ML20012G464
| ML20012G464 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/30/1992 |
| From: | Schroeder C COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20012G465 | List: |
| References | |
| NUDOCS 9303020529 | |
| Download: ML20012G464 (57) | |
Text
l s
Semi Annual Report Distribution All Stations Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Station P1-137 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 Marek, Acting Manager Maywood Regional Office 1701 First Avenue Maywood, IL 60153 Illinois Environmental Protection Agency Division of Water Pollution Control Environmental Protection Specialist 2200 Churchill Rd Springfield, IL 62706 If delivered by private carrier (i.e. Federal Express) direct carrier to the lower back area of the One White Flint North Bldg, Mail Station P1-137
' (p:\\ptntact\\cws93\\D085.93)
A K
R
l t
Semi Annual Report Distribution All Stations (Cont'd)
Murray & Trettel, Inc Environmental Meteorologist 414 West Frontage Rd Northfield, IL 60093 Teledyne Isotopes Midwest Laboratory 7
General Manager i
700 Landwehr Rd Northbrook, IL 60062 Chemistry Services Chemistry Services Director Downers Grove Emergency Preparedness Emergency Preparedness Director Downers Grove r
Nuclear Quality Programs and I
Assessments General Manager Suite 650 Downers Grove I
i l
(p:\\pintmgr\\cws93\\DDB5.93) i l
I
r Semi Annual Report Distribution Dresden Station Manager Dresden j
Health Physics Services Supervisor I
Dresden l'
I NRC Senior Resident Inspector Dresden U.S.
Nuclear Regulatory Commission Region III 799 Roosevelt Rd.
Glen Ellyn, IL 60137 (Two copies)
Nuclear Quality Programs Superintendent Dresden l
I i
h k
b (p:\\pintmgr\\cws93\\0085.93)_
L
?
e DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 REGULATORY LIMITS Gaseous Effluents - Dose This Specification is provided to ensure that the dose at the
[
unrestricted area boundary from gaseous effluents from the i
units on site will be within the annual dose limits of 10 CFR i
Part 20 for unrestricted areas.
The annual dose limits are the doses associated with the concentrations of 10 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 CFR Part 20.106(b)).
The specified release I
rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the unrestricted area boundary to less than or equal to i
500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year.
For purposes of calculating l
doses resulting from airborne releases, the main chimney is considered to be an elevated release point and the reactor building vent scack is considered to be a mixed mode release l
point.
i i
Dose, Noble Gases This Specification is provided to implement the requirements f
of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Conditions For Operation implement the guides set forth in Section II.3 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 gaseous effluents will be kept "as low as is reasonably achievable."
The Surveillance Requirements implement the requirements in Section III. A of Appendix I that conformcnce with the guides of Appendix I is to be shown by calculat;onal procedures based on models and data such that the actua. exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated.
The j
dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble
]
gases in gaseous effluents will be consistent with the i
methodology provided in Regulatory Guide 1.109, " Calculation l
of Annual Doses to Man from Routine Releases of Reactor Ef fluents for the Purpose of Evaluating Compliance with 10 CFR i
l (p:\\pintmgr\\cws93\\0085.93),
i
DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 REGULATORY LIMITS Dose, Noble Gases (continued)
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 doses at the unrestricted boundary based upon the historical average atmospheric conditions.
NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.
l
\\
l l
l I
i (p:\\pintmgr\\cws93\\0085.93),
i
DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 J
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, 10 CFR Part 50.
The Limiting Conditions for Operation are the guides set forth in Section II.C 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 materials in gaseous effluents will be kept "as low as l
reasonably achievable."
The ODCM calculational methods specified i
in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of l
Appendix I be shown by calculational procedures based on models and l
data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM 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 Compliance with 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.
These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
The release rate specifications for radioiodines, 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 inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man and 3) deposition onto grassy areas'where milk animals graze with consumption of the milk by man.
Gaseous Waste Treatment The OPERABILITY of the gaseous waste treatment which reduces amounts or concentrations of radioactive materials ensures that the system will be available for use whenever gaseous ef fluents require treatment prior to release to the environment.
The requirement that the appropriate portions of this system be operable when specified provides reasonable assurance that the releases of radioactive naterials in gaseous effluents will be kept "as low as reasonably achievable".
This specification implements the requirements of 10 CFR Part 50.36a, General Desian Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50.
(p: \\ pint ngr\\r ws93 \\0085.93)_
DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 i
LIOUID EFFLUENTS concentration l
This specification is provided to ensure the concentration of i
radioactive materials released in liquid waste effluents from the l
site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix 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 t
International Commission on Radiological Protection (ICRP) l Publication 2.
Dose j
This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50.
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 j
reasonably achievable".
The dose calculations in the ODCM i
implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
The equation <: 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 in Regulatory Guide 1.109, " Calculation of j
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.
UUREG-0113 provides methods for dose calculations with Reg Guide 1.109 and 1.113.
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 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 Part 50.
)
(p:\\pintrier\\cws93\\0085.93)_
J
DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)
I The concentration of radioactive materials released in gaseous and liquid effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B,
Table II, Columns 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 Radiological Protection (ICRP) Publication 2.
t MAXIMUM PERMISSIBLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE MPC(uci/ml)*
Kr-85m 2.OE-04 Kr-85 5.0E-04 Kr-87 4.OE-05 Kr-88 9.OE-05 Ar-41 7.0E-05 Xe-131m 7.OE-04 Xe-133m 5.OE-04 Xe-133 6.OE-04 Xe-135m 2.0E-04 Xe-135 2.OE-04 L
Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for infinite cloud submersion in water, and R = 0. 01 rem / week, density = 1. 0 g/cc and Pw/Pt =
1.0.
i l
t i
(p:\\pintmgr\\cws93\\0085.93),
1 DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 AVERAGE ENERGY The average energy of fission and activation gases was calculated for the gaseous effluents released from the i
site.
The average energy is based on the percentage of each fission gas nuclide present and its average energy per disintegration (E in MeV/ dis) for gamma and beta emissions separately.
Eo = 3.75E-01 MeV/di ;
Ea = 2. 97E-01 MeV/ dis l
EOUIPMENT OUT-OF-SERVICE:
The Units 2 and 3 Main Chimney SPING (System Particulate Iodine Noble Gas Monitor) was out of service from January 29, 1992 to February 29, 1992.
This was due to calibration work on the SPING.
The 2/3 Chimney G.E.
Radiation Monitors and the respective Iodine and particulate samplers were utilized during this period.
I b
i i
f i
9 b
t (p:\\piningr\\cws93\\0085.93)
I DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10,
[
50-237, 50-249 MEASUREMENTS AND APPROXIMATIONS i
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.
Tritium is sampled monthly via a grab sample on the D-1
- Chimney, D2/3 Chimney, and D2/3 Reactor Building Vent and analyzed using l
a Liquid Scintillation Counter.
Krypton-85 is estimated in the D2/3 Chimney using a
recoil or non-recoil calculation using the fission per second plot and the sum of Kr-85m, Kr-87, Kr-88, Xe-133, Xe-135, and Xe 138 activities present in Reactor Off-Gas.
B.
Iodine and Particulate:
Iodine and particulate samples from the D-1 Chimney, D2/3 Chimney and the D2/3 Reactor 1
Building Vent are collected for a maximum seven day 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 that the sample may not be representative, an average of the preceding sample and the following sample is used to calculate the release.
A monthly composite of the particulate samples is sent to a vendor to be analyzed for Fe-55, Sr-89, Sr-90, and Gross Alpha activity.
j C.
Liquid Effluents:
Analyzed for specific isotopes present in the release using a HP Ge spectrometry system.
A i
composite of all batches for the month is sent to a vendor to be analyzed for Sr-89, Sr-90, Fe-55, H-3, and Gross Alpha activity.
A sample of each Containment Cooling Service Water (CCSW) system is analyzed each month for specific isotopes present in the release using a HP Ge spectrometry syste.a.
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.
f D.
Estimation of Overall Errors:
The methods used for i
estimating overall errors associated with radioactivity 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.
(p:\\pintngr\\cws93\\0085.93),
DRESDEN NUCLEAR POWER STATION UNITS 1,2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1911 GASEOUS EFFLUENTS Docket Numbers: 50-10 50-237 SUMMATION OF ALL RELEASES 50-249 TYPE OF RELEASE UNITS 1st QUARTER 2nd QUARTER $kRdk ^
FISSION AND ACTIVATION GASES l
1.
Total Release l
Ci j7.69E+00 l 1.09E+00 7.31 2.
Average Release Rate for Period uC1/secj 9.78E-01 1.39E-01 l
3.
Percent of Technical Specification Limit B.
IODINES l
1.
Total Iodine-131 l
Ci j 2.18E-07 l 1.18E-04 9.51
' 1.50E-05 2.
