUCLEAR POWER STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT April' Throuch June 1993 DI Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES l
Docket Number: 50-10 SEMI-ELEVATED RELEASES i
1 XX ELEVATED RELEASES l
CONTINUOUS MODE NUCLIDES RELEASED jUNIT.l APRIL MAY JUNE 2nd QUARTER TOTAL FISSION GASES !
! Ci Xe-135m Ci t
i 1
Kr-87 Ci Kr-88 Ci t
Fr-85m Ci 1
1 Kr-85 Ci Xe-135 t Ci l
t Xe-133
! Ci TOTAL f Ci t
i I-133 t Ci !
I-135 Ci TOTAL Ci PARTICULATES t
Sr-89 Ci Sr-90 C1 1.87E-07 1.93E-07 1.87E-07 5.67E-07 i
j Cr-51 Ci t
Mn-54 C1 t
Co-58 Ci l
f Fe-59 Ci Co-60 Ci Zr-95 Ci Nb-95 Ci I
t Pu-103 Ci Ac-110m Ci Sb-124
! Ci
{
I-131 Ci Cs-134 Ci Cs-136 Ci f
=
Cs-137 Ci 1
Ba-140 Ci l
La-140 Ci f
Ce-141 Ci Ce-144 Ci 2n-65 Ci a
l l
Ba-133 Ci t
Sb-125
! Ci t
! Ci !
f TOTAL i Ci !
1.87E-07 1
1.93E-07 1.87E-07 5.67E-07 C
The activity of this nuclide is less than the LLD listed on the appropriate table.
l i
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i t
t e-
I r
I l
DRESDEN NUCLEAR POWER STATION UNITS 2 and 3 EFFLUENT AND WASTE DISPOSAL SEMIANFUAL REPORT I
j January Through July 1911
)
i D2/3 Chimney GASEOUS EFFLUENTS j
i GROUND LEVEL RELEASES Docket Numbers: 50-237 i
SEMI-ELEVATED RELEASES 50-249 l
f XX ELEVATED RELEASES l
CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED jUNITj let QUARTER j 2nd QUARTER l
1st QUARTERj 2nd QUARTER l
FISSION GASES !
f Xe-138
! Ci 1
Xe-135m
! Ci 1.34E+00 Kr-87 Ci Kr-88 Ci Kr-85m Ci r
Kr-85 C1 3.62E-04 4.86E-04 1
Xe-135 l Ci 1.03E+00 5.9BE+00 t
l Xe-133 Ci 1
1 j
TOTAL Ci 1.03E+00 7.32E+00 None None IODINES I-131 Ci 3.18E-04 1.14E-04 I-133 Ci 1.52E-03 7.37E-04 t
I-135 Ci 1.20E-03 TOTAL Ci 3.04E-03 8.51E-04 None None PARTICULATES i
Sr-89 Ci 1.29E-04 l
t l
Sr-90 Ci 1.09E-06 Cr-51
! Ci 4.08E-04 Mn-54 i Ci 3.87E-05 1.69E-05 t
t Co-58 Ci Fe-59 Ci !
! Ci !
9.76E-05 3.27E-05 t
f Zr-95 t Ci i
Nb-95 Ci t
Ru-103 Ci t
Ao-110m Ci !
1 Sb-124 Ci !
I-131 Ci Cs-134 Ci Cs-136 Ci i
Cs-137 Ci 2.85E-05 2.06E-05 Ba-140 Ci 5.33E-05
[
l La-140 Ci 5.33E-05 Ce-141 Ci Ce-144 Ci Zn-65 Ci Ba-133 Ci a
Sb-125 Ci t
Fe-55 Ci 4.10E-03 1.97E-02 f
TOTAL Ci 4.91E-03 1.98E-02 None None l
The activity of this nuclide is less than the LLD listed on the appropriate table.
(1:\\wk-Proc \\pintmgr\\gfs93\\0050.93) 16 l
l l
l
i 1
DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 j
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l
January Through March 1993
]
D2/3 Chimney GASEOUS EFFLUENTS i
l GROUND LEVEL RELEASES-i Docket Numbers: 50-237 SEMI-ELEVATED RELEASES 50-249 i
'i XX ELEVATED RELEASES CONTINUOUS MODE t
NUCLIDES RELEASED UNITj JANUARY l
FEBRUARY MARCH j 1st QUARTER TOTAL
{
FISSION GASES
.j Xe-138 Ci !
f Xe-135m Ci !
l Kr-87 Ci !
Kr-88
! Ci !
Kr-85m Ci !
3.62E-04 l
Kr-85 Ci !
3.61E-04 1.41E-06 Xe-135 1 Ci 1.03E+00 t
1.03E+00 1
! Ci i
]
TOTAL Ci 1.03E+00 f
1.41E-06 1.03E+00 IODINES I-131 Ci 1.92E-04 1 24E-04 2.41E-06 3.18E-04
+
1.52E-03 I-133 i Ci 1.03E-03 4.93E-04 i
1.20E-03
- l I-135 Ci 1.20E-03 4
TOTAL C1 2.42E-03 6.17E-04 2.41E-06 3.04E-03 PARTICULATES l
Sr-89 1 ci !
6.89E-05 4.60E-05 1.30E-05 1.29E-04 l
! Ci !
4.83E-07 4.73E-07 1.38E-07 1.09E-06 i
Cr-51
! Ci 2.31E-04 1.77E-04 4.08E-04 l
3.87E-05 i
Mn-54 Ci 1.98E-05 1.89E-05 l
Co-58 Ci l
}
l Fe-59 Ci Co-60 C1 1.08E-05 2.94E-05 t
5.74E-05 9.76E-05
?
i tr-95 Ci
]
Nb-95 Ci j
Ru-103 Ci !
4 Aa-110m l
Ci !
j t
Sb-124 Ci i
l I-131 Ci Cs-134 Ci i
j f
Cs-136 Ci Ce-137 Ci 2.82E-06 2.56E-05 3.43E-08 2.85E-05 I-Ba-140 Ci !
5.33E-05 5.33E-05 r
5.33E-05 La-140 Ci 5.33E-05
}
Ce-141 Ci t
l Ce-144 Ci !
2n-65 Ci !
f t
Ba-133
! Ci !
Sb-125 Ci !
f Fe-55 Ci i 2.09E-04 2.23E-04 3.65E-03 4.10E-03 l
TOTAL Ci !
6.50E-04 1
3.43E-04 3.90E-03 4.91E-03 i
The activity of this nuclide is less than the LLD listed on the appropriate table.
l i
i j
(1:\\wk-Proc \\p1ntmgr\\gfs93\\0050.93) 17 i
e i
i I
}
DRESDEN NUCLEAR POWER STATION UNITS 2 and 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPCRT April ___ Through June 1993 D2/3 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 SEMI-ELEVATED RELEASES 50-249 XX ELEVATED RELEASES CONTINUOUS MODE NUCLIDES RELEASED jUNITj APRIL j
MAY j
JUNE l2ndQUARTERTL FISSION CASES Xe-138 Ci Xe-135m Ci a
1 1.34E+00 1.34E+00 Kr-87 Ci Kr-88 Ci Kr-85m Ci 2.39E-04 2.47E-04 4.86E-04 Kr-85 Ci Xe-135 Ci 4.10E+00 4.30E-01 1.45E+00 5.98E+00 Xe-133 Ci TOTAL Ci 4.10E+00 4.30E-01 2.79E+00 7.32E+00 IODINES I-131 Ci !
4.12E-05 7.30E-05 1.14E-04 I-133 Ci 1.41E-05 1
2.67E-04 t
4.56E-04 7.37E-04 I-135 Ci TOTAL Ci 1.41E-05 3.08E-04 5.29E-04 8.53E-04 PARTICULATES Sr-89 Ci Sr-90 Ci Cr-51 Ci Mn-54 Ci 1.04E-05 6.51E-06 1.69E-05 Co-58 Ci Fe-59 Ci Co-60 Ci !
1 3.27E-05 3.27E-05 Zr-95 Ci !
Nb-95
! Ci !
Ru-103
! Ci !
Ao-110m Ci !
Sb-124 Ci !
I-131 Ci !
Cs-134 Ci !
Cs-136 Ci !
Co-137 Ci !
6.98E-06 1.36E-05 2.06E-05 Ba-140 Ci !
La-140 Ci !
Ce-141 Ci !
Ce-144 Ci !
Zn-65 Ci Ba-133 Ci Sb-125 Ci Fe-55 t Ci 6.38E-03 t
6.79E-03 6.54E-03 1.97E-02 TOTAL
! Ci 6.38E-03 6.81E-03 6.59E-03 1.98E-02 The activity of this nuclide is less than the LLD listed on the appropriate table.
(1:\\wk-Proc \\pintmgr\\gfs93\\0050.93) 18 l
m-.
ij 4
(
DRESDEN NUCLEAR POWER STATION I
UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l
s January Through June 1993 i
D2/3 Rx Buildina Vent GASEOUS EFFLUENTS t
GROUND LEVEL RELEASES Docket Numbers: 50-237 l
XX SEMI-ELEVATED RELEASES 50-249
)
J i
ELEVATF.D RELEASES l
}
CONTINUOUS MODE BATCH MODE i
WUCLIDES RELEASED jUNIT:
1st QUARTER l
2nd QUARTER 1st QUARTER l 2nd QUARTER
)
FISSION GASES !
Xe-138 Ci Xe-135m Ci 1
t I
Kr-87 Ci l
Kr-88 Ci t
t Kr-85m Ci Kr-85 Ci Xe-135 Ci 1
l l
Xe-133 Ci TOTAL Ci NONE NONE IODINES f
I-131 Ci 2.60E-05 1.81E-05 I-133 Ci 1.05E-04 1.99E-04 l
I-135 t Ci TOTAL Ci 1.31E-04 2.17E-04 MONE NONE i
PARTICULATES i
i j
Sr-89
! Ci !
3.44E-07 Sr-90
! Ci !
4.10E-07 t
[
a Cr-51 i Ci !
2.24E-04 4.34E-05 t
l 3
! Ci !
7.71E-04 7.65E-04 l
Co-58 Ci !
1.05E-04 3.13E-05 1
Fe-59 Ci 5.92E-05 Co-60 Ci 3.62E-03 2.44E-03 r
Zr-95 Ci Nb-95 Ci !
I
)
Ru-103 Ci !
Aa-110m Ci !
i Sb-124 Ci !
1 I-131 Ci i Cs-134 Ci !
j Cs-136 Ci Cs-137 Ci 6.24E-05 2
Ba-140 Ci La-140 Ci Ce-141 Ci Ce-144 Ci En-65 Ci a
Ba-133 Ci 7.68E-05 x
Mo-99 Ci Sb-125 Ci a
Fe-55 Ci 4.55E-03 9.99E-04 1
TOTAL Ci 9.63E-03 4.28E-03 None None The activity of this nuclide is less than the LLD listed on the appropriate table.
I (lt\\wk-Proc \\pintmgr\\gfs93\\0050.93) 19 I
9 i'
1
e i
l
+
4 DRESDEN NUCLEAR POWER STATION UNITS 2 and 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through March 199_3
]
3 I
D2/3 Rx Buildino Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 XX SEMI-ELEVATED RELEASES 50-249 l
l f
ELEVATED RELEASES CONTINUOUS MODE DATCH MODE i
NUCLIDES RELEASED UNIT l JANUARY l
FEBRUARY MARCH
, M QUARTER I
FISSION GASES Xe-138 Ci !
i Xe-135m Ci !