Average Release Rate of I-131 for Period uCi/sec 2.77E-08
[
3.
Percent of Technical Specification Limit t
4.
Total Iodine-131, Iodine-133,and Iodine-135' Ci 2.87E-04 1.39E-03 f
C.
PARTICULATES j
l 1.
Particulates with half-lives > 8 days Ci 6.40E-03 l 9.56E-03 l 8.09 2.
Average Release Rate for Period uCi/sec 8.14E-04 1.22E-03
{
j 3.
Percent of Technical Specification Limit 4.
Gross Alpha Radioactivity Ci 3.95E-06 LLD D.
TRITIUM' l
1.
Total Release Ci 6.17E-01 1.51E+00 7.89 2.
Average Release Rate for Period uCi/sec 7.84E-02 1.92E-01 3.
Percent of Technical Specification Limit
- The information is contained in the Radiological Impact on Man section of the report.
Total airborne release data is provided which includes fission and activation gases, lodines, particulates, and tritium.
[
f
(
l I
i f
i i
i E
l i
i 42:\\pintegr\\cws93\\DDB5.93)
.}
DRESDEN NUCLEAR POWER STATION UNITS 1,2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1991 GASEOUS EFFLUENTS Docket Numbers: 50-10 50-237 SUMMATION OF ALL RELEASES 50-249 LLD (uCi/cc) 1.
FISSION GASES Xe-138 1.60E-07 Xe-135m 9.90E-QH Kr-87 4.40E-08 Kr-88 5.40E-08 Kr-85m 1.80E-08 Kr 5.10E-06 Xe-135 1.60E-08 Xe-133 4.40E-08 Ar-41 2.50E-08_
Xe-133m 1.50E-07 2.
IODINES I-131 7.90E-13 I-133 3.40E-12 1-135 4.70E-10 3.
PARTICULATES Sr-89 1.60E-14 Sr-90 3.00E-15 Cr-51 5.40E-12 Mn-54 6.80E-13 Co-58 8.00E-13 Fe-55 3.00E-14 Fe-59 1.60E-12 Co-60 1.40E-12 r
Zr-95 1.40E-12 Nb-95 7.10E-13 Mo-99 7.40E-13 Ru-103 7.20E-13 Aa-110m 6.30E-13 Sb-124 5.70E-13 I-131 7.70E-13 3
Cs-134 6.80E-13 l
i Cs-136 7.30E-13 Cs-137 7.60E-13 Ba-140 3.30E-12 La-140 1.10E-12 Ce-141 9.99E-13 Ce-144 3.80E-12 Zn-65 1.70E-12 Ba-133 7.20E-13 Sb-125 1.90E-12 i
Others i
Gross Alpha 1.2E-14 1
IP:\\pintgr\\cws93\\DG85.93),
s
DRESDEN NUCLEAR POWER STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1992 p1 chimney CASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Number 50-10 SEMI-ELEVATED RELEASES XX ELEVATED RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED
. UNIT Ist QUARTER 2ndQUARTER J_s_t QUARTER EDd QUARTER l
FISSION GASES Xe-138 Ci Xe-135m Ci Kr-37 Ci Kr-88 Ci l
Kr-85m Ci Kr-85 Ci Xe-135 Ci a
Xe-133 Ci TOTAL Ci !
I-133 Ci !
I-135 Ci !
TOTAL Ci !
NONE NONE PARTICULATES l
Sr-89 Ci l 3.88E-07 1.75E-07 Sr-90 Ci !
8.19E-08 i
Cr-51 Ci !
i Mn-54 Ci !
co-58 Ci !
Fe-59 Ci Co-60 Ci 2.79E-06 2.25E-06 Zr-95 Ci Ub-95 Ci Mo-99 Ci Ru-103 Ci !
l Aa-110m Ci l
J Sb-124 Ci I-131 Ci Cs-134 Ci !
i es-136 Ci Cs-137 Ci 6.79E-06 3.81E-06 Ba-140 Ci La-140 Ci Ce-141 Ci !
Ce-144 Ci '
Zn-65 Ci Ba-133 Ci i
Sb-125 Ci 3.09E-06 l
Fe-55 Ci TOTAL Ci 1.00E-05 9.33E-06 NONE NONE The activity of this nuclide is less than the LLD listed on the-appropriate table.
i P
i (p:\\pintner\\tws93\\D085.93),
'1 DRESDEN NUCLEAR POWER STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through March 19H DI Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Number: 50-10 SEMI-ELEVATED RELEASES XX ELEVATED RELEASES CONTINUOUS MODE NUCLIDES RELEASED ' UNIT' JANUARY l
FEBRUARY j
MARCH l 1et QUARTER TOTAL FISSION GASES l
1 Xe-138 Ci Xe-135m Ci Kr-87 Ci Kr-88
! Ci Kr-85m
! Ci a
? Ci Xe-135 t Ci Xe-133
! Ci a
TOTAL
! Ci i
I-133
! Ci i I-135 t Ci !
TOTAL
! Ci !
PARTICULATES !
Sr-89
! Ci !
6.29E-08 1
3.90E-08 2.86E-07 3.88E-07 i
! Ci !
4.91E-09 4.40E-08 3.30E-08 8.19E-08
~
Cr-51 Ci t
Mn-54 Ci 1
Co-58 Ci Fe-59 Ci 1
1.53E-06 1.26E-06 2.79E-06 Co-60 Ci a
Zr-95 Ci a
?
Nb-95 Ci i
Mo-99 Ci i Ru-103 Ci !
Aa-110m Ci Sb-124
! Ci I-131 Ci t
Cs-134 Ci Cs-136 Ci Cs-137 Ci 2.17E-06 4.62E-06 6.79E-06 Ba-140 Ci La-140 Ci !
Ce-141 Ci !
Ce-144
! Ci !
1 Zn-65 Ci !
Ba-133 Ci !
Eb-125 1 Ci !
! Ci !
TOTAL
! Ci !
2.24E-06 6.23E-06 1.5BE-06 1.00E-05 The activity of this nuclide is less than the LLD listed on the appropriate table.
(p:\\pintmgr\\cws93\\0055.93),
7 4
l DRESDEN NUCLEAR POWER STATION
{
UNIT 1 t
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT April Through June 1992 DI Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Number: 50-10 SEMI-ELEVATED RELEASES XX ELEVATED RELEASES t
CONTGUOUS MODE NUCLIDES RELEASED UNIT l APRIL j
MAY JUNE j
2nd QUARTER TOTAL l
FISSION GASES 1
Xe-138 Ci '
1 Xe-135m Ci l
1 1
Kr-87 Ci Kr-88 Ci Kr-85m Ci Kr-85 Ci !
Xe-135 Ci !
I Xe-133 Ci !
TOTAL Ci !
IODINES 1
I-131 Ci I-133 Ci t
I-135
! Ci i t
TOTAL
! Ci !
I PARTICULATES Sr-89 C1 1.46E-07 1
2.91-06 1
1.75E-07 f
Sr-90 Ci !
l t
Cr-51 Ci !
l Mn-54 Ci !
Co-58 Ci Fe-59 Ci 1
2.25E-06 Co-60 Ci 2.2SE-06 Zr-95 Ci Nb-95 Ci Ru-203 Ci a
Ac-110m Ci Sb-124 Ci I-131 Ci t
Cs-134
.' Ci !
Cs-136
! Ci Cs-137 Ci 2.3DE-06 1.43E-06 3.81E-06 Ba-140 Ci l
i f
La-140 Ci 1
ce-141 Ci 7
Ce-144 Ci Zn-65 Ci Ba-133 Ci 1
Sb-125 l Ci Fe-55
! Ci 9.13E-07 1.96E-06 L
2.16E-07 3.09E-06 TOTAL
! Ci !
5.69E-06 1.99E-06 1.65E-06 9.33E-06 The activity of this nuclide is less than the LLD listed on the appropriate table.
I i
i i
(p:\\pintmgr\\cws93\\0DB5.93) l
DRESDEN NUCLEAR POWER STATION UNITS 2 and 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1992 D2/3 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 SEMI-ELEVATED RELEASES 50-249 XX ELEVATED RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED QUNITl lei QUARTER l 2nd QUARTER l
1st QUARTER.
2nd QUARTER FISSION GASES Xe-138 Ci Xe-135m Ci 3.75E+00 Kr-87 Ci 7.22E-01 Kr-88 Ci 6.92E-02 1
Kr-85m Ci !
1.31E-01 7
Kr-85 l Ci !
1.15E-04 4.69E-04 Xe-135 t Ci !
2.64E+00 t
1.09E+00 Xe-133 Ci !
3.81E-01 TOTAL Ci !