1 Kr-87 Ci 1 Kr-88 Ci Kr-85m Ci 1
Kr-85 Ci Xe-135 Ci Xe-133 Ci TOTAL Ci f
IODINES I-131 Ci 1.50E-05 9.44E-06 1.55E-06 2.60E-05 1.05E-04 I-133 Ci 7.72E-05 2.82E-05 I-135 Ci TOTAL Ci 9.22E-05 3.76E-05 1.55E-06 1.31E-04 PARTICULATES 1.9BE-07 1.46E-07 3.44E-07 Sr-89 Ci Sr-90 Ci 7.90E-08 2.16E-07 1.15E 4.10E-07 Cr-51 Ci 8.12E-05 1.43E-04 2.24E-04 Mn-54 C1 1.78E-04 1.66E-04 4.27E-04 7.71E-04 Co-58 Ci 7.21E-05 1.68E-05 1.64E-05 1.05E-04 Fe-59 Ci 5.34E-05 5.75E-06 5.92E-05
- j Co-60 Ci 6.47E-04 3.73E-04 2.60E-03 3.62E-03 i
Zr-95 Ci Nb-95 Ci Ru-103 Ci t
Aa-110m Ci Sb-124 Ci I-131 Ci Cs-134 Ci 1
Cs-136
! Ci Cs-137
! Ci 1.58E-05 t
4.46E-05 6.24E-05 l
Ba-140 Ci j
La-140 Ci a
Ce-141 Ci !
t Ce-144 f Ci !
_t Zn-65 Ci !
7.6BE-05 7.68E-05 Ba-133 C1 f
1.40E-03 1.74E-03 1.41E-03 4.55E-03 TOTAL Ci !
2.30E-03 2.45E-03 4.72E-03 9.47E-03
- The activity of this nuclide is less than the LLD listed on the I
appropriate table.
J (1:\\wk-Proc \\pintegr\\gfs93\\0050.93) 20 i
.e.,-
v,.,
i
?
I l
DRESDEN NUCLEAR POWER STATION UNITS 2 and 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT
__Ap_ril__ Through June 1993 j
D 2/3 Rx Buildina Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 l
XX SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONTINUOUS MODE l
NUCLIDES RELEASED l UNIT APRIL l
MAY j
JUNE 2nd QUARTER TOTAL FISSION GASES 1
Xe-138 Ci !
l Xe-135m Ci i Kr-87 Ci !
Kr-88 Ci !
Kr-85m Ci Kr-85 Ci Xe-135 Ci j
Xe-133 Ci TOTAL Ci i
t i
IODINES i
l I-131 Ci 5.68E-06 1.24E-05 1.81E-05 l
I-133 Ci 2.32E-05 5.41E-05 1.22E-04 1.99E-04 j
I-135 Ci TOTAL Ci 2.32E-05 5.9BE-05 1.34E-04 2.17E-04 PARTICULATES 1
l Sr-89 Ci 1
j Sr-90 Ci
?
Cr-51 Ci a
4.34E-05 4.34E-05 l
Mn-54 Ci 3.34E-04 1.96E-04 2.35E-04 7.65E-04 Co-58 Ci 3.13E-05 3.13E-05 t
Fe-59 Ci Co-60 Ci 9.85E-04 9.55E-04 5.03E-04 2.44E-03 Zr-95 Ci t
i l
4 Nb-95 Ci d
Ru-103 Ci i.
Aa-110m Ci Sb-124 Ci i
4 1-131 Ci I
Cs-134 Ci Cs-136 Ci i
Cs-137 Ci t
Ba-140 Ci t
l La-140 Ci 3
Ce-141 Ci l
Ce-144 Ci Zn-65 Ci Ba-133 Ci Mo-99 Ci Sb-125 Ci !
Fe-55 Ci !
3.19E-04 3.36E-04 3.44E-04 9.99E-04 TOTAL Ci !
1.67E-03 1.49E-03 1.13E-03 i
4.28E-03 1
- The activity of this nuclide is less than the LLD listed on the appropriate table.
l
~
(1:\\wk-Proc \\pintmgr\\gfs93\\0050.93) 21 1
i i
i 7
I
l
~
DRESDEN NUCLEAR POWER STATION 3
UNITS 1, 2, and 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1993 LIQUID EFFLUENTS I
SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237 4
50-249 i
EST. TOTAL UNITS Ist QUARTER 2nd QUARTER ERROR,%
A.
FISSION AND ACTIVATION PRODUCTS Ci 8.80E-02 4.04E-02 10.6 no ine tritium, gases, alpha)
- 2. Average Diluted Conc. During Period uci/mL 3.37E-08 3.57E-09
- 3. Percent of Applicable Limit j
i B.
- 1. Total Release ci 4.38E+00 4.67E+00 11.4 l
l i
- 2. Average Diluted Conc. During Period uCi/mL 1.68E-06 4.13E-07 l i
l l
]
- 3. Percent of Applicable Limit 3-C.
DISSOLVED AND ENTRAINED GASES l
j
- 1. Total Release Ci
<LLD
< LLD 5.58
- 2. Average Diluted Conc. During Period uCi/mL
<LLD
< LLD--
- 3. Percent of Applicable Limit l
l D.
GROSS ALPHA RADIOACTIVITY l
- 1. Total Release l
Ci l < LLD l
< LLD l
15.1 i
j E.
VOLUME OF WASTE RELEASED (prior to dilution) j Liters j 7.42E+08 l9.49E+06 j 5.00.
F.
VOLUME OF DILUTION WATER USED DURING PERIOD j
liters l 1.87E+09 l.l.13E+10 l 5.00 l
- The information is contained in the Radiological Impact on Man section of this report. Total liquid release data is provided which includes fission and activation products, tritium, and dissolved and entrained gases.
I I
-(1:\\wk-Proc \\pintmgr\\gfs93\\0033.93)
I DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1992 TABLE OF LOWER LIMITS OF DETECTABILITY Docket Numbers: 50-10 FOR LIQUID EFFLUENTS 50-237 50-249 NUCLIDE LLD (uCi/mL)
Sr-89 2.00E-08 Sr-90 9.00E-09 Mn-54 5.50E-08 Co-58 4.20E-08 Fe-59 9.30E-08 Co-60 1.23E-07 Zn-65 1.20E-07 Sb-124 4.50E-08 I-131 4.50E-08
.Cs-134 4.60E-08 cc-137 7.20E-08 Ba-140 2.20E-07 La-J40 4.60E-08 Ce-141 6.90E-08 Xe-133 1.20E-07 Xer135 4.20E-08 pr-51 3.70E-07 Fe-55 7.00E-08 Cs-138 3.10E-07 H-3 2.00E-07 Gross Alpha 7.00E-09 Zr-95
- 9. 8 0E -08 Kr-87 1.50E-07 Kr-88 1.70E-07 I-135 2.10E-07 I-132 6.70E-08 Aa-110m 5.90E-08 Ba-133 6.00E-08 Ce-144 3.10E-07 Cs-136 5.50E-08 I-133 6.30E-08 I-134 1.50E-07 Kr-85 1.10E-05 Mo-99 3.90E-08 Nb-95 5.00E-08 No-239 1.50E-07 Ru-103 5.30E-08 Sb-125 1.50E-07 Xe-131m 1.80E-06 Xe-133m 3.60E-07 Xe-138 4.10E-06 (1:\\wk-Proc \\pintmgr\\gfs93\\0050.93) 23 e
l l
DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 19133 Radwaste LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 1.
Number of Batch Releases: 66 50-249 2.
Total Time Period for Batch Releases:
2.33E+04 min 3.
Maximum Time Period for a Batch Release:
4.43E+02 min 4.
Average Time Period for Batch Releases:
3.53E+02 min 5.
Minimum Time Period for a Batch Release:
2.3E+00 min 6.
Average Stream Flow During Periods of Release of Effluent into a Flowing Stream:
5.64E+05 L/ min CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED
' UNIT l 1st QUARTER l
2nd QUARTER 1st QUARTER 2nd QUARTER Sr-89 Ci !
Sr-90 Ci !
2.61E-05 Mn-54 Ci i 1.46E-03 6.42E-03 Co-58
! Ci 3.90E-05 Fe-59
! Ci co-60 Ci !
6.35E-03 1.83E-02 2n-65 Ci !
t t
)
Ru-103 Ci 4.88E-06 Ao-110m Ci Sb-124 Ci !
I-131 Ci Cs-134 Ci Cs-137 Ci 1.26E-03 1
4.87E-03 Ba-140 Ci La-140 t Ci 1
Ce-141
! Ci Cs-138
! ci Fe-55 Ci 4.76E-03 1.03E-02 Zr-95 Ci
]
I - 132
! Ci l
l I - 134 Ci Bi-214 Ci 1.09E-02 (above)
Total For Period Ci NONE NONE 1.39E-02 4.02E-02 Xe-133 l
Ci Ci Xe-135 Kr-88
! Ci !
The activity of this nuclide is less than the LLD listed on the appropriate table.
M 4
s I
I (1:\\wk-Proc \\pintmgr\\gfs93\\0050.93) 24 l
1
~
i I
r DRESDEN NUCLEAR POWER STATION
[
UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through March 1993 Padwaste LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 I
50-249 i
1 BATCH MODE JANUARY l
FEBRUARY MARCH let QUARTER TOTAL l
NUCLIDES RELEASED jUNIT t
Sr-89 i Ci Sr-90
! Ci 1.42E-05 1.19E-05 2.61E-05 l
! C1 1.08E-04 7.62E-05 1.28E-03 1
1.46E-03 i
Co-58 i ci Fe-59
! Ci !
l Co-60 t Ci !
4.22E-04 5.14E-04 5.41E-03 t
6.35E-03 i
t Zn-65
! Ci !
4.BBE-06 4.88E-06 Ru-103
! Ci t
e l
Aa-110m
! Ci f
l Sb-124
! Ci f
I-131 i ci !
1 f
l Cs-134
! Ci !
Cs-137 i Ci t 9.15E-05 t
1.50E-04 f
1.02E-03 t
1.26E-03 l
Ba-140 Cf f i
La-140 Ci !
1 Cs-138 Ci !
t l
Fe-55 Ci !
6.00E-05 t
6.56E-04 1
4.04E-03 4.76E-03 i
4 I-132 Ci t
1
.l I-134
! Ci t
Bi-214
! Ci 1.09E-05 1
1.09E-05 l
4 i
m i
i i
i j
(above) i Total For Period l Ci !
6.82E-04 1.41E-03 1.18E-02 1.39E-02 j
l Xe-133 Ci !
xe-135 Ci !
f a
3, s
The activity of this nuclide is less than the LLD listed on the appropriate table.
j There were no Radwaste liquid discharges in July, 1992.
+
i 1
l T
l 3
i i
e i
l
\\
(1:\\wk-Proc \\pintmgr\\gfs93\\0050.93) 25 j
r
i I
a DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT.AND WASTE DISPOSAL SEMIANNUAL REPORT t
April Through June 1993 l
Radwaste LIQUID EFFLUENTS Docket Numbers: 50-10 l
50-237 I
50-249 i
i BATCH MODE NUCLIDES RELEASED,UNITj APRIL j
FXI l
JUNE 2nd QUARTER TOTAL 3
r i
Sr-89 Ci !
t t
1 Sr-90 t Ci !
t
{
l Mn-54
! Ci t B.65E-04 1
1.97E-03 1
3.58E-03 i
6.42E-03 t
Co-58
! Ci j
=
i Fe-59
! Ci 1
3.90E-05 3.90E-05 l
Co-60 t Ci 3.21E-03 t
5.37E-03 t
9.76E-03 1
1.83E-02 f
t t
Zn-65 t Ci !