7.69E+00 1.09E+00 Nont None j
I
.1 Ci 9.95E-05 I-133 Ci 1.95E-04 1.05E-03 L
I-135 Ci TOTAL Ci 1.95E-04 1.15E-03 i
None None PARTICULATES Sr-89 Ci '
1.16E-05 3.42E-05 1
' Ci 5.95E-07 7.66E-07 6
Cr-51 Ci Mn-54 Ci 1.28E-04 1.23E-04 f
I 1
Co-58 Ci !
Fe-59 Ci !
Co-60 Ci !
2.670-04 1
2.79E-04 1
Zr-95 Ci !
Nb-95 Ci !
Ru-103 Ci !
1 Ao-110m Ci !
Sb-124 Ci i I-131 Ci !
Cs-134 Ci !
Cs-136 Ci Cs-137 Ci 2.05E-05 2.04E-05 Ba-140 l Ci La-140 Ci !
Ce-141 Ci !
l Ce-144 Ci !
j Zn-65 Ci !
Ba-133 Ci !
Sb-125 Ci !
Fe-55 Ci !
9.56E-04 1.47E-03 f
TOTAL f Ci i 1.3BE-03 1.93E-03 None None
- The activity of this nuclide is less than the LLD listed on the l
appropriate table.
P i
(gn\\pintgr\\c493\\0D85.93)_
l DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT January Through March 1922 D2/3 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 SEMI-ELEVATED RELEASES 50-249 XX ELEVATED RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT' JANUARY FEBRUARY l
KARCH l let QUARTER TOTAL FISSION GASES Xe-138 Ci l
Xe-135m Ci 3.75E*0C 3.75E+00 7.22E-01 7.22E-01 Kr-87 Ci 6.92E-02 6.92E-02 Kr-88 Ci 1.31E-01 1.31E-01 Kr-85m Ci 3.86E-05 7.61E-05 1.15E-04 Kr-85 Ci 1.87E+00 7.71E-01 2.64E+00 Xe-135 Ci Xe-133 Ci 3.46E-02 3.46E-01 3.81E-01 TOTAL
! Ci 2.83E400 4.87E+00 7.69E+00 IODINES I-131 Ci !
7.75E-05 1.17E-04 1.95E-04 I-133 Ci !
I-135 Ci TOTAL Ci 7.75E-05 1.17E-04 1.95E-04 PARTICULATES Sr-89 Ci 6.72E-07 6.18E-06 4.77E-06 1.16E-05 Sr-90 Ci 1.90E-07 2.68E-07 1.37E 5.95E-07 Cr-51 Ci Mn-54 CL 1.54E-05 6.15E-05 5.10E-05 1.28E-04 Co-58 Ci Fe-59 Ci Co-60 Ci 3.27E-05 8.77E-05 1.47E-04 2.67E-04 Zr-95 Ci Nb-95 Ci Ru-103 Ci Aa-110m Ci Sb-124 Ci I-131 Ci Cs-134 Ci 1
Cs-136 Ci Cs-137 Ci 1.31E-05 7.44E-06 2.05E-05 Ba-140 Ci La-140 Ci Ce-141 Ci Ce-144 Ci Zn-65 Ci Ba-133 Ci Sb-125 Ci Fe-55 Ci 1.34E-04 3.92E-04 4.30E-04 9.5CE-04 TOTAL Ci 1.96E-04 5.55E-04 6.33E-04 1.38E-03 The activity of this nuclide is less than the LLD listed on the appropriate table.
(p:\\pintmgr\\cws93\\0085.93)_
r 4
DRESDEN NUCLEAR POWER STATION UNITS 2 and 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT April Through June 1992 D2/3 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 SEMI-ELEVATED RELEASES 50-249 XX ELEVATED RELEASES CONTINUOUS MODE NUCLIDES RELEASED lUNITj APRIL MAY JUNE Znd QUARTER TL FISSION GASES Xe-138 Ci Xe-135m Ci Kr-87 Ci 2
Kr-88 Ci i
Kr-85m Ci Kr-SS Ci 1.12E-04 1.84E-04 1.73E-04 4.69E-04 1.09E+00 Xe-135 Ci 1.09E+00 1
Xe-133 Ci a
TOTAL Ci 1.09E+00 1.84E-04 1.73E-04 1.09E+00 IODINES
+
I-131 Ci !
1.46E-05 1
4.24E-05 4.25E-05 9.95E-05 I-133 Ci 3.00E-04 2.99E-04 4.46E-04 1.05E-03 I-135 Ci TOTAL Ci 3.15E-04 3.41E-04 4.89E-04 1.15E-03 PARTICULATES Sr-89 Ci 1.59E-05 3.60E-06 1.47E-05 3.42E-05 Sr-90 C1 2.87E-07 4.79E-07 7.66E-07 Cr-51 Ci 1.23E-04 Mn-54 Ci 7.79E-05 1
4.53E-05 Co-58 Ci Fe-59 Ci Co-60 C1 1.19E-04 1.08E-04 l
5.23E-05 l
2.79E-04 Zr-95 Ci Nb-95 Ci !
Ru-103 Ci !
Ac-110m Ci Sb-124 Ci I-131 Ci Cs-134 Ci Cs-136 Ci 2.04E-05 Cs-137 Ci 1.24E-05 8.00E-06 Ba-140 Ci La-140 Ci a
Ce-141 Ci i
Ce-144 Ci Zn-65 Ci Ba-J33 Ci Sb-125 Ci i
Fe-55 Ci 8.51E-04 5.37E-04 8.52E.05 1.47E-03 j
TOTAL Ci 1.08E-03 7.02E-04 1.52E-04 1.93E-03 The activity of this nuclide is less than the LLD listed on the i
appropriate table.
j i
l 4
(p:\\pintmgr\\cws93\\0085.93)
DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT January Through June 192.2 D2/3 Rx Buildino Vent GASEOUS EFFLUENTS CROUND LEVEL RELEASES Docket Numbers: 50-237 j
XX SEMI-ELEVATED RELEASES 50-249 l
ELEVATED RELEASES CONTINUOUS MODE BATCH MODE i
EUCLIDES RELEASED jUNITl 1st QUARTER 2nd QUARTER j
let QUARTER M QUARTER j
l FISSION GASES l
Xe-138 Ci l
Xe-135m Ci Kr-87 Ci l
Kr-88 Ci !
Kr-85m Ci !
l Kr-85 Ci !
l l
Xe-135 Ci !
Xe-133 Ci !
TOTAL Ci !
I-131 l Ci 2.18E-07 1.84E-05 i
I-133 Ci 9.19E-05 1
2.20E-04 j
I-135 Ci 6
TOTAL
! Ci 9.21E-05 2.38E-04 NONE NONE i
PARTICULATES Sr-89
! Ci 6.56E-06 3.81E-06 Sr-90
! Ci 5.94E-08 1.81E-07 Cr-51 Ci Ir6(E-04 2.13E-04 t
Mn-54 Ci 4.12E-04 5.89E-04 Co-58 Ci 1.18E-04 2.42E-04 i
Fe-59 Ci 4.57E-05 1.24E-04 Co-60 C1 1.51E-03 2.07E-03 l
Zr-95 Ci Nb-95 Ci Ru-103 Ci l
Aa-110m Ci Sb-124 Ci i
a l
I-131 Ci Cs-134 ci l
Cs-136 Ci Cs-137 Ci 8.89E-06 Ba-It0 Ci 1
La-140 Ci i
Ce-141 Ci Ce-144 C1 t
En-65 Ci 3.18E-05 Ba-133 Ci Mo-99 Ci 8.53E-05
[
j Sb-125 Ci Fe-55 Ci 2.63E-03 4.39E-03 l
TOTAL Ci 5.01E-03 7.62E-03 None None The activity of this nuclide is less than the LLD listed on the appropriate table.
i l
[
5 (p:\\pintmgr\\cws93\\0085.93)_
DRESDEN NUCLEAR POWER STATION UNITS 2 and 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through March 19R D2/3 Rx Buildino Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 5
XX SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED JUNITj JANAURY l
FEBRUARY MARCH l 1st QUARTER FISSION GASES Xe-138 Ci !
Xe-135m Ci !
Kr-87 Ci Kr-88 Ci Kr-85m Ci Kr-85 Ci l
Xe-135 Ci Xe-133 Ci TOTAL Ci 10 DINES 2.18E-07 2.18E-07 I-131
! Ci 2.04E-05 7.15E-05 9.19E-05 I-133
! Ci I-135
! Ci TOTAL
! Ci 2.04E-05 7.17E-05 9.21E-05 PARTICULATES Sr-89
! Ci !
1.85E-07 1
7.96E-07 5.58E-06 6.56E-06 5.94E-08 Sr-90 1 Ci !
3.9BE-08 1.96E-08
' Ci !
3.10E-05 1.35E-04 1.66E-04 Cr-51 Mn-54 Ci !
1.81E-05 1.97E-04 1
1.97E-04 4.12E-04 4.71E-05 7.05E-05 1.18E-04 Co-58 Ci 1.84E-05 2.73E-05 4.57E-05 Fe-59 Ci
)
Co-60 Ci 1.29E-04 6.85E-04 6.92E-04 1.51E-03 l
Zr-95
! Ci l
Nb-95
! Ci !
a Ru-103 Ci !
Aa-110m Ci !
Sb-124 Ci !
I-131 1
Ci Cs-134
! Ci Cs-136 Ci 1.68E-06 8.89E-06 Cs-137 Ci !
7.21E-06 l
Ba-140 Ci !
La-140 Ci !
Ce-141 Ci !
Ce-144 Ci !
- n-65 Ci 1.97E-05 1.21E-05 3.18E-05 Ba-133 Ci 8.51E-05 8.51E-05 Mo-99 Ci a
Sb-125 Ci !
! Ci !
3.32E-04 1.04E-03 1.26E-03 2.63E-03 TOTAL
! Ci !
4.86E-04 2.04E-03 2.49E-03 5.01E-03 The activity of this nuclide is less than the LLD listed on the i
appropriate table.
l (p:\\ptntmgr\\cws93\\0085.93)_
F DRESDEN NUCLEAR POWER STATION UNITS 2 and 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL PEPORT I
April Through June 1912_2 D 2/3 Rx Buildino Vent GASEOUS EFFLUENTS f
GROUND LEVEL RELEASES Docket Numbers: 50-237 XX SEMI-ELEVATED RELEASES 50-249 f
ELEVATED RELEASES i
CONTINUOUS MODE NUCLIDES RELEASED l UNIT /
APRIL l
MAY JUNE 2nd QUARTER TOTAL i
FISSION GASES !
l Xe-138 ci a
Xe-135m ci L
Kr-87 ci !
1 Kr-88 Ci !
Kr-85m ci !
Kr-85 ci
?
Xe-135 ci Xe-133 ci TOTAL ci IODINES I-131 l
Ci !
6.23E-06 2.67E-06 9.50E-06 1.84E-05 i
I-133 i
ci !
9.07E-05 1.91E-05 1.1cE-04 2.20E-04 I-135 ci TOTAL ci 9.69E-05 2.18E-05 1.20E-04 2.38E-04 PARTICULATES t
Sr-89
! Ci 1.25E-06 1.21E-06 1.35E-06 3.81E-06 1.81E-07 1.81E-07 Sr-90
! Ci Cr-51
! Ci 1.19E-04 9.42E-05 2.13E-04 Mn-54
! ci 2.59E-04 7.36E-05 2.56E-04 5.89E-04 Co-53 ci 6.70E-05 5.49E-05 l
1.20E-04 2.42E-04 i
6.20E-05 1.24E-04 Fe-59 ci 6.19E-05 Co-60 ci 6.96E-04 3.49E-04 1.02E-03 2.07E-03 Zr-95 Ci Nb-95 ci l
Ru-103
! Ci Ac-110m
,1 ci Sb-124 ci !
I-131 ci !
Cs-134 ci Cs-136 ci 4
Cs-137 Ci 1
Ba-140 ci La-140 t ci a
a a
Ce-141 ci Ce-144 ci l
Sb-125 ci !
' ci !
1.33E-03 6.97E-04 2.35E-Ol_
4.3BE-03 TOTAL
! Ci !
2.53E-03 1.18E-03
?
3.90E-03 7.62E-03 i
- The activity of this nuclide is less than the LLD listed on the appropriate table.
i (p:\\ptntmgr\\cws93\\0085.93).
)
t DRESDEN NUCLEAR POWER STATION UNITS 1, 2, and 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1991 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237 50-249 EST. TOTAL [
UNITS let QUARTER 2nd QUARTER ERROR,4 A.
FISSION AND ACTIVATION PRODUCTS Ci 1.47E-02 6.31E-03 5.58 no ic tritium, gases, alpha) a
- 2. Average Diluted cone. During Period uci/mL 6.52E-09 1.98E-09 t
- 3. Percent of Applicable Limit B.
TRITIUM l
l
- 1. Total Release Ci
' l.24E+00 !1.54E+00 5
- 2. Average Diluted Conc. During Period uCi/mL 5.50E-07 l4.83E-07 j
- 3. Percent of Applicable Limit C.
DISSOLVED AND ENTRAINED GASES l
- 1. Total Release Ci j 1.64E-05
< LLD 5.58 1
- 2. Average Diluted Conc. During Period uCi/mL 7.29E-12
< LLD j
- 3. Percent of Applicable Limit t
l D.
GROSS ALPHA RADIOACTIVITY j.,
- 1. Total Release l
15.1 f
f E.
VOLUME OF WASTE RELEASED (prior to dilution) l Liters j 4.36E+06 l3.09E+06 l 5.00 l
l l
F.
VOLUME OF DILUTION WATER USED DURING PERIOD l
liters l2.25E+09 j 3.19E+09 j 5.00 l
a
- 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.
b I
r On \\ptningr\\cws93\\0085.93)_
f I
I DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 l
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 l
50-249 l
NUCLIDE LLD (uCi/mL)
Fr-89 7.00E-08*
Sr-90 5.02E-09 l
Mn-54 5.50E-08 Co-58 4.20E-08 i
Fe-59 9.30E-08 co-60 1.23E-07 In-65 1.20E-07 l
Sb-124 4.50E-08 I-131 4.50E-08 Cs-134 4.60E-08 i
Cs-137 7.20E-08 Ba-140 2.20E-07 l
La-140 4.60E-08
[
Ce-141 6.90E-08 l
Xe-133 1.20E-07
}
Xe-135 4.20E-08 Cr-51 3.70E-07 Fe-55 1.50E-07
[
Cs-138 3.10E-07 H-3 3.00E-07 Gross Alpha 8.00E-08 Zr-95 9.80E-08 f
Kr-87 1.50E-07 Kr-88 1.70E-07 I-135 2.10E-07 1
I-132 6.70E-08 Aa-110m 5.90E-08 Ba-133 6.00E-08 e
Ce-144 3.10E-07 i
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 i
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 6
- This limit was reported as an MDA by the of f site vendor for CCSW samples for discharges from 06-13-92 to 06-16-92.
All other discharge samples had MDAs reported at less than or equal to 1.00E-08 uCi/ml.
f 1
4 I
(p:\\pintmgr\\cws93\\D085.93) v
i h
f DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT j
t January Through June 1991 Radwaste LIQUID EFFLUENTS Docket Numbers: 50-10 l
50-237 i
1.
Number of Batch Releases:
71 50-249 2.
Total Time Period for Batch Releases:
1.83E+04 min i
3.
Maximum Time Period for a Batch Release:
3.74E+02 min l
4.
Average Time Period for Batch Releases:
2.57E+02 min 5.
Minimum Time Period for a Batch Release:
1.52E+02 min 6.
Average Stream Flow During Periods of f
Release of Effluent into a Flowing Stream:
3.00E405 L/ min i
CONTINUOUS MODE BATCH MODE PiUCLIDES RELEASED UNITj Ist QUARTER j
M QUARTER j
1st QUARTER 2nd QUARTER
(
7.81E-06 Sr-89 Ci o
l Fe-59 Ci 8.15E-05 Co-60 Ci 7.69E-03 2.52E-03
.i Zn-65 Ci Ru-103 Ci Ac-110m Ci Sb-124 Ci j
I-131 Ci Cs-134 Ci 1
Cs-137 Ci !
2.14E-03 2.08E-03 Ba-140
! Ci '
La-140 Ci I
Ce-141 Ci Cs-138 Ci Fe-55 Ci 1.01E-03 7.44E-04 i
I Zr-95 Ci I - 132 Ci I-134 Ci Bi-214
! Ci 1.60E-05 (above)
Tota 1 For Peri _od Ci NONE NONE 1.47E-02 6.30E-03 Xe-133 Ci Xe-135 Ci 1.64E-05 Ci l
Kr-88 The activity of this nuclide is less than the LLD listed on the appropriate table.
i f
i k
t t
f
?
t i
t (p:\\pintmgr\\cws93\\D085.93),
}
i
i l
DRESDEN NUCLEAR POWER STATION l
UNITS 1, 2, AND 3 4
I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through tiarch 1991 Radwaste LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 l
50-249 I
BATCH MODE NUCLIDES RELEASED LUNIT.
JANUARY FEBRUARY MARCH n
let QUARTER TOTAL r
Fr-f9 C1
[
Sr-90 Ci Hn-54 ci 5.79E-04 1.43E-03 1.79E-03 3.80F-03 3.94E-06 3.94E-06 l
,,_ _ _ _ Co-5 8 Ci 8.15E-05 8.15E-05
_ Fe-59 Ci Co-60 Ci 2.20E-03 2.60E-03 2.89E-03 7.69E-03 f
i t
Zn-65 Ci Ru-103 Ci
~
l An-110m Ci !
i sb-124 Ci !