Sb-124 t Ci !
t 1
! Ci l
f Cs-134
! Ci Cs-137
! Ci 1.48E-03 i
1.74E-03 1.65E-03 1
4.87E-03 i
t Ba-140 t Ci a
t i
La-140 1 Ci !
t 4
ce-141 i ci t t
Cs-138 i ci !
Fe-55 t Ci 1 3.45E-03 3.15E-03 1
3.72E-03 1
1.06E '
1 I-132 i ci i 1
t Ci i t
t j
! Ci (above)
Total For Period i Ci 9.01E-03 1.23E-02 1.87E-02 4.02E-02
[
Xe-133 i Ci j
Xe-135 l Ci The activity of this nuclide is less than the LLD listed on the appropriate table.
s 1
J l
i e
4 i
1 e
4 E
i 4
l (1:\\wk-Proc \\pintmgr\\gfs93\\0050.93) 26 i
f k
i
.. - -. +,
r i
4 I
DRESCEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1992 l
CCSW LIQUID EFFLUENTS Docket Numbers: 50-237
{
50-249 1.
Number of Batch Releases:
18 2.
Total Time Period for Batch Releases:
2.23E+01 min 3.
Maximum Time Period for a Batch Release:
1.24E+00 min 4.
Average Time Period for Batch Releases:
1.24E+00 min l
5.
Minimum Time Period for a Batch Releace:
1.24E+00 min 6.
Average Stream Flow During Periods of Release of Effluent into a Flowing Stream:
2.05E+06 L/ min CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED lUNITj lst QUARTER l
And QUARTER j lsi QUARTER l
2nd QUARTER l
r Sr-89 i Ci !
Sr-90 t Ci !
t t
Mn-54 Ci 1
1 f
Co-58 Ci Fe-59
! Ci Co-60 Ci i t
8.04E-07 9.17E-06 l
'Zn-65 Ci !
t Sb-122 1 Ci t
l Sb-124 Ci i
l t
I-131 Ci I-132 Ci l
I-135 Ci i
[
Cs-134 Ci 4.95E-07 6.63E-07 Cs-137 Ci 4.37E-06 1.56E-04 i
1 Ba-140 Ci La-140 t Ci !
f Cs-138 i C; i Fe-55 t Ci i Ba-133
! Ci !
t 1.82E-06 ci t
t (above) l l
Total For Period Ci NONE l
NONE t
5.67E-06 1.68E-04 Xe-133 1 Ci !
t l
Xe-135 t Ci !
t The activity of this nuclide is less than the LLD listed on the appropriate table.
l t
d i
I J
i f
i.
5
+
a i
I
{
(1:\\wk-Proc \\pintmgr\\gfs93\\0050.93) 27 1
J i
i l
4 1
]
i 2
DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT
)
January Through March 1993 l
3 CCSW LIQUID EFFLUENTS Decket Numbers: 50-237 50-249 i
BATCH EODE f
WUCLIDES RELEASID QUNITL JANUARY j
FEBRUARY l
MARCH l M QUARTER TOTAL j
i Sr-89 Ci f
l Sr-90 Ci !
f 1
i
]
Mn-54 Ci !
t f
f Co-58
! Ci !
f Fe-59
! Ci !
f 8.04E-07 !
8.04E-07 l
Co-60 Ci !
1 Zn-65 Ci j
l Sb-122 Ci t
j f
Sb-124
! Ci f
d I-131
! Ci f
t a
I-132 Ci a
t t
l 1
I-135 Ci t
f 4.95E-07 1 4.95E-07
{
t Cs-134 Ci !
3.92E-06 4.37E-06 Cs-137 Ci !
4.52E-07 i
f i
m Ba-140 Ci !
j La-140
! Ci !
i Cs-138 Ci !
Fe-55 Ci !
f Ci I
4 1 Ci I
(above) l l
5.22E-Ofi l 5.67E-06 J
Total For Period i Ci 4.52E-07 1
1 t
l 1
Xe-133 t Ci !
i l
Xe-135
! Ci !
i I
l The activity of this nuclide is less than the LLD listed on the appropriate table.
(
i i
t i
5 a
4 4
J i
i a
F 9
1 l
l 1
?
5 h
i l
)
t I
J (1:\\wk-Proc \\pintegr\\gfs93\\00FD.93) 28 1
i
,,m
DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT April Through June 1992 CCSW LIQUID EFFLUENTS Docket Numbers: 50-237 50-249 BATCH MODE NUCLIDES RELEASED lUNITj APRIL l
MAY l
JUNE j
2nd QUARTER TOTAL Sr-89 i Ci i 1
=
Sr-90 t Ci t f
t a
Mn-54 i ci !
f t
t Co-58
! Ci Fe-59 1 Ci Co-60
! Ci !
1.38E-06 l
3.51E-6 l
4.28E-06 9.17E-06 Zn-65
! Ci f
t t
sb-122 Ci 1
=
=
t Sb-124 Ci I-131 Ci t
?
I-132 t Ci t
I-135 t Ci t
1 6.63E-07 l
..6.63E-07 Ce-134 t ci
_i Cs-137
! Ci 2.11E-06 t
4.31E-05 1
1.11E-04 !
1.56E-04 Ba-140 t Ci t
La-140
! Ci !
t Cs-138 i ci f
Fe-55 Ci I.82E-06 Ba-133 Ci 1.92E-06 Ci l
Ci (above) l Total For Period Ci 3.49E-06 4.84E-05 j
1.16E-04 1.68E-04 t
Xe-133 Ci Xe-135 Ci !
t i
The activity of this nuclide is less than the LLD listed on the appropriate table.
l
.1 l
l 1
1 (1:\\wk-Proc \\pintmgr\\gfs93\\0050.93) 29
l 1
DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 i
l.
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l
l i
January Through June-1993 i
Docket Numbers: 50-10 J
4 50-237 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 50-249
)
Est Tot.
i A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)
Error.%
- 1. Type of Waste
' Unit: 6-month periodQ q
m3 1.86E+02 a.
Spent resins, filter sludges, evaporator bottoms, etc.
y Ci 4.45E+02 12.4 l e
m
.10E+03 b.
Dry comprescible waste, contaminated equip., etc.
Ci 1.36E+01
- 16.6 i
m3 6.55E+00 1
c.
Irradiated components, control rods, etc.
, Ci l 1.89E+04 16.6 l
t m3 None d.
Other (describe) l' CL None
\\
- 2. Estimate of Major Nuclide Compocition (by type of waste) l Ci i
s.
Co-60 l
29.2
! 1.30E+02 i
Fe-55 t
58.7
! 2.61E+02 r
i Mn-54 6.40 2.85E+01 e
1 Cs-137 i
3.98 1.77E+01 I
b.
Co-60 l
20.8 2.83E+00 Fe-55 l
63.2 8.60E+00 Mn-54 10.2 1.39E+00 Ni-59 1.30 1.77E-01 s
]
Ni-63 f
1.01 1.37E-01 l
l Cs-137 1
2.96 4.03E-01 l
c.
Co-60 f
32.3 6.11E+03 l
Mn-54 l'
2.58 4.87E+02
{
Fe-55 1
58.2 1.10E+04 l
3 Ni-63 6.51 1.23E+03 j
l
- 3. Solid Waste Disposition Hy?!BER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION I
49 Motor freight (exclusive use only)
CNSI, Barnwell, SC 11 Motor freight (exclusive use only)
Quadrex, Oak Ridge, TN
]
3 Mator freight (exclusive use only)
CNSI, Channahon, IL j
7 1
4 Motor freight (exclusive use only)
SEG, Oak Ridge, TN B.
IRRADIATED FUEL SHIPMENTS (Disposition) l
}
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION l
None n
1 4
l 1
I i
i l
l I
d i
i (1:\\wk-Proc \\pintmgr\\gfs93\\0050.93) 30
-+
r w
--w
.i
.t I
-l I
1 DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 E1 FLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I
i January Through June 1923 l
l ABNORMAL RELEASES Ei A.
LIQUID
'i
)
1.
Number of Releases:
1 i
i 2.
Total Activity Released:
7.41E-02 Ci B.
GASEOUS 1.
Number of Releases:
O 2.
Total Activity Released:
0 TOTAL 1
l 1
I A.
1.
On February 18, a routine Service Water Sample from Unit 2 showed activity with a j
proportional counter.
The concurrent Camma spectroscopy showed no activity.
All I
activity was assumed to be Sr-90 at 101 pCi/1. Water flow was calculated at 202,000 l
4 gpm.
The activity was assumed to be present between samples with activity less than l
hrs).
The resulting activity is 1
LLD '
Sr-90 7.41E-02Ci l
i
+
i i
i I
l l
I i
1 d
l t
i 1
i I
i (1:\\wk-Proc \\pintmgr\\gfs93\\0050.93) 31
.u DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 RADIOLOGICAL IMPACT ON MAN l
-I i
l l
1 I
t i
i I
i t
i (1:\\wk-Proc \\pintmgr\\gfs93\\0050.93) 32
DRESDEN STATION UNIT ONE ACTUAL 1993 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 l
INFANT RECEPTOR l
IST 2ND 3RD 4TH l
TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC l
GAMMA AIR 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
(MRAD)
(
)
(
)
(
)
(
)
(
)
l BETA AIR 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t
(MRAD)
(
)
(
)
(
)
(
)
(
)
l TOT. BODY 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MREM)
(
)
(
)
(
)
(
)
(
)
l SKIN 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MREM)
(
)
(
)
(
)
(
)
(
)
j ORGAN 6.12E-05 1.29E-06 0.00E+00 0.00E+00 6.23E-05 (MREM)
(SSE )
(E
)
(
)
(
)
(SSE )
i LIVER LUNG LIVER i
)
THIS IS A REPORT FOR THE CALENDAR YEAR 1993 i
i COMPLIANCE STATUS - 10CFR 50 APP. I INFANT RECEPTOR j
% OF APP I.
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 f
BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 l
TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 l
1 SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 i
LIVER LUNG LIVER l
]
RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 i
ODCM DATABASE VERSION 0.1 APRIL 1993 4
9 i
i 1
r
DRESDEN STATION UNIT ONE ACTUAL 1993 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 CHILD RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MRAD)
(
)
(
)
(
)
(
)
(
)
BETA AIR 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MRAD)
(
)
(
)
(
)
(
)
(
)
TOT. BODY 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MREM)
(
)
(
)
(
)
(
)
(
)
SKIN 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MREM)
(
)
(
)
(
)
(
)
(
)
ORGAN 5.56E-05 1.78E-05 0.00E+00 0.00E+00 7.34E-05 (MREM)
(SSE )
(SSE )
(
)
(
)
(SSE )
BONE BONE BONE THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 10CFR 50 APP. I CHILD RECEPTOR
% OF APP I.