! Ci Cs-134
! Ci Cs-137
' Ci 1.24E-03 4.64E-04 4.32E-04 2.14E-03 l
)
Ba-140 Ci e
La-140 Ci f
Cs-138 Ci Fe-55 Ci 6.10E-04 2.74E-04 1.23E-04 1.01E-03 l
I-132 Ci I-134 Ci !
1.60E-05 1.60E-05 Bi-214 C1 '
(above)
Ipj;al For Period Ci 4.63E-03 4.78E-03 5.32E-03 1.47E-02 j
I Xe-133 Ci I
Xe-135 Ci !
6.02E-06 1.04E-05 1.64E-05 I
The activity of this nuclide is less than the LLD listed on the appropriate table.
I i
i l
3 I
t r
f t
f I
i b
(p:\\ptntnq+\\cws93\\0085.93),
i
e DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Ar.r il Through June 1911 Radwaste LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 1
50-249 BATCH MODE WUCLIDES RELEASED l UNIT" APRIL MAY l
JUNE l
2nd QUARTER TOTAL Sr-89 Ci 7.81E-06 7.81E-06 Sr-90 Ci 6.09E-06 5.81E-07 7.23E-07 7.39E-06 Mn-54 Ci 4.92E-04 2.10E-04 2.34E-04 9.36E-04 Co-58 Ci Fe-59
! Ci Co-60 1 Ci 3.16E-03 l
S.86E-04 7.69E-04 2.52E-03 t
2n-65 Ci !
I Sb-124 Ci !
I-131 Ci !
Cs-134 Ci Cs-137
! Ci 1.27E-03 2.88E-04 i
5.24E-04 2.08E-03
(
Ba-140 t Ci L
La-140
! Ci f
=
Ce-141 Ci Cs-138 Ci Fe-55 C1 1.99E-04 1.27E-04 4.18E-04 7.44E-04 I-132 Ci Ci l
! Ci (above) l Total For Period Ci 3.13E-03 1.21E-03 1.95E-03 6.30E-03 i
l 1
! Ci j
Xe-135
! Ci The activity of this nuclide is less than the LLD listed on the i
appropriate table.
l i
a i
d I
]
I i
i f
i d
i d
~
i I
l i
(p:\\pintmgr\\cws93\\DD85.93).
b e
i
E DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT i
.Tanuary Throuch June 19.91 CCSW LIQUID EFFLUENTS Docket Numbers: 50-237 50-249 1.
Number of Batch Releases:
72 2.
Total Time Period for Batch Releases 8.93E+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 5.
Minimum Time Period for a Batch Release:
1.24E+00 min 6.
Average Stream Flow During Periods of Release of Effluent into a Flowing Stream:
1.94E+06 L/ min CONTINUOUS MODE BATCH MODE i
NUCLIDES RELEASED UNITj 1st QUARTER 2nd QUARTER l
1st QUARTER 2nd QUARTER Sr-89 Ci Sr-90 Ci 1.80E-06 7.75E-07 Mn-54 Ci Co-58 Ci !
i Fe-59 Ci !
Co-60 Ci 1.13E-05 2.91E-06 Zn-65 Ci Sb-122 Ci !
Sb-124 Ci !
1 I-131
! Ci !
I-132 Ci t l
I-135 Ci Os-134 Ci Cs-137 Ci 2.60E-06 6.39E-06
(
Ba-140 Ci f
La-140 Ci Cs-138 Ci i
i Fe-55 Ci ci J
Ci l
Ci Ci (above) l Total For Period Ci NONE NONE 1.55E-05 1.01E-05 j
Xe-133 Ci !
Xe-135 Ci !
l The activity of this nuclide is less than the LLD listed on the appropriate table.
i
.r i
P l
[
l (p:\\pintmgr\\cws93\\DOBS.93)_
f
DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through March 1992 CCSW LIQUID EFFLUENTS Docket Numbers: 50-237 EO-249 BATCH MODE NUCLIDES RELEASED jUNITj JANAURY FEBRUARY MARCH let QUARTER TOTAL Sr-89
! Ci !
Sr-90 Ci 5.13E-07 1.29E-06 1.80E-06 Mn-54 Ci l
Co-58 Ci F_e-59 Ci Co-60 Ci !
5.31E-06 2.07E-06 3.68E-06 1.11E-05
~
Zn-65 Ci !
Sb-122 Ci Sb-124 Ci I-131 Ci I-132 Ci !
l I-135 Ci !
Cs-134 Ci !
6.60E-07 1.94E-06 2.60E-06 Cs-137 Ci !
Ba-140 Ci !
La-140 Ci !
Cs-138 ci !
! Ci '
! Ci
! Ci
! Ci
! Ci (above) l j
s Total For Period i ci 5.31E-06 1
3.24E-06 6.91E-06 1.55E-05 Xe-133
! Ci !
Xe-135
! Ci !
j The activity of this nuclide is less than the LLD listed on the appropriate table.
4 J
4 d
M i
j (p:\\pt nimgr\\cvs93\\0085.93),
I t
i DRESDEN NUCLEAR POWER STATION i
UNITS 2 AND 3 i
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT j
April Through June 1992 j
)
CCSW LIQUID EFFLUENTS Docket Numbers: 50-237 50-249 1
i BATCH MODE NUCLIDES RELEASED l UNIT APRIL j
MAY l
JUNE j
2nd QUARTER TOTAL Sr-89 Ci i
7.75E-07 Sr-90 Ci 6.76E-07 9.86E-08 1
Mn-54 Ci Co-58 Ci !
Fe-59 Ci
=
2.91E-06 Co-60 C1 2.91E-06 i
=
Zn-65 Ci Sb-122
! Ci
[
' Ci Sb-124 I-131 Ci I-132 Ci i I-135
! Ci !
=
l Cs-134
! Ci !
Cs-137 Ci !
1.37E-06 2.36E-06 2.66E-06 6.39E-06 l
i 1
Ba-140 Ci i I
j La-140 Ci !
Cs-138 Ci l
l Fe-55 Ci t
Ci I
Ci i
(
i j
Ci l
! Ci i
(above) j Total For Period Ci 4.96E-06 l
2.46E-06 2.66E-06 1.01E-05 t
Xe-133 Ci _J_
{
i Xe-135 Ci !
The activity of this nuclide is less than the LLD listed on the appropriate table.
l 4
i h
i Y
i c
1 0p:\\pintrmr\\ews93\\0085.93)_
l 3
I
.., i
\\
1 DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 l
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1992 Docket Numbers: 50-10 50-237 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 50-249 Est Tot.
i A.
SOLID WASTE SHIPPED OFFSITE FOR BURI AL OR DISPOSAL (NOT IRRAD ATED FUEL)
Error,%
Unit 6-month period 1.
Type of Waste m3 2.04E+02 a.
Spent resins, filter sludges, evaporator bottoms, etc.
Ci 1.70E+03 12.4 m3 9.95E+02 b.
Dry compressible waste, contaminated equip., etc.
C1 2.99E+01 16.6 m
0.OOE+00 c.
Irradiated components, control rods, etc.
Ci O.OOE+00 16.6 f
m3 0.OOE+00 d.
Other (describe)
Ci O.OOE+00 2.
Estimate of Major Nuclide Composition (by type of waste)
Ci a.
Co-60 66.6 1.13E+03 ?
f Fe-55 1.34 2.28E+01 Mn-54 14.2 2.41E+02 Ni-63 11.6 1.97E+02 Cs-137 3.02 5.13E+01 b.
Co-60 21.2
! 6.34E+00 li Fe-55 64.4 1.93E+01 Mn-54 6.15 1.84E+00 Ni-59 1.32 4.01E-01 Ni-63 1.02 3.05E-01 Cs-137 1
5.14 1.54E+00 l
3.
Solid Waste Disposition NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION l
43 Motor freight (exclusive use only)
CNSI, Barnwell, SC 4
Motor freight (exclusive use only)
Quadrex, Oak Ridge, TN 9
Motor freight (exclusive use only)
CNSI, Channahon, IL
{
7 Motor freight (exclusive use only)
SEG, Oak Ridge, TN 23 Motor freight (exclusive use only)
US Ecology, Beatty, NV l
B.
IRRADIATED FUEL SHIPMENTS (Disposition)
EUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 1
Motor Freight (Highway Route Babcock and Wilcox Controlled)
Lynchburg, VA.
a
)
a i
(p:\\pintmgr\\nns93\\0DB5.93) f
I
\\
i l
l i
DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1912 j
ABNORMAL RELEASES A.
LIQUID e
1.
Number of Releases:
0 2.
Total Activity Released:
0 B.
GASEOUS f
1.
Number of Releases:
4 2.
Total Activity Released:
2.45E-03 Ci 7
TOTAL 4
1.
On January 9,1992, a backup sample pump was placed in service fo: Unit I chimney at 13:30.
The sampler was discovered with a blown f*ase on t
January 10, 1992 at 08:00.
Sampling was re-established at 09:30. The estimLted activity released is.
i Cs-137 1.10E-06 Ci Sr-90 4.09E-10 Ci Gross Alpha 1.95E-08 Ci H-3 5.99E-05 Ci j
)
2.
On February 11, 1992, the Units 2/3 Reactor Building Ventilation Stack Samples were not analyzed for the period from 08:25 to 16:15.
The
{
primary sampler (SPING) was out of service for modification work on a i
motor control center during this period. At the filter pull on February 18, 1992, the backup filters were not identified as the proper samples and therefore they - were not analyzed.
Corrective actions entail analyzing primary and backup samples at each filter pull (LER 92-09).
The estimated activity released is:
l l
I-133 5.22E-07 Ci Mn-54 1.93E-06 Ci j
Co-58 5.3BE-07 Ci 4
Co-60 7.06E-06 Ci' Zn-65 1.04E-07 Ci Fe-55 6.39E-06 Ci l
Sr-89 4.27E-09 Ci Sr-90 9.20E-10 Ci j
Gross Alpha 7.22E-09 Ci j
H-3 9.43E-04 C1 3
i h
e f
(p:\\pintegr\\en93\\0DB5.9 ).
DRESDEN NUCLEAR POWER STATION UNITS 1, 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT January Through June 1991 l
ABNORMAL RELEASES 3.
The Unit 1 Chimney Backup Sampler was found with a blown fuse on April 9, 1992 at 07:15. The sampler was last known to be running at 15:45 on April 8, 1992. The blown f use was discovered to be the wrong size. All 7
samplers of this type were then checked for proper fuses. Correct size fuses are currently installed.
(DVR #12-1-92-04)
The estimated activity during the unsampled period is:
Fe-55 2.llE-08 Ci Co-60 1.5DE-06 Ci i
Sr-89 2.69E-09 Ci H-3 4.65E-05 Ci t
4.
On March 22, 1992 at 01:00, the Unit 2/3 Chimney G.E.
System (backup sampler) flow was restricted by a f ailed fuse for a solenoid, causing a valve to close.
The 2/3 Chimney SPING was placed in service at 03:35.
l The estimated activity during this period is:
t Fe-55 1.16E-06 Ci Sr-89 2.88E-05 Ci H-3 1.35E-03 Ci 4
j i
[
4 r
4 l
5 i
i i
(
n s
t i
5 i
i r
I i
(p:\\ptntmgr\\cws93\\00BS.93)_
i
~
+
3 i
i h
f DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 f
i
\\
RADIOLOGICAL IMPACT ON MAN e
s i
r
[
t 1
i i
+
1 i
i l
r i
a
?
y-t h
t t
4 t
(p:\\ptntmgr\\cws93\\0085.93),
i 4
u--
e y
ce
P i
DRESDEN UNIT ONE 1992 ANNUAL REPORT l
MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/22/93 INFANT 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 1.07E-05 7.68E-06 1.14E-06 1.11E-06 2.04E-05 (MREM)
(SE
)
(SE
)
(N
)
(N
)
(SE
)
LIVER LIVER L'JNG LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1992 COMPLIANCE STATUS - 10 CFR 50 APP. I INFANT RECEPTOR
% OF APP I.
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAli-MAR APR-JUN JUL-SEP OCT-NOV 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 LIVER LIVER LUNG LIVER LIVER RESULTS BASED UPO!
ODCM ANNEX REVISION O FARCH 1989
^ ^ ^ ^ - - - - - - - - -
DRESDEN UNIT ONE l
l 1992 ANNUAL REPORT l
MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/22/93 ADULT 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 9.44E-06 1.32E-05 6.78E-06 4.40E-06 3.39E-05 (MREM)
(SE
)
(SE
)
(SE
)
(SE
)
(SE
)
r LIVER LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1992 4
l I
COMPLIANCE STATUS - 10 CFR 50 APP. I ADULT RECEPTOR l
t
% OP APP I.
QTRLY iST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV 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 i ORGAN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 LIVER LIVER LIVER LIVER LIVER RESULTS BASED UPON!'
ODCM ANNEX REVISION 0 MARCH 1989 i
I!P
DRESDEN UNIT TWO 1992 ANNUAL REPORT MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/26/93 INFANT RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 1.47E-04 5.95E-06 3.83E-06 1.05E-05 1.68E-04 (MRAD)
(NE
)
(NE
)
(NE
)
(NE
)
(NE
)
BETA AIR 2.00E-05 1.25E-06 8.07E-07 2.20E-06 2.43E-05 (MRAD)
(N
)
(N
)
(N
)
(N
)
(N
)
TOT. BODY 7.20E-05 2.50E-06 1.61E-06 4.40E-06 8.05E-05 (MREM)
(NE
)
(NE
)
(NE
)
(NE
)
(NE
)
SKIN 1.30E-04 5.47E-06 3.52E-06 9.61E-06 1.48E-04 I
(MREM)
(NE
)
(NE
)
(NE
)
(NE
)
(NE
)
ORGAN 1.47E-02 8.65E-03 8.59E-04 1.72E-03 2.58E-02 (MREM)
(NNE )
(NNE )
(NNE )
(NNE )
(NNE )
j LUNG LUNG THYROID LUNG LUNG j
THIS IS A REPORT FOR THE CALENDAR YEAR 1992 1
6 i
COMPLIANCE STATUS - 10 CFR 50 APP. I INFANT RECEPTOR r
% OF AFP I.
QTRLY iST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV OBJ APP.I j f
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 t SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.20 0.12 0.01 0.02 15.0 0.17 i
LUNG LUNG THYROID LUNG LUNG RESULTS BASED UPONf ODCM ANNEX REVISION O MARCH 1989 i
DRESDEN UNIT TWO 1992 ANNUAL REPORT MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/26/93 ADULT RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 1.47E-04 5.95E-06 3.83E-06 1.05E-05 1.68E-04
+
(MRAD)
(NE
)
(NE
)
(NE
)
(NE
)
(NE
)
BETA AIR 2.00E-05 1.25E-06 8.07E-07 2.20E-06 2.43E-05 (MRAD)
(N
)
(N
)
(N
)
(N
)
(N
)
TOT. BODY 7.20E-05 2.50E-06 1.61E-06 4.40E-06 8.05E-05 (MREM)
(NE
)
(NE
)
(NE
)
(NE
)
(NE
)'
SKIN 1.30E-04 5.47E-06 3.52E-06 9.61E-06 1.48E-04 (MREM)
(NE
)
(NE
)
(NE
)
(NE
)
(NE
)
ORGAN 1.50E-02 8.98E-03 1.01E-03 1.89E-03 2.67E-02 (MREM)
(NNE )
(NNE )
(NNE )
(NNE )
(NNE )
LUNG LUNG THYROID LUNG LUNG THIS IS A REPORT FOR THE CALENDAR YEAR 1992 COMPLIANCE STATUS - 10 CFR 50 APP. I ADULT RECEPTOR i
% OF APP I.
% OF 8
4 OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV OBJ APP.I 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 SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00,
ORGAN (MREM) 7.5 0.20 0.12 0.01 0.03 15.0 0.18,
LUNG LUNG THYROID LUNG LUNG RESULTS BASED UPON-ODCM ANNEX REVISION O MARCH 1989
[!p 5
DRESDEN UNIT THREE 1992 ANNUAL REPORT MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/26/93 l
INFANT RECEPTOR 1
IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUART.*ER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 0.00E+00 9.59E-06 1.45E-05 3.35E-05 5.75E-05 (MRAD)
(
)
(NE
)
(NE
)
(NE
)
(NE
)
BETA AIR 0.00E+00 2.02E-06 3.05E-06 7.05E-06 1.21E-05 (MRAD)
(
)
(N
)
(N
)
(N
)
(N
)
TOT. BODY 0.00E+00 4.03E-06 6.08E-06 1.41E-05 2.42E-05 (MREM)
(
)
(NE
)
(NE
)
(NE
)
(NE
)
SKIN 0.00E+00 8.81E-06 1.33E-05 3.07E-05 5.28E-05 (MREM)
(
)
(NE
)
(NE
)
(NE
)
(NE
)
i ORGAN 6.82E-04 1.24E-02 4.32E-03 9.86E-03 2.66E-02 (MREM)
(NNE )
(NNE )
(NNE )
(NNE )
(NNE )
LUNG LUNG THYROID LUNG THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 1992 f
COMPLIANCE STATUS - 10 CFR 50 APP. I INFANT RECEPTOR
(
% OF AFP I.
QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV 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 i
ORGAN (MREM) 7.5 0.01 0.16 0.06 0.13 15.0 0.18 I
LUNG LUNG THYROID LUNG THYROID RESULTS BASED UPON ODCM ANNEX
?
REVISION 0 MARCH 1989 1
)
J l
DRESDEN UNIT THREE 1992 ANNUAL REPORT MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/26/93 ADULT RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 0.00E+00 9.59E-06 1.45E-05 3.35E-05 5.75E-05 (MRAD)
(
)
(NE
)
(NE
)
(NE
)
(NE
)
BETA AIR 0.00E+00 2.02E-06 3.05E-06 7.05E-06 1.21E-05 (MRAD)
(
)
(N
)
(N
)
(N
)
(N
)
TOT. BODY 0.00E+00 4.03E-06 6.08E-06 1.41E-05 2.42E-05 (MREM)
(
)
(NE
)
(NE
)
(NE
)
(NE
)
SKIN 0.00E+00 8.81E-06 1.33E-05 3.07E-05 5.28E-05 (MREM)
(
)
(NE
)
(NE
)
(NE
)
(NE
)
ORGAN 6.92E-04 1.37E-02 5.04E-03 1.05E-02 2.89E-02 (MREM)
(NNE )
(NNE )
(NNE )
(NNE )
(NNE )
LUNG GI-LLI THYROID LUNG GI-LLI THIS IS A REPORT FOR THE CALENDAR YEAR 1992 o
COMPLIANCE STATUS - 10 CFR 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-NOV 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 0.01 0.18 0.07 0.14 15.0 0.19 LUNG GI-LLI THYROID LUNG GI-LLI j
RESULTS BASED UFO!-
ODCM ANNEX REVISION-0 MARCH 1989 l
[tp
i DRESDEN UNIT TWO INFANT RECEPTOR 1992 ANNUAL REPORT MAXIMUM DOSES (MREM) RESULTING FROM LIQUID EFFLUENTS PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.09E-05 9.95E-06 5.41E-06 2.21E-06 2.85E-05 BODY INTERNAL 2.67E-05 2.65E-05 6.43E-06 3.22E-06 6.29E-05 ORGAN LIVER LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1992 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-NOV OBJ APP.I TOTAL BODY (MREM) 1.5 0.00 0.00 0.00 0.00 3.0 0.00t CRIT. ORGAN (MREM) 5.0 0.00 0.00 0.00 0.00 10.0 0.00:
LIVER LIVER LIVER LIVER LIVER RESULTS BASED UPO5 ODCM ANNEX REVISION 0 MARCH 1989 f
e F
DRESDEN UNIT TWO i
INFANT RECEPTOR 1992 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM.*
[
PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 l
1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.09E-05 9.95E-06 5.41E-06 2.21E-06 2.85E-05 BODY INTERNAL 2.67E-05 2.65E-05 6.43E-06 3.22E-06 6.29E-05 ORGAN LIVER LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1992 l
l l
COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT
% OF LIMIT TOTAL 4.0 (MREM) 0.001 BODY 0.002 INTERNAL 4.0 (MREM)
ORGAN LIVER 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 l
MARCH 1989 l
l l
h l
i h
r i
DRESDEN UNIT TWO ADULT RECEPTOR 1992 ANNUAL REPORT MAXIMUM DOSES (MREM) RESULTING FROM LIQUID EFFLUENTS PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 3.51E-05 3.70E-05 3.91E-06 2.76E-06 7.87E-05 INTERNAL 5.23E-05 5.47E-05 5.01E-06 3.83E-06 1.16E-04 BODY ORGAN LIVER LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1992 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-NOV OBJ APP.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. 0 f:
LIVER LIVER LIVER LIVER LIVER RESULTS BASED UP ODCM ANNEX REVISION 0 MARCH 1989 i
1 l
1
i k
DRESDEN UNIT TWO ADULT RECEPTOR 1992 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM,*
PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 t
1ST 2ND 3RD 4TH t
DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 4.94E-06 5.00E-06 1.93E-06 8.46E-07 1.27E-05 INTERNAL 7.03E-06 5.90E-06 2.03E-06 9.11E-07 1.48E-05 i
BODY ORGAN GI-LLI LIVER GI-LLI LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1992 COMPLIANCE STATUS - 40 CFR 141 ANNUAL LIMIT
% OF LIMIT TYPE TOTAL 4.0 (MREM) 0.000 BODY 0*000 f
INTERNAL 4.0 (MREM)
ORGAN LIVER
+
i THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE i
COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIF FROM THOSE DESCRIBED IN 40 CFR 141.
RESULTS BASED UPON; ODCM ANNEX i
REVISION O l
MARCH 1989 i
!!P r
i i
1 e
i l
i DRESDEN UNIT THREE INFANT RECEPTOR t
1992 ANNUAL REPORT MAXIMUM DOSES (MREM) RESULTING FROM LIQUID EFFLUENTS PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 L
IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.19E-05 1.00E-05 5.38E-06 2.19E-06 2.95E-05 INTERNAL 3.03E-05 2.66E-05 6.31E-06 2.69E-06 6.60E-05 BODY ORGAN LIVER LIVER LIVER LIVER LIVER IS A REPORT FOR THE CALENDAR YEAR 1992 THIS 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-NOV OBJ APP.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 LIVER RESULTS BASED UPON!
ODCM ANNEX REVISION 0 MARCH 1989 l
4 3
1 I
DRESDEN UNIT THREE INFANT RECEPTOR 1992 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.19E-05 1.00E-05 5.38E-06 2.19E-06 2.95E-05 BODY INTERNAL 3.03E-05 2.66E-05 6.31E-06 2.69E-06 6.60E-05 ORGAN LIVER LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1992 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT
% OF LIMIT TOTAL 4.0 (MREM) 0.001 BODY INTERNAL 4.0 (MREM) 0.002 ORGAN LIVER o
THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH FDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141.
l RESULTS BASED UPON' ODCM ANNEX REVISION O MARCH 1989 l
j
t DRESDEN UNIT THREE ADULT RECEPTOR 1992 ANNUAL REPORT MAXIMUM DOSES (MREM) RESULTING FROM LIQUID. EFFLUENTS PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 4.13E-05 3.71E-05 3.71E-06 1.78E-06 8.39E-05 BODY INTERNAL 6.16E-05 5.49E-05 4.72E-06 2.34E-06 1.24E-04 ORGAN LIVER LIVER LIVER LIVER LIVER E
THIS IS A REPORT FOR THE CALENDAR YEAR 1992 COMPLIANCE STATUS - 10 CFR 50 APP. I
% OF APP I.
QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY
% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV OBJ APP.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 r
LIVER LIVER LIVER LIVER LIVER RESULTS BASED UPON ODCM ANNEX REVISION 0 MARCH 1989 I
\\
m.
=.
DRESDEN UNIT THREE ADULT RECEPTOR 1992 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM
- PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 IST 2ND 3RD 4TH DOSE TYPE QUARTEK QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 5.44E-06 5.03E-06 1.91E-06 7.86E-07 1.32E-05 BODY INTERNAL B.49E-06 5.91E-06 2.00E-06 8.56E-07 1.55E-05 ORGAN
+
GI-LLI LIVER GI-LLI GI-LLI GI-LLI THIS IS A REPORT FOR THE CALENDAR YEAR 1992 1
d COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT
% OF LIMIT i
TOTAL 4.0 (MREM) 0.000 BODY INTERNAL 4.0 (MREM) 0.000 ORGAN GI-LLI 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 MARCH 1989
[Ip l
1
3 i
l 5
1 DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 l
t METEOROLOGICAL DATA i
r i
+
t 6
t 4
e l
t i
i l
t 5
i 1
i i
6 f
r t
i i
t i
I t
(p:\\ptntmgr\\cws93\\0085.93),
6
a CitoCRISCIISTATICX huary-partti Ill!
35 ft.130 SPIED m! VII DIRitTICI 150-35 ft. IIFTilill!Al IINFERATURI i
ItXillDFOBSERVA110XS: 2184 HlDISARIFEltEKIDCCURREkt!