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 BONE BONE BONE RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993
i
'a DRESDEN STATION UNIT ONE ACTUAL 1993 i
MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES I
PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 TEENAGER RECEPTOR N
1ST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL i
JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I
(MRAD)
(
)
(
)
(
)
(
)
(
)
BETA AIR 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MRAD)
(
)
(
)
(
)
(
)
(
)
{
TOT. BODY 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
(MREM)
(
)
(
)
(
)
(
)
(
)
SKIN 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
(MREM)
(
)
(
)
(
)
(
)
(
)
ORGAN 5.26E-05 1.08E-05 0.00E+00 0.00E+00 6.24E-05 l
(MREM)
(SSE )
(SSE )
(
)
(
)
(SSE )
l LIVER BONE BONE I
THIS IS A REPORT FOR THE CALENDAR YEAR 1993 l
)
i COMPLIANCE STATUS - 10CFR 50 APP.-I i
TEENAGER RECEPTOR l
J i
[
% OF APP I.
t j
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.05 i
TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 i
i f
1 LIVER BONE BONE 3
RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 t
ODCM SOFTWARE VERSION 0.1 APRIL 1993 i
ODCM DATABASE VERSION 0.1 APRIL 1993 i
I I
4 I
l a
i i
l
l DRESDEN STATION UNIT ONE ACTUAL 1993 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 l
ADULT RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL j
JAN-MAR APR-JUN JUL-SEP OCT-DEC i
i GAMMA AIR 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
(MRAD)
(
)
(
)
(
)
(
)
(
)
{
BETA AIR 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MRAD)
(
)
(
)
(
)
(
)
(
)
i i
TOT. BODY 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MREM)
(
)
(
)
(
)
(
)
(
)
l 1
SKIN 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
(MREM)
(
)
(
)
(
)
(
)
(
)
ORGAN 5.11E-05 8.67E-06 0.00E+00 0.00E+00 5.91E-05 (MREM)
(SSE )
(SSE )
(
)
(
)
(SSE )
LIVER BONE BONE THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 10CFR 50 APP. I j
ADULT RECEPTOR
% OF APP I.
l QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I i
2 GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 l
BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 i
TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 i
SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00
)
]
LIVER BONE BONE l
RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 7l ODCM DATABASE VERSION 0.1 APRIL 1993 i
t i
j
DRESDEN STATION UNIT TWO
[
I ACTUAL 1993 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES i
PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 INFANT RECEPTOR i
1ST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 1.24E-06 6.83E-06 5.02E-05 0.00E+00 5.83E-05 (MRAD)
(N
)
(N
)
(N
)
(
)
(N
)
BETA AIR 2.32E-07 1.39E-06 1.62E-04 0.00E+00 1.63E-04 (MRAD)
(E
)
(E
)
(N
)
(
)
(N
)
TOT. BODY 8.21E-07 4.57E-06 2.79E-05 0.00E+00 3.33E-05' (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
l SKIN 1.13E-06 6.50E-06 8.63E-05 0.00E+00 9.40E-05
)
(MREM)
(N
)
(N
)
(N
)
(
)
(N
)
ORGAN 1.78E-03 2.77E-03 3.53E-04 0.00E+00 4.87E-03 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
LUNG LUNG THYROID LUNG THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 10CFR 50 APP. I l
INFANT RECEPTOR l
% OF APP I.-------------
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I j GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 ;
BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 !
TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ;
ORGAN (MREM) 7.5 0.02 0.04 0.00 0.00 15.0 0.03 !
LUNG LUNG THYROID LUNG RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 i
ODCM SOFTWARE VERSION 0.1 APRIL 1993 i
ODCM DATABASE VERSION 0.1 APRIL 1993
DRESDEN STATION UNIT TWO ACTUAL 1993 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 CHILD RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 1.24E-06 6.83E-06 5.02E-05 0.00E+00
-5.83E-05 (MRAD)
(N
)
(N
)
(N
)
(
)
(N
)
BETA AIR 2.32E-07 1.39E-06 1.62E-04 0.00E+00 1.63E-04 (MRAD)
(E
)
(E
)
(N
)
(
)
(N
)
TOT. BODY 8.21E-07 4.57E-06 2.79E-05 0.00E+00 3.33E-05 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
SKIN 1.13E-06 6.50E-06 8.63E-05 0.00E+00 9.40E-05 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
ORGAN 1.80E-03 2.87E-03 3.93E-04 0.00E+00 4.99E-03 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
LUNG LUNG THYROID LUNG THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 10CFR 50 APP. I CHILD RECEPTOR
% OF APP I.
QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00.
SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.02 0.04 0.01 0.00 15.0 0.03 LUNG LUNG THYROID LUNG RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993
. =.-_
l DRESDEN STATION UNIT TWO f
i ACTUAL 1993 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 l
TEENAGER RECEPTOR l
IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL l
JAN-MAR APR-JUN JUL-SEP OCT-DEC l
GAMMA AIR 1.24E-06 6.83E-06 5.02E-05 0.00E+00
.5.83E-05 (MRAD)
(N
)
(N
)
(N
)
(
)
(N
)
l BETA AIR 2.32E-07 1.39E-06 1.62E-04 0.00E+00 1.63E-04 (MRAD)
(E
)
(E
)
(N
)
(
)
(N
)
j TOT. BODY 8.21E-07 4.57E-06 2.79E-05 0.00E+00 3.33E-05 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
SKIN 1.13E-06 6.50E-06 8.63E-05 0.00E+00 9.40E-05 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
ORGAN 1.80E-03 2.85E-03 3.65E-04 0.00E+00 4.98E-03 i
(MREM)
(N
)
(N
)
(N
)
(
)
(N
)
l LUNG LUNG THYROID LUNG THIS IS A REPORT FOR THE CALENDAR YEAR 1993 i
l COMPLIANCE STATUS - 10CFR 50 APP. I TEENAGER RECEPTOR
% OF APP I.
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I -!
GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 ;
BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 !
SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 l ORGAN (MREM) 7.5 0.02 0.04 0.00 0.00 15.0 0.03 ;
3 LUNG LUNG THYROID LUNG f
RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 l
4 t
ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 j
l
. ~. _
DRESDEN STATION UNIT TWO j
l ACTUAL 1993 i
MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 ADULT RECEPTOR i
l i
IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL l
1-MAR APR-JUN JUL-SEP OCT-DEC l
o i
GAMMA AIR 1.24E-06 6.83E-06 5.02E-05 0.00E+00 5.83E-05 (MRAD)
(N
)
(N
)
(N
)
(
)
(N
)
i BETA AIR 2.32E-07 1.39E-06 1.62E-04 0.00E+00 1.63E-04 (MRAD)
(E
)
(E
)
(N
)
(
)
(N
)
l TOT. BODY 8.21E-07 4.57E-06 2.79E-05 0.00E+00 3.33E-05 i
(MREM)
(N
)
(N
)
(N
)
(
)
(N
)
SKIN 1.13E-06 6.50E-06 8.63E-05 0.00E+00 9.40E-05 (MREM)
(N
)
(N
)
(N
)
(
)
ORGAN 1.79E-03 2.82E-03 3.70E-04 0.00E+00_
(N
)
l 4.94E-03 (MREM)
(N
)
(N
)
(N
)
(
)
(N-
)
LUNG GI LLI THYROID GI LLI THIS IS A REPORT FOR THE CALENDAR YEAR 1993 i
l l
1 i
i COMPLIANCE STATUS - 10CFR 50 APP. I ADULT RECEPTOR I
____________ g op App I, QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I t GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 !
BETA AIR (MRAD) 10.0 0.00 0.00_
0.00 0.00 20.0 0.00 TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 i ORGAN (MREM) 7.5 0.02 0.04 0.00 0.00 15.0 0.03 LUNG GI_LLI THYROID GI_LLI i
RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 I
4 i
I l
6 m
,n
.--0
DRESDEN STATION UNIT THREE ACTUAL 1993 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 i
INFANT RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNGAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 5.21E-06 6.01E-05 5.73E-05 0.00E+00 1.23E-04 l
(MRAD)
(N
)
(N
)
(N
)
(
)
(N
)
BETA AIR 9.74E-07 1.18E-05 1.63E-04 0.00E+00 1.75E-04 i
(MRAD)
(E
)
(E
)
(N
)
(
)
(N
)
TOT. BODY 3.45E-06 4.00E-05 3.26E-05 0.00E+00 7.61E-05 l
(MREM)
(N
)
(N
)
(N
)
(
)
(N
)
SKIN 4.76E-06 5.62E-05 9.29E-05 0.00E+00 1.54E-04 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
ORGAN 1.60E-02 9.27E-03 1.93E-03 0.00E+00 2.70E-02 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
l LUNG THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 1993 1
i COMPLIANCE STATUS - 10CFR 50 APP. I INFANT RECEPTOR l
% OF APP I.
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I I
l GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 i
BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 i
l SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 i
ORGAN (MREM) 7.5 0.21 0.12 0.03 0.00 15.0 0.18 l
l LUNG THYROID THYROID THYROID i
1 RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 I
l I
l
)
l l
DRESDEN STATION UNIT THREE ACTUAL 1993 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 CHILD RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER
-QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 5.21E-06 6.01E-05 5.73E-05 0.00E+00 1.23E-04 (MRAD)
(N
)
(N
)
(N
)
(
)
U;l
)
BETA AIR 9.74E-07 1.18E-05 1.63E-04 0.00E+00 1.75E-64 (MRAD)
(E
)
(E
)
(N
)
(
)
(N
)
TOT. BODY 3.45E-06 4.00E-05 3.26E-05 0.00E+00 7.61E-05 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
SKIN 4.76E-06 5.62E-05 9.29E-05 0.00E+00 1.54E-04 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
ORGAN 1.61E-02 1.06E-02 2.15E-03 0.00E+00 2.84E-02 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
LUNG GI LLI THYROID THYROID THIS IS A REPORT FOR THE CALE5DAR YEAR 1993 COMPLIANCE STATUS - 10CFR 50 APP. I CHILD RECEPTOR
% OF APP 1.
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP.
I' GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 j
BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 i
TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 l
SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.22 0.14 0.03 0.00 15.0 0.19 LUNG GI_LLI THYROID THYROID RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 i
ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993
DRESDEN STATION UNIT THREE ACTUAL 1993 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 TEENAGER RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 5.2]E-06 6.01E-05 5.73E-05 0.00E+00 1.23E-04 (MRAD)
(N
)
(N
)
(N
)
(
)
(N
)
BETA AIR 9.74E-07 1.18E-05 1.63E-04 0.00E+00 1 75E-04 (MRAD)
(E
)
(E
)
(N
)
(
)
(N
)
TOT. BODY 3.45E-06 4.00E-05 3.26E-05 C 00E+DO 7.61E-05 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
SKIN 4.76E-06 5.62E-05 9.29E-05 0.00E+00 1.54E-04 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
ORGAN 1.62E-02 1.06E-02 2.00E-03 0.00E+00 2.83E-02 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
LUNG GI LLI THYROID GI LLI THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 10CFR 50 APP. I TEENAGER RECEPTOR
% OF APP I.
QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.22 0.14 0.03 0.00 15.0 0.19 LUNG GI_LLI THYROID GI_LLI RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993
u
..u.
...a
.a an_s 1
.u-j
-s DRESDEN STATION UNIT THREE ACTUAL 1993 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES I
PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 ADULT RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL l
JAN-MAR APR-JUN JUL-SEP OCT-DEC i
GAMMA AIR 5.21E-06 6.01E-05 5.73E-05 0.00E+00 1.23E-04 (MRAD)
(N
)
(N
)
(N
)
(
)
(N
)
i BETA AIR 9.74E-07 1.18E-05 1.63E-04 0.00E+00 1.75E-04 l
(MRAD)
(E
)
(E
)
(N
)
(
)
(N
)
l TOT. BODY 3.45E-06 4.00E-05 3.26E-05 0.00E+00 7.61E-05 i
(MREM)
(H
)
(N
)
(N
)
(
)
(N
)
]
SKIN 4.76E-06 5.62E-05 9.29E-05 0.00E+00 1.54E-04 (MREM)
(N
)
(N
)
(N
)
(
)
(N
)
l ORGAN 1.60E-02 1.05E-02 2.02E-03 0.00E+00 2.82E-02 l
(MREM)
(N
)
(N
)
(N
)
(
)
(N
)
l LUNG GI LLI THYROID GI LLI i
THIS IS A REPORT FOR THE CALENDAR YEAR 1993 l
COMPLIANCE STATUS - 10CFR 50 APP. I
)
ADULT RECEPTOR
% OF APP I.
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.21 0.14 0.03 0.00 15.0 0.19 LUNG GI_LLI THYROID GI_LLI RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 4
E I
l s
DRESDEN STATION UNIT TWO ACTUAL 1993 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS
{
PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 i
INFANT RECEPTOR l
1ST 2ND 3RD 4TH l
DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL i
JAN-MAR APR-JUN JUL-SEP OCT-DEC i
TOTAL 9.35E-03 2.92E-05 3.50E-06 0.00E+00 9.39E-03 i
BODY INTERNAL 3.66E-02 6.70E-05 1.55E-05 0.00E+00 3.67E-02 i
ORGAN I
BONE LIVER LIVER BONE l
THIS IS A REPORT FOR THE CALENDAR YEAR 1993 i
COMPLIANCE STATUS - 10 CFR 50 APP. I f
% OF APP I.
I QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I l
\\
TOTAL BODY (MREM) 1.5 0.62 0.00 0.00 0.00 3.0 0.31 ~
CRIT. ORGAN (MREM) 5.0 0.73 0.00 0.00 0.00 10.0 0.37 BONE LIVER LIVER BONE RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 i
I P
i i
3 I
i
I i
s DRESDEN STATION UNIT TWO
~
1993 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM
- l PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 INFANT RECEPTOR l
IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL l
JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 9.35E-03 2.92E-05 3.50E-06 0.00E+00 9.39E-03 BODY INTERNAL 3.66E-02 6.70E-05 1.55E-05 0.00E+00 3.67E-02 ORGAN BONE LIVER LIVER BONE THIS IS A REPORT FOR THE CALENDAR YEAR 1993 I
l COMPLIANCE STATUS - 40 CFR 141 f
TYPE ANNUAL LIMIT
% OF LIMIT TOTAL 4.0 MREM 0.235 a
BODY INTERNAL 4.0 MREM 0.917 i
ORGAN BONE THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE o
COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL.
THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141.
l RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 4
l f
l i
i 1
i 1
I
[
1 t
I l
f
-t
. ~.. -
-a
~
.-s s
DRESDEN STATION UNIT TWO ACTUAL 1993 1
MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 CHILD RECEPTOR l
IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL 4
JAN-MAR APR-JUN JUL-SEP OCT-DEC j
TOTAL 1.99E-02 2.08E-04 6.20E-05 0.00E+00 2.01E-02 BODY j
INTERNAL 7.84E-02 1.23E-03 4.02E-04 0.00E+00 8.00E-02
~
ORGAN BONE BONE BONE BONE
]
THIS IS A REPORT FOR THE CALENDAR YEAR 1993 l
COMPLIANCE STATUS - 10 CFR 50 APP. I
% OF APP I.
i
=
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF I
OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I i
TOTAL BODY (MREM) 1.5 1.32 0.01 0.00 0.00 3.0 0.67 i
CRIT. ORGAN (MREM) 5.0 1.57 0.02 0.01 0.00 10.0 0.80 i
BONE BONE BONE BONE RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 i
ODCM SOFTWARE VERSION 0.1 APRIL 1993 4
ODCM DATABASE VERSION 0.1 APRIL 1993 I
i
?
I l
4 i
l t
t v--,
y
- y.,.
f DRESDEN STATION UNIT TWO
~
1993 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM
- PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 CHILD RECEPTOR IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.31E-02 3.08E-05 3.95E-06 0.00E+00 1.31E-02 BODY INTERNAL 5.14E-02 5.70E-05 1.21E-05 0.00E+00 5.14E-02 ORGAN BONE LIVER LIVER BONE THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT
% OF LIMIT l
TOTAL 4.0 MREM 0.327 BODY INTERNAL 4.0 MREM 1.286 ORGAN BONE THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL.
THESE TECHNIQUES DIFFER i
FROM THOSE DESCRIBED IN 40 CFR 141.
RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 3
3 4
DRESDEN STATION UNIT TWO
~
ACTUAL 1993 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 TEENAGER RECEPTOR IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP-OCT-DEC TOTAL 1.37E-02 4.57E-04 1.47E-04 0.00E+00 1.43E-02 BODY INTERNAL 5.50E-02 1.28E-03 4.17E-04 0.00E+00 5.63E-02 ORGAN BONE LIVER LIVER BONE THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 10 CFR 50 APP. I
% OF APP I.
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I TOTAL BODY (MREM) 1.5 0.91 0.03 0.01 0.00 3.0 0.48 CRIT. ORGAN (MREM) 5.0 1.10 0.03 0.01 0.00 10.0 0.56 BONE LIVER LIVER BONE RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993
~
ODCM DATABASE VERSION 0.1 APRIL 1993
l
-=
DRESDEN STATION UNIT TWO 1993 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 TEENAGER RECEPTOR IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 6.21E-03 1.82E-05 2.75E-06 0.00E+00 6.23E-03 BODY INTERNAL 2.51E-02 2.82E-05 5.86E-06 0.00E+00 2.51E-02 ORGAN BONE LIVER GI_LLI BONE THIS IS A REPORT FOR THE CALENDAR YEAR 1993 i
COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT
% OF LIMIT TOTAL 4.0 MREM 0.156 i
BODY INTERNAL 4.0 MREM 0.628 ORGAN BONE THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE o
COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL.
THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141.
RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 l
, _. - - ~
DRESDEN STATION UNIT TWO b
ACTUAL 1993 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 ADULT RECEPTOR IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC 2
TOTAL 1.72E-02 8.27E-04 2.66E-04 0.00E+00 1.83E-02 BODY i
INTERNAL 6.91E-02 1.26E-03 4.07E-04 0.00E+00 7.03E-02 ORGAN BONE LIVER LIVER BONE l
f THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 10 CFR 50 APP. I
% OF APP I.
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I TOTAL BODY (MREM) 1.5 1.14 0.06 0.02 0.00 3.0 0.61 f
CRIT. ORGAN (MREM) 5.0 1.38 0.03 0.01 0.00 10.0 0.70 BONE LIVER LIVER BONE RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 i
ODCM DATABASE VERSION 0.1 APRIL 1993 i
A i
I i
Y '
i
/
]
1 DRESDEN STATION UNIT TWO
~
1993 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM
- PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 ADULT RECEPTOR IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC 1
TOTAL 8.07E-03 2.79E-05 4.55E-06 0.00E+00 8.10E-03 BODY INTERNAL 3.28E-02 3.91E-05 9.24E-06 0.00E+00 3.28E-02 ORGAN BONE GI_LLI GI_LLI BONE f
THIS IS A REPORT FOR THE CALENDAR YEAR 1993 f
COMPLIANCE STATUS - 40 CFR 141 l
TYPE ANNUAL LIMIT
% OF LIMIT TOTAL 4.0 MREM 0.202 BODY INTERNAL 4.0 MREM 0.820
(
ORGAN BONE THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL.
THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141.
RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993
I l
l f
DRESDEN STATION UNIT THREE i
ACTUAL 1993 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS i
PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 l
INFANT RECEPTOR j
i 1ST 2ND 3RD 4TH l
DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.64E-05 2.90E-05 3.50E-06 0.00E+00 4.89E-05 BODY l
INTERNAL 2.23E-05 6.45E-05 1.55E-05 0.00E+00 1.02E-04 i
ORGAN l
LIVER LIVER LIVER LIVER i
i THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 10 CFR 50 APP. I
% OF APP I.
i QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF f
OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I i
TOTAL BODY (MREM) 1.5 0.00 0.00 0.00 0.00 3.0 0.00 CRIT. ORGAN (MREM) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 LIVER LIVER LIVER LIVER RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993
DRESDEN STATION UNIT THREE 1993 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM
- PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 INFANT RECEPTOR IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.64E-05 2.90E-05 3.50E-06 0.00E+00 4.89E-05 BODY INTERNAL 2.23E-05 6.45E-05 1.55E-05 0.00E+00 1.02E-04 ORGAN LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT
% OF LIMIT TOTAL 4.0 MREM 0.001 BODY INTERNAL 4.0 MREM 0.003 ORGAN LIVER o
THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL.
THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141.
RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993
-=
= -
t i
i DRESDEN STATION UNIT THREE i
ACTUAL 1993 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 i
CHILD RECEPTOR IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL j
JAN-MAR APR-JUN JUL-SEP OCT-DEC 1
TOTAL 5.20E-05 1.98E-04 6.20E-05 0.00E+00 3.12E-04 l
BODY j
~
INTERNAL 2.42E-04 1.16E-03 4.02E-04 0.00E+00 1.80E-03 i
ORGAN j
BONE BONE BONE BONE i
THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 10 CFR 50 APF. I
____________ g op App y,
)
e j
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF I
OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I l
i l
TOTAL BODY (MREM) 1.5 0.00 0.01 0.00 0.00 3.0 0.01 l
~
CRIT. ORGAN (MREM) 5.0 0.00 0.02 0.01 0.00 10.0 0.02 L
\\
BONE BONE BONE BONE j
i' RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 d
J f
j h
9
i 1
DRESDEN STATION UNIT THREE I
1993 ANNUAL REPORT l
PROJECTED DOSE AT NEAREST CCMMUNITY WATER SYSTEM l
PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 CHILD RECEPTOR IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL
{
JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.72E-05 3.05E-05 3.95E-06 0.00E+00 5.17E-05 BODY j
INTERNAL 2.04E-05 5.51E-05 1.21E-05 0.00E+00 8.76E '
ORGAN LIVER LIVER LIVER LIVER l
THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT
% OF LIMIT i
TOTAL 4.0 MREM 0.001 BODY INTERNAL 4.0 MREM 0.002
}
ORGAN LIVER THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE l
o COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL.
THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141.
i RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 I
)
DRESDEN STATION UNIT THREE ACTUAL 1993 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 TEENAGER RECEPTOR IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 9.32E-05 4.32E-04 1.47E-04 0.00E+00 6.71E-04 BODY INTERNAL 2.47E-04 1.21E-03 4.17E-04 0.00E+00 1.87E-03 l
ORGAN I
LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1993 COMPLIANCE STATUS - 10 CFR 50 APP. I
% OF APP I.
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I TOTAL BODY (MREM) 1.5 0.01 0.03 0.01 0.00 3.0 0.02 CRIT. ORGAN (MREM) 5.0 0.00 0.02 0.01 0.00 10.0 0.02 LIVER LIVER LIVER LIVER RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993
~
ODCM DATABASE VERSION 0.1 APRIL 1993 1
r DRESDEN STATION UNIT THREE 1993 ANNUAL REPORT' PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM
- I l
PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 TEENAGER RECEPTOR e
1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 9.26E-06 1.79E-05 2.75E-06 0.00E+00 2.99E-05 BODY INTERNAL 1.09E-OS 2.73E-05 5.86E-06 0.00E+00 4.34E-05 ORGLN GI_LLI LIVER GI_LLI LIVER l
i THIS IS A REPORT FOR THE CALENDAR YEAR 1993 l
\\
i COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT
% OF LIMIT I
TOTAL 4.0 MREM 0.001
)
BODY INTERNAL 4.0 MREM 0.001 1
ORGAN LIVER i
THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL.
THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141.
RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 a
a I
i
)
l 4
1 i
4 DRESDEN STATION UNIT THREE ACTUAL 1993 MAX _' MUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 ADULT RECEPTOR IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.65E-04 7.79E-04 2.66E-04 0.00E+00 1.21E-03 BODY INTERNAL 2.44E-04 1.19E-03 4.07E-04 0.00E+00 1.84E-03 ORGAN LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1993 l
I COMPLIANCE STATUS - 10 CFR 50 APP. I
% OF APP I.
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I TOTAL BODY (MREM) 1.5 0.01 0.05 0.02 0.00 3.0 0.04 CRIT. ORGAN (MREM) 5.0 0.00 0.02 0.01 0.00 10.0 0.02 LIVER LIVER LIVER LIVER RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993 ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 l
l l
)
i s
L i
DRESDEN STATION UNIT THREE j
1 1993 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM
- l PERIOD OF RELEASE - 01/01/93 TO 12/31/93 CALCULATED 08/25/93 l
ADULT RECEPTOR j
i IST 2ND 3RD 4TH l
DOSE TYPE QUARTED QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC l
~
TOTAL 1.33E-05 2.73E-05 4.55E-06 0.00E+00 4.52E-05 l
BODY INTERNAL 1.61E-05 3.91E-05 9.24E-06 0.00E+00 6.44E-05 j
ORGAN i
GI_LLI GI_LLI GI_LLI GI_LLI THIS IS A REPORT FOR THE CALENDAR YEAR 1993 i
COMPLIANCE STATUS - 40 CFR 141 j
i TYPE ANNUAL LIMIT
% OF LIMIT TOTAL 4.0 MREM 0.001 BODY INTE7NAL 4.0 MREM 0.002 ORGAN l
l GI_LLI t
o THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL.
THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141.
I RESULTS BASED UPON:
ODCM ANNEX REVISION 0.K JANUARY 1993
_l ODCM SOFTWARE VERSION 0.1 APRIL 1993 ODCM DATABASE VERSION 0.1 APRIL 1993 l
t i
l I
i I
l l
l i
i t
i DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 METEOROLOGICAL DATA
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Cit:DRESDERSTATIER hmry4ar:h 1993 35 ft. WIX0 !?IID v4 f!ND DIFiti!D2
!!H5ft.DIFFIRINTIAL7EMPIElil!E!
UEER OF O!!EF(A71ths : 2152 V41EES 4EI FIRtikT ttCURRiktE SFEID RIk! IIRiti!Oh CLAS!!S -
- STA!!LITY ttASSES -------
i CIASS n HI hE iki E
iSE Si SSE 5
Sir
!r WSt t
thf it m IDIAL f!!
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SS NS IS 10ill IU.00.00.00.00.00.00.00.t3.00.t3.C0.t!.00.00.00.00
.00.00 i
N 00.00.C0.00.00.00.00.00.00.00.00.00.!D.00
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.H l
C SU.00
.2
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.00 W NS.00.00.00.t0.00.00.00.00.00.00.00.00.t0.00.00.00
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.it 42.C9.!!.21.28.23
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.19.19
.09.18 3.52 3.52 i
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- 9.37 4.35 4.36
[
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.19
.05.00.00
.14.00.19
.28.09.50
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.14
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.14 1.07 1.07 i
11.fi i
l 1
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42.28 JD
.0
.14.05.42
.74
.f!.37.70 5.93 5.93 l
i M
14
.14
.!9.22.37.37.29.00.09 00.19.14 45.05
.14 2.52 2.92 4 50 45 46.70.74.70.46
.00.Di.19
.14
.t5.19 46 1.t2.00.00 5.f5 5.65 i
- t 1.07 1.(2 1.f7 1.11 1.11.79 42 46 19 15.!6.32 1.D2 1.16.97.!! 13.21 13.21 7 SS.37
.42
.23
.0
.19.28.19.79 46.37.74.23.46
.fD.74.42 E.49 5.49 I
i
- 5.00.t5 J0.00.00.05.00.00.51 42 14
.19
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IU.!3.2r.f3.09 42 1.11.37.05.37.2!
45 42
.n 1.99 1.h.25 9.96 9.96 l
H.to.05.32 42.28.51
.14
.23.15.19
.H
.a 14.37.28
.14 1.34 3.34 l
8 SU.19
.it 1.11 1.02.E0.09 39.05
.it
.C5.t9.05.!3.97.!3.23 f.49 6.49
.it.46
.97.37 1.44 1.25.56.32.70 42.79.93 2.13 2.?7 1.48.55 15.41 15.48 l
t $$.19
.M 23.37.0!.I!.05.Il.05.05.51.00
.it
.23.21.09 2.35 2.36 2RS
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1.20 l
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.14 23. 37.00.32 26.09.28.fD.14
.23 42.!1.22 42.55 5.19 5.19 l
1SS.14 14.32.00.00.00.00 J5 19.t!
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tit:IRESafiSTATItt
,!anuary4trch1953 35 ft. WIhD SfliD ed WIhD CIE! TItt 150-35 ft. DIFFIR!KTIAL IIM?iRAil!EE SFila IIC DIRitTIch CLAS$!S STABILITYCLASSES-CIASS I hki nt EnE I
!W tSt t
int Et kRt TOTAL EU NU SU R
SS XS ES 10iAt fl!.t9.00.00.00.00.00.00.00.09.09.05.09.00.00.00.05 46 46 1 #3.00.00.00.00.00.50.00 00.t5.00.05.00.00.00.00.00
.09
.09 i SU.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00
-4
.00.00.00.C0.00.00.00.05.23.51.00.09.05.00.00.00
.33
.93 2SS.00.00.00.00.00.00.00.00.00.t5.00.00.00.00.00.00
.05
.t5 I
4 NS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
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.00
.00 1.53 l
?
t EU.It.00.00.00.00.00.00.00.00.00.00.00.t0.00.00.00
.00.00 G du.00.00.00.00 JD.00.00.00.00.00.00.00.00.00.00.00
.00
.00 I SU.00.00 to.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 4.00.00.t0.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 t
2$$.00.00.00.00.00.00 E0.00.00.00.00.00.00.00.00.00
.00
.00 4 RS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
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IS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
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1 TOI !.t2 5.33 !.34 5.28 f.30 7.09 3.06 3.29 4.96 4.E3 4.91 4.7310.1012.33 7.92 5.70100.00 20.95 7.6814.13 33.3214.37 3.06 1.30 100.00 l
I l
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titt Dire:ti:t ty Stattlity lt N
HE kE INE I
i!E
$1 CSE S
S$t St I!t t
- Nr KV MW TOTAL
-STABIL!if CLASSES-i J
1.10.74 1.t7
.14
.70 1.95.70.19
.56.71.!! 1.39 2.!9 3.20 1.95 1.f2 20.95 Extrerely Wstatie
.19
.!i
.fD.70.79.97.28 2!.37.23.32.37.51 1.t7.51.51 7 !!
- erately Dstable
.55.t! !.t3 f.!! 1.30.il.28.19.37.23
.14
.23 1.76 2.22.17,32 14.13 Slightly Mstable 2.13 2.41 3.15 1.10 2.97 2.78 1.34 1.39 1.95 1,71 1.76 1.19 3.29 3.94 2.57 2.04 38.32 hegtral
.!3 1.11 1.16.60.55.51.32 1.25 1.02.85 1.44.51.97 1.11 1.20.!8 14.37 Slightly Stade
.23 14
.19
.05 JD.05
.!4 JD.70.70.23.19 19.05.09.14 3.05 Moderately Stable
.ti.09.05.05.00.ti.00.00.00.09.14.00.19 14.23.19 1.30 Entrerely SitMe tir:tDire:ttentytied3;eed I
s
.I N
u!
hE Eh!
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.00.00.tt.00.00.00.00.00.00.00.00.tB.to.to.00.00
.00 tat #
l
.70.!8.71.74
.46
.51.t0.70.79 1.15.50.!1 1.02.70.56.57 11.!B 1.0 - 3.5 r;h 2.!3 3.10 3.15 2.18 2.f 4 2.'l6
.97 1.34 1.53 1.!! 1.71 1,48 3.01 4.17 2.27 1.90 35.91 3.6 - 7.5 t;h 1.15.93 3.25 2.21 2.7! 3.t1 1.20.74 1.id.37 1.!! 1.45 4.36 5.54 4.12 1.35 37.63 7.E-12.5trh
.45
.42 1.11.C9
.42 1.20.!!
45.!3.!C.!5 1.t7 1.(7 1.(2.97 1.39 13.25 12.5 - 18.5 r;h
.El.00.0D 00.00.00.00 J5.37.t!.09.19.05.00
-.00
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.00.00.00 00.00.00.00.00.00.00.00.00.00.00.00.00
.00
>24.5rph l
1 4
4 i
C10c DR!$0il STATI;t
.'attary-Maren1993 200 ft. WIED SPEED and IIk0 O!Rf0 TION 300-35 ft. OIffEREETIAL TEMPERATl'RE i
kWiiR 0F CBSERVATIONS : 2077 VALDES ARE FERDEhi 000URElh0E SFff0 IIhD CIR!Di!0N CLASSIS Si4EILITY DIASSES -------
OLA!S 4 Wh!
hE Eh!
Sf SSE S
Sit St WSW W
HW kW AAW TOTAL EU NU S!!
!B.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00.00 FU.00.00.00. 00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 0 SU.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 AX.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 l SS.00.00.00.r;.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 N NS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 ES.00 00.00.00.t0.00 00.00
.00.00.00.00.00.00.00
.00
.00
.00 EU.00.00.00.00.00.00.00.00.00.00.00.00.00.00 00.00
.00.00 WU.00.00.00 00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 f
f 50.00.00 05
.00.00.00.00.00.00.00.00.00.00.00.05.00
.10
.0
-N
.14
.10.00.05.14.10.05.10.05.05
.14
.05.00.14.00.05 1.15 1.16 3 SS.ti.00.CJ.00.00.00.05.00.05.10.24.19 19.00.00.05
.91
.91
{
NS.00.00.00.t0.00.00.00.00.05.00.00.00.00.00.00.00
.05
.05 IS.00.00.00.00.00.00.00.05.00.00.00.00 00.00.00.00
.05
.05 i
2,25 EU.00 10.00.00.00.00.00.00.00.00.00.00.00.00.00.05
.14
.!4 80.00.00.00.00.00.00.00.00.00.00.00 SO.00.00.0!.19
.24 24 4 50.05.05.05.05.00.00.05.00.00.00
.1f
.10
.0b
.05.10.14
.72
.72
-4
.34 4!
.43
.61 48.63.i0.10.34 29
.h
.!! 1.25.91 48.34 7.95 7.99 7SS.05
.14 0;
.9
.29.19.29.10.14.10
.24.19 4!.24.05.05 2.74 2.74 RS.00.00
.0u 05 19.00.05.00.00.05
.00.00.10.00.00.00
.43
.43 00 00.00.05.00.00.00.00 10.10.19.05
.10.00.00.00 12.!5 fli.19
.10.C0.00.00.00.00.00.00.00.00.00.00.05.05.05 43 43 PU.00
.14
.00.00.10.00.00.00.00.00.00.00.05.10.05.!D
.53
.53 i Sil.05.10.10.05.00.10.24
.00.00.00.00.05.19.00 14.00 1.01 1.01 l
-4
.ti 2.02 2.31 1.59 1.73 1.40 48.53.72.63.53.63 1.35 2.41.95.24 18.49 18.49 1 53.34.f3.82 43.24
.29.24
.34.29.58
.34.??
.34
.53 48.!! 7.27 7.27 l
2NS.0!
.10.00.19.05.05.00.00.00
.14
.29.24.19.05
.14.14 1.!4 1.54 ES 10.10.05. 05
.10.00.00.00.00.00.00,10.00.19.00.00
.67
.67 8
30.04 fU.19 10.05.00.00.05.00.00.00.00.00.00
.14
.05
.14 10
.22.22 1 NU.10.00.24.00.00.19.10.00.00.00.00.00
.14
.34 10
.14 1.35 1.35 3 Sil.00.05 10.00.10.19.00.00.00.05.10.19
.14
.43
.24.14 1.73 1.7)
-E
.!?.72 2.07 1.49 1.01 1.!4.!?.34.29.63.91 1.01 1.44 3.51 2.31.!8 19.64 19.f 4 1SS.24 48.24
.29.77.29 19
.14.53.29 39.72.!!.67.72 43 7.08 7.08 I #3 00.05 14.00. 05.05.00.05.10.34
.29 34.00.00.00.05 1.44 1.44
]
ES.10.05 JD.00.00.00.00.00.00 00.00.10.00.35.00.00
.39
.29 12.45 i
l tite tiiSOEX STATIDQ JugarrFar;h 1993 i
300 ft. VIO SPiit ud VIk0 DIE!!TICE 300-35ft.IIfiEREETIALTIRFIEAilTE t
SFif0 (In CIEf t1 ICE CLASSES
- STAlllITY tlAS$!S -----
CIASS X u!
kE Ih!
E ISI h !!i S
$5f if Wit t
in Et ut ICIAL EU M SU i
RS ES TOTAL I
fu.00.00.00.00.00.00.00.00.00.00.00.00.c0.00.00.00
.00.00 1 NU.00.00.t$.00.00.00.00.00.00.00.00.00.!D 10.05.00 19
.19 950.05.00.00.00.00.05.00.05.05.05.00.10.00.19
.00.05
.!B
-N
.72.19.57 1.59.82 1.01.05.19.14.19.24.48 1.44 2.21.il.96 11.!!
11.!9
'SS.00
.14
.05.00.24.63.24
.14 43.39.53.29
.48
.29
.14.29 4.29 4.29 4 QS.00.00.00.00.00.00.00.00.00.05
.14.00.00.00.00.00
.11 ES.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 11.14 EU.05.00.00.00.00.00.00.00.00.00.00.00.00.00.00.05
.10.10 GW.10
.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.10
.10 i SU.10
.00.00.00.00.00.00.00.05.00.00.00.00.0D.00.00
.14
.14 1
19.39.77.00.00.05.00.00
.14
.!7 10
.14
.34
.14
.29.28 3.71 3.71 i
2SS.00.00.00.00.00.00.00.05.24.!!.00.34.00.00.00.00 1.20 1.20 4 NS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 ES.00.00.00.t3.00.00.00.t0.00.00.00.00.00.00.00.00
.00
.00 5.25 I
i i
?
101 5.01 f.21 8.25 f.74 f.31 f.58 2.94 2.17 3.80 5.44 !.10 f.f4 8.5512.fi 7.51 5.t5100.00 1.49 2.41 4.29 62.!! 23.50 3.76 1.69 100.00
- its Dire::ica by Statility r
R HE ti ih!
$!t it WSt t
tu u ut iDIAL
-STA!!1ITY CLASSIS-
.43
.29.05.00.00.05.00.00.00.00.00.00 14
.10
.11.24 1.49 Extrerely tr, stat!e
.11
.!4
.29.00.10.19
.10.00.00.!D.00.00.11.53.24.43 2.41 hieratelyUtstable 24.19.29
.10.10.34.29.ti.10.10.19 43.34.!7.53.34 4.29 SligttlyUnstable 3.23 3.30 5.26 5.39 4.19 4.72 1.41 1.25 1.78 2.f 5 2.26 3.13 5.83 9.34 5.01 2.46 62.!8 kertral l
.57 1.40 1.11
.91 1.!4 1.59 1.01.77 1.59 2.02 1.73 !.45 2,07 1.73 1.40 1.40 23.50 Slfgttly Stable
. 05
.14
.14
.24
.28 10.!!.05
.14
.58.T2.!!.29.05.14.19 3.76 hderately Stable
.19
.14
.14 10.10.00.00.t5 10 10.ti.24.10.24
.00.00 1.69 btrerely Stable I
vird Dire:t:en ty kind Stee0 j
4 ME Af Ik!
E ESE SI $5E
!!i St WSt t
ut n ut 10iAl
-VIG spi [D OLASSES-
.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00 tALM
.19
.10.05.05
.14
.10.10.14.14 14.39.24.19.14
.05.10 2.26 1.0 - 3.5 rph 43.77 45 1.01.96.!2 48.19.58.53.87 1.16 1.93 1.20.57.77 12.!$
3.6 - 7.5 ren 1.il 3.!! 3.27 2.31 2.21 1.93.96.87 1.01 1.35 1.16 1.?3 2.12 3.32 1.f 3 1.11 30.04 7.5 - 12.5 rph 1.41 1.44 2.94 1.71 1.93 2.41 1.11
!31.011.301.692.352.4!!.063.511.44 32.45 12.6-18.5::n
.77.34.77 1.!9 1.0f 1.il.!!.39.!3. 17.91.!7 1.93 2.79 1.15 1.30 17.14 18.6 - 24.5 rph
-]
43.39.77
.00.00.05.00.05 43 1,44.10.48.34
.14
.29.34 5.25
>24.5r;h J
i I
J l
DEcc ORISDEN STATIOE April-Jue 1993 3
35 ft. VING SFi!D W 6I00 DIRECTICE 15H5ft.DIfffREETIALTENFERATURE MfR Cf DBIERVATI0k$ : 2181 VALUESAREPERDEET0000RRfhCE spi!D W!k0DIRit7IONCLASSES
$7AlllITYCLASSES-CLASS 4 th!
(E Eh!
E ES!
Sik SW tSt t
nr KW kW TOTAL
!U NU SU i
SS NS ES TOTAL IU.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00.00 OU.00.00.00.00.00.00.00.00.0D.00.00.00.00.00.00.00
.00
.00 0 SU.00.00.00.0D.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 A4.00.00.00.00.00.00.00.00.00.00.00.00.00.00. 00.00
.00
.00 L SS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 N 03.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 ES.00.00
.~0
.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00
.00 EU.09.00.00.00.00.00.00.00.00.09.00.05.05
.14
.14
.00
.55.55 80.00.00.05.00.00.00.00.00.00.05.00.05.09.00.05.00
.28
.28 1 50.00.00.05.00.00.00.00.05.00.05.00.00.05.00.05.05
.25
.28
-N
.05.14.23.09
.14.05
.14.09.00.00.05.05.1!.00.00.00 1.19 1.19 3 $$.23
.(9
.14
.46 18
.14.23
.14
.28.23.18.28.05.32.32 4.03 4.03 NS.14.23.09.05.00.00 18.23.28.28 46.05.32.55
.14.00 2.58 2.98 15 18 14.05.00.05.09
.14
.00.09
.14
.37.09.18.09.09.23 1.93 1.93 11.23 EU.50.37.32.32.50.69
.14.18
.00.09.23.83
.41
.fi.E3.50 6.59 f.fi rd.00.05.18
.18
.32.23.00
.it
.00.05
.14.05.09.18
.00.05 1.E5
!.55 4 50.00.09.23.37.23
.14
.05
.14
.00.05.05.05.00.09.05.00 1.51 1,51 i
-N
.23
.41 2.34 3.21 2.20 1.19.37.50.54
.28.37.23
.41
.55.28 41 13.12 13.62 i
7SS.32 45.il.50 1.24 1.93 1.19.73.23
.14
.32.37.60.10.92.!5 10.87 10.87 NS.05.00.00.09.05.it.46.05.09.55 1.05.28
.14.37.00.18 4.13 4.13 ES.00.00.00.00.00
.14
.05.05.00.00.32.05.00.00.09.00
.59
.19 39.16 i
i ft.41.23
.E4
.28.23.18.50
.14.28.37.37.96.37 1.42 1.42 1.38 9.17 9.17 i
F!!.00.05 18 1!.05
.14.23.09.05
.14
.28.09.05.00.05.18 1.74 1.74
)
i SU.00.!5.23
.14
.09
,?!
.32.18.05.05.09.14.05.09.09.05 1.79 1.79 X.E0
.41
.f4.59 1.05 1.42 2.02 1.15.SE.!9.it.28.f4.f7.!4.73 13.43 13.43 1 $$
18.28.00.00.09.37 1.70.63 45.73.95.32.37.23.18.14 f.23 5.23 l
2QS.00.00.00.0D.00.05.00.00.00.05.18.00.00.05.00.00
.32
.32 is.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 -
l 33.29 i
l EU.00.00.05.00.00.14.46
.32.55.18
.14 1.t5.05.23.18.09 3.44 3.44 14.00.00.00.00.00.05
.14
.14
.05.09.00.00.05.05.00.00
.!5 3 SU.05.00.00.00.00 14
.14
.23.05.09.00.09.00.00.00.00
.78
.78
- K.28.iG.37.00.32.28.!! 1.38 1.28.23.41.28
.f4.22.23.55 1.44 8.44 1SS.00.00.00.00.05.18.28
.14
.18.18.00.00.05.05.00.00 1.10 1.10 i #$.00.00.00.00.00.00.00.00.00.00.05.00.05.00.00.00
.tl
.09 ES.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 14.40
CICs IRESCIR STATICA April-kne1993
+
g 35 ft. II G SFf!D ana VIG DIEftTICt 150-35 ft. LITTEREli!!At T!RPIRAT0EE SFIED WIG DIRECT! 5CLAS!!$
STABILIir CLASSES CLASS N kk!
LE ik!
I IS!
$! S$f S
S$f !W tSt t
kkW kV kkt 70iAt EU NU SU R
SS ES ES TOTAL EU.00.00.00.00.00.00.00.00.00 09.28.09.05.00.00.00
.50.50 1 M3.00.00.00.00.00.00.00.00.00.05.00.00.00.00.00.00
.05
.05 9 SU.00.00.00.00.00.00.00.00.00.05.05.00.09.00.00.00
.18
.18
-X
.00.00.00.00.00.00.00.05.23.37 05.00.05.00.00.00
.73
.73 2 SS.00.00.00.00.00.00.00.00.00.09.05.00.00.00.00.00
.14
.14 4KS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.?O
.00 IS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 1.60 EU.00.00.00.00.00.00.00.00.00.05.00.00.00.00.00.00
.05.05 G fu.00.00.00.00.00.00.00.00.00.09.05.00.00.00.00.00
.14
.14 7 SU.00.00.00.00.00.00.00.00.00.t!.00.00.00.00.00.00
.05
.05 I.00.00.00.00.00.00.00.00.00.05.05.00.t0.00.00.00
.09
.09 2SS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 4FS.00.00.00.00.00.00.00.00.t0.00.00.00.00.00.00.00
.00
.00 ES.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00
.32 10i 3.30 4.17 6.!$ i.37 7.15 8.53 9.31 7.02 5.!$ l.!! 7.20 5.59 5.27 6.51 5.73 5.41100.00 20.40 4.40 4.!9 37.5122.97 7.52 2.(1 100.00 kitd Direct 1:n ty Stat 11ity E
hhi AE Eh!
E ISE
$! SSE S
S!b St t:W f
akt NW hkt 10TAL
-STABILITYtlAS$iS-1.01.50 1.01.f!.!3 1.01 1.10.54.83.!71.012.98.92 2.48 2.57 1.97 20.40 ExtrerelyDestatie
.00.09 41.37.37
.41
.37.37.09
.46.46 18.23.23.09.23 4.43
- a:tratelyUtstable
.05. 14.50.50.32 45.50.60.09.32.ti.28.18.18.18.09 4.!9 Sit;ttlyUnstatle 1.15 1,55 3.!B 3.99 3.71 2.93 3.21 3.16 3.12 2.20 1.!!.83 1.93 1.74 1.15 1.70 37.51 Kestral
.73 1.42.92.71 1.f3 2.fi 3.30 1.i1 1.01 1.42 1.!!.87 1.28.83 1.42 1.01 22.97 SlightlyStable
.18.23.09.14
.05.f3.54.28.37.87 1.74.32.50.96.14.11 7.!!
Faderately Stable
.18
.14
.05.0C.t!.23
.18
.05.09
.14
.!9
.14.18.C9.12.23 2.11 Extremely Stable litid tirectict ty tits $;ect i
Khi n! lhi f
iSE
$[ $$f S
551 SW kSW W
ikk kN kht TOTA!
-FIG SFi[D CLASSES-
.00.50.00.00.00.00.00.00.00.00.00.00. 00.00.00.00
.00 Cati
.f9 1.19.50.32.f4.32.it.50.50.37 1.10 46 1.15.23.78.!D 11.23 1.0 - 3.5 rph 1.10 1,38 3,25 4.77 4.53 5.09 2.25 1,79.96 1.15 2.48 1.23 1.f! 2.3! 2.15 1.70 39.18 3.5 - 7.5 rph 1.19 1.t1 1.10 1.28 1.51 2.34 4.77 2.38 1.79 2.02 2.52 1,79 1.47 2.!6 2.38 2.4! 33.29 7.5-12.5r;n
.32.10
.41
.00.37.7! 1.70 2.20 2.11 1.38.60 1.42.83
.it
.41
.it 14.40 12.5-i8.!t;n
.00.fD.00.00.00.00.50.t5.23.E4
.41
.09 18. 00.C0.00 1.fD II.6-24.5r;t
.00.00.00.00.tB.00.00.00.00.23.09.00.00.00.00.00
.32
>24.5rpn
3 CItoIRISCEhSTATIH A;riNue 1993 300 ft. VMD SFi!D ad tIH DIR!tTIDX 300-35 ft. DIFFIE!ETIA! TERPIRATUEE 1
I DEIROFCBSIFVATI0h5: 2154 i
VA!UES ARE FIRtfET DCCUREEkCE i
SFI!D --
- VIkt DIR!CTI H tlASSES STASILITYtlAS!!$
i CLASS k hh! kE ik!
E ESE
$! S!!
S S$r !W WSK i
tkW hv kkW TOTA!
EU RU SU R
SS FS IS TOTAL i
i k
4 EU.00.C0.00.00.00
.H
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.00.00 RU.00.00.00
.H
.00.00.00
.H
.H
.00.00
.H
.00.00.00
.H
.H
.00 t 50.00.00
.H
.00.00
.9
.00.00.50
.H
.00.00.00
.H
.H
.00
.00
.00 An
.H
.00
.H
.00.00.00.00.00.00.00
.0'
.00.C0
.H
.00.00
.00
.00 L SS
.H
.H
.00.00.00.00.00.00.00.t0.00.00
.H
.00
.H
.00
.00
.00 NR$
.H
.H
.00.00.00.00.00.00.00.00.00.E0.00.00.00.00
.00
.H I
i 15.00.00.00.00
.H
.00.00.00
.H
.00.00.00.00.00.00.00
.00
.00
.00 i
EU.00.00
.H
.00.00
.H
.00.00
.H
.H
.H
.00.00
.H
.t0.00
.00
.H i
NU.00.00.00
.H
.00.00.00.t0.00 00.00.t0.00.00.00.00
.00
.H 1 Sti.00.00.00.!D.00
.H
.00.00.00.00
.H
.00.00.00.00.00
.00
.00 i
-X
.00.C5.00.00.05
.H
.00.05.00.09.05.00.05.to.05.00 42 42 I
3 !$.00.C0.00.ta.tl.00.05.00.00
.H
.00.00.05
.H
.00.00
.19
.19 R5.05.C5 30.C5.00.05
.H
.H
.00.00.09.09.05.05.05.00
.51
.51 ES.00.C0.CD
.H
.05.00.09.00.00.00.00.C0
.H
.00.00.00
.14
.!4 1.25
[U.Cl.00.00
.H
.00.00
.H
.00.00.00.00.00.00
.H
.00.00
.05.05
- D.0!.C5.00.00
.H
.00.00.00.00.00.00
.H
.H
.00.00.00
.09
.09 4 SU.00.05.09.05
.H
.09.00.00.00.00
.H
.05
.H
.05.09.00 46
.45
-K
.00.09.19
.H i6.!6.23.23.00.05 '.23.50.23.50.37.32 4.87 4.87 E
7$$.19.19
.23
.14
.09
.H
.25.23.23.09.09.19.19
.14
.14.09 2.51 2.51 R$.05.00.C5.00
.H
.09.t5
.14.23.09
.14
.00.05.19.09.14 1.30 1.30 ES
.H
.14
.00.00.05
.H
.09.00.00
.H
.00.00.t!.05.05.C9
.51
.51 9.t0 t
L i
ED.09
.H
.00
.H
.00.00.00.00.00.00.03.00
.H
.00.00.32
.42.42 NU.00 09.23.09.00.!D.00 00
.H
.H
.00.00.00.00.14.32
.28 8 SD.19.09.32 46.09.00.00.00.00
.H
.00.23.05
.14.09.19 1.!6 1.fi
-t
.32.37 1.21 2.09 1.!! 1.t2.79 1.07.37.32.f0.fi 46.93.fD.tl 12.81
!!.11 1 SS.23.2! 1.49 1.16 1.15.28.!!
.f4 23.23.37.50.!!.51.!i.23 9.fi 9.f,6 2MS.09.09
.H
.05.00.05
.H
.14
.14
.19
.14
.79.46
.19.28.09 2.69 2.!!
IS.00.05.00.00.00.00.00.09
.H 00.05.00.00.05.09.05
.37
.37
?
!!.it -
i 1
fu.t!.19.00.00.00.00
!O.00
.H
.00.00
.H
.00.00.00.14
.37.37 4
1 QU.09.09.14.00.05.00.00.00.00
.H
.00.00.00.00.19.37
.93
.93 3 SU
.14
.00.09.05.05
.H
.05.09.t0.00.00.00.00.09
.14.23
-. 93
.93
- n
.H
.23 1.39 1.07.70
.93. 1.39 1.25.!I 1.25.70.50 46 1.67 1.35 1.21 15.97 15.17 i
4 1 SS.!!.28
.45
.3!.61 1.49 3.11 1.21 1.02.70.tB.!$.50.f0.97.37 13.83 13.83 iR$.00.05
.14
.H
.19.09 46
.42.!4
.19.45.93.28.23.32.t9 3.99 3.H ES.19.00.00
.H
.00.00.00.05.00.05
.14
.09.21.t5.00.05 3f.91
\\
l
4' 1
CEtcDRESDEQSTATIDX A;ril-htt 1993 300 ft. VIk0 SFifD ttd VIH IIFICTICX HM5 ft. DIFTEREEilAl TINFERAlliRE SFi!D Win 0LIFECTICEIlASSES SIGILIIf CLASSES -
C! ASS N HI kE ih!
ESE
!! SSE S
S!r St WSW V ut ny ut TOTAL EU U
SU K
SS NS IS ThiAl l
1 IU
.H
.00.00.00
.H
.00.CD
.H
.C0.00.00.00.00.00.00.00
.00.00 1 FU.00.00
.H
.00.00.00.00.00.00.00.00.00.00
.H
.00.00 00
.t0
+
9 SU.t5.05.05.00.00.09.14.09.00.05.00.00.50.05.05.00
.50
.50
-N
.!!.37.09.05.56 45.74.84 1.25.!!.37.28.28.79.56.50 9.24 9.24 2 !S.0S.23.14.00.09 14.55 1.21.97 1.11.74.74.37.23.05.00 6.7!
6.78 I
4 NS CG.00.00
.H
.05.05.23.00.00.00.37.14
.H
.00.00.00
.!4
.84 IS.00.00.00.00.00
.H
.00.14.00.00.05.00.00.00.00.00
.19
.19 17.t.
I
!D
.H
.00.00.00
.H
.00.00.00.00.00.00.00.00.00.00.00
.H 00 G dll.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.50 i SU.00.00.00.00.00.00.C0.00.00.00.00.00.00.00.00.00
.00
.00 X.09.ED.32
.H
.00
.H 05.05
.14
.!6.70 45.51.09.00.09 3.76 3.76 2 SS.05.;0
.id
.00.00.09.09 19 32.32.32
.H
.H
.14.00.05 1.!!
1.!1 4 FS
.H H
.H
.00
.H
.H
.00.00.00.00.05.05.05.00.00
.H
.14 14 ES.50.00.00.00.00.00.00.C0.00.t0
.H
.00.00.s0.00.00
.00
.00 t
5.71 IDI 3.!1 3.f ? 6.78 6.17 6.27 5.12 9.38 f.91 5.!! 6.17 6.27 7.99 5.01 f.!7 6.22 5.25100.00.84 1.90 3.85 47.05 34.77 9.47 2.09 100.00 i
tit: Dire::icn by Sta;11ity N
u!
k! ER!
E
!! !SE S
S!V St (Sk 1
tkV kW ut TOTAL
-STA!!tIiy CLASSES-t
.19
.19
.00.00.00.00.00.00.02 00
.H
.C0 00.00
.H 46
.tt Entrerely Utstalle
.14 23.37
.H
.t5.00.0C
.H
.0D.00
.H
.00.00.00.32 70 1.90 Necerately lltstatte
.37
,19.!!.56
.te.19. !9.19
.00.05
.H
.25.05.32.37 42 3.f5 Sli;htlylltstable j
1.!3 1.72 2.20 3.!! 3.44 3.11 3.20 4.09 2.32 3.16 2.15 3.44 2.00 4.09 2.92 2.41 47.08 Ecutral 1.21.97 2.46 1.f 2 2.32 2.H 5.05. 3.17 2.79 2.45 2.14 2.11 1.75 1.17 1.72.74 34.77 5119htlyStat!e 19 19 19.I9.23.32.74.7s.51 45 1.25 2.00.BB.65.74.32 9.47 Nederately Sttile 19
.if.00
.H
.09.00.19.28.00.!!.23.09.32.14.14
.19 2.t9 Intrerely Stable i
tird Dire: tion ty bito Spea j
h u!
n! EhE E
$!t It VSt t
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