- =.........._.... IlhD CIRiti!OR CLASSES ----------
$1111tIII 'lAS$!$ ------
sp((p CLASS I kli EI Iki I
$$t SI til I
Vkt it att TOTAL IU U SU i
SS KS IS isfA5 10.00.00.00.00.00.00.00.00.00.00.00.00.50.00.00.00
.00.00 0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 t 50.00.00.00.00.50.00.00.00.00.00.00.00.00.00.00.00
.00
.00 A I.00.00.00.00.00.00.00.00.00.00
.t>0
.00.00.00.00.00
.00
.33 L SS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 4 WS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.08
.00
.00 ES.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 N
EU.00.09.00.00.00.00.00.00.00.00.05.00.05.05.00.00
.23.23 H.00.05.00.00.00.05.05.09.05.00.05.09.00.00.00.01
.50
.50 1SU.00.00.00.00.t5 '.00.05.05.00.05.00.00.00.05.05.tl
.37
.37
-R
.18.23.23.09 11.14.14
.09.18.18.14
.14
.05
.41.27.27 2.13 2.13 3SS.05
.14
.00 18.09.09.14.09
.18.18.05
.14.14.32 18.11 2.15 2.15
($.00.00.00.00.00.09.05.18
.14.09.09.00.00.05.!!.tl
.96
.11 ES.05.t!.00.05.09.09.05.00.09.01.01.05.00.09.05.05
.87
.li f.C 7
14.09.09.05.23.ta.09.09.09.01.tl.37.37.!!
46.21 3.94 3.14 G.01.18.05.09.09.32.18.18.09.05.14
.14.14.14.18.tl 2.15 2.15 4 SU.09.05.23.11,18.09.18.09.09.00.00.05.23.18.11.01 1.92 1.92
- X 1.01.962.011.!11.421.371.47.27.37.50.32
.18 1.11 1.t$.12 1.33 18.48 16.4!
i SS.50.23.23.05.32 1.12.!!.!2.87 1.05.18.23 1.37.ti.09.78 10.44 10.44 NS.00.00.05.00.05.ti.21.14.23.50.!!
.18.05
.14.00.00 2.56 2.fi IS.00.00.00.00.00.05.00.05.05.18.09
.01.09.00.00.tt
.50
.50 3t..
EU 1.05.64.21.23.f4.32.27.23.23.32.23.21.21 1.05 1.14 1.50 !.il B.il U.09.00.tl
.14
.14
.05.18.tl.01.09.05.00.23.21.50.14 2.11 2.11 i SU.14
.05.09.23.3!.46.05.09.tl.05.12.09.23.31.!!.23 3.21 3.21 r
-E
.li.52.!!.73 1.05 2.75.78.!! 1.01-.56 1.10.!! 1 !! 2.15 2.15 1.01 11.11 ff.fi 1 $$.00.00.00.00.05.09.23
.46.82.li.37.00.t5.14.00 3.34 3.34 2RS.00.00.00.00.00.00.00.00.00.00.01.05.00.00
.00.
00
.14
.14 ES.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 37.'
IO.14
.00.00.00.05.05.00.01
.14.18.18.37.23
.14.55 45 2.!6 2.!i tW.37.tl.00 00.00.05.00.00.t5.23.t9.09.00.!!.18.11 1.42 1.42 3 SU.05
.14.00.05.00.05.00.00.!!,41.09.05
.14
.18.05.14 1.50 1.60
-N
.37
.18.C5.00.14.50 46.21.it 1.01 45.23.50.f4 1.24 1.ti f.Il i.fi 1SS.00.00.00.00.00.00.00.00.23.05.14
.00.00.to.00.O!
46 41 INS.00.00.00.00.t0.00.00.00.00.00.t0.00.00.00.00.t!
.00
.00 15.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 13.i
titoCREs0[ISTATICE January-Farch Ill!
15ft.IIt0SPII0staIIk0!!Rit110X 150-35ft.DIfflifti!AlilstlR4TRI
ST Allitif TUSSIS ----------
----- IMS DIPHIEt (U55[S
-=----- --
SPEED ftASS # liki
!! Inf f
$ SSV St fit I
ur kt kku TOTAL ID RD SU R
=
EU.00.00.00.00.00.00.00.00.!!.32.32.05.00.t5.05 46 1.51 1.51 1 Kil.00.00.00.00.00.00.00. 00.09.05.00.00.00.00.05.08
.2i
.21 1 SU.00.00.00.00.00.00.00.00.01.00.00.00.00.09.05.00
.23
.23
-t
.00.00.00.00.00.00.00.00.05.C5.00.00.00.11.01.14
.50
.50 2SS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 4KS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.00 15.00.C0.00.00.00.00.00.00.00.00.00.00.00.C0.00.00
.00
.00
}
EU.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00.00 G Xil.00.00.00.00.00.00.00.00,00.00.00.00.00.00.00.00
.00
.00 iSU.00.00.00.00.00.C0.00.00.00.00.00.00.00.00.00.00
.00
.00 t.00.00.00.00.00.00.00.00.00.00.C0.00.00.00.00.00
.00
.00 2$$.00.t0.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.fi
.00 4R$.00.00.00.00.00.00.00.00.00.00.00.00.00.t0.00.00
.00
.00 ES.00.00.00.00.00.00.00.00.00.00.00.to.00.00.00.00
.00
.00 10T 5.11 4.01 4.11 3.57 5.08 f.!! 5.45 3.18 6.!! i.51 6.45 4.C3 7.1410.C3 9.39 8.19100.:317.03 Vit! Ofrettfen ty Stability X
HE I! Elf I
ESE St SSI
$ S!V SV r$1 I ru Er 111 itut
-STAllllIYttASSIS-1.33.!!.37.21.!!.li.37.41.13.52.ti 1.05.92 2.11 2.20 2.76 17.03 Intretely hstable
.!!.32.t9.23.23 46 41.37.37 41.32.32.37.50.62.50 6.15 hdtrately hstable
.27.23.32 46.55.50.27.23.55.50.27
.11.50.li.!?.55 T.33 Slf;htly h stahlt 2.43 2.29 3.11 2.34 2.11 4.16 2.14 1.51 2.38 2.70 2.01 1.37 3.62 5.04 4.67 3.10 ti.fi teatral
.55.37.23.23.451.101.111.101.742.111.!!.731.511!4
.41 1.01 II.!!
StilhtlyStable
)
.00.00.05.00. 05.37.32.32.37.10.51.23.05.18.!!.00 3.15 hieratelyStable i
.05.C5.00.05.09 14.05.05.14.27. 18.14.09.tl.05.ti 1.41 Extretely Stable.
l i
Virdtirectionty11tdSped I
MI kE ikE E
!! $$i 5 551
!V WSW f HV Et ut 70'At
-tIND SFI!D CUSSIS-
.00.00.00 00.00.00.00.00.00.00.00.00.00.00.00.00
.10 CAIN
.27.55.23.32
.41 45 46.50.ti.50 46
.41.23.li.62.fi f.;1 1.0 - 2.5 ;h 1.13 1.51 2.11 1.!I 2.29 4.12 3.02 1.65 1.19 2.38 2.11 1.24 3.'43 1.10 1.13 2.!I 31.:0 3.3 - 7.5 *;h l
I 2.15 1.!D 1.24 1.33 2.20 3.16 1.51 1.47 1.58 2.24 1.51 1.60 2.51 3.89 4.49 2.18 37.15 1.6 - 12.5 t;h
.92 41.t5.05 11.54 45.371.471.!!.56.73.ti 1.05 2.01 1.!! 13.12 12.6-16.5rph
.to.00.00.00.00.00.00.00.50 41.32.05.00.32.23.tl 2.!!
18.5 - 24.5 ;h l
.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00 3
>24.5r;h i
O 4
tit:til5tilli4TER JanttrFard ill!
I 300 f t.130 SPIED and !!nD CIRitiltN 300-35 ft. fiffRiti!Al ifRPERAiNI U51R CF tl5[RVATRt3 : 2110 VALUl$ ARE flHill OtttEtikti 1
-.. 5f H RITY CU S$15 -
gg3 pngtgg egg 3gg _
spgg5 CLASS A An!
n! III I
$51 I Ikt if 111 TOTAL fu RU
$U R
$5 NS (5 101Al; EU
.H
.00.00
.H
.H
.00.00
.H
.00.C0.00.00.00
.H
.H
.50
.00
.H M.00.00.t0
.H
.H
.H
.00
.H
.H
.00.00
.H
.00.00.00.f0
.00
.00 C$U.00.00.00.00
.H
.H
.00.00.00
.H
.00.ta.00
.H
.00.88
.H
.H AE
.H
.00.00.00.00
.H
.00.00
.H
.00
.H
.00.00
.H
.00
.H
.H
.H l$$.00
.H
.00.00.00.00.00
.H
.H
.H
.00.00.00
.3
.00
.H
.H
.H RR3.ta.00.00.00.00.00.00.t0
.H
.00.00.00.00.00.00.00
.00
.H
[3
.H
.H
.H
.00
.H
.00
.H
.00.00.00.00.00
.H
,H
.H
.O
.60
.0
,00l EU
.H
.H
.H
.t0.00.00
.H
.H
.H
.t0
.H
.to
.H
.c0.tc
.H
.00
.H l
n.00.00
.H
.H
.00
.H
.00
.H
.00
.0
.t0
.H
.00.00
.0
.H
.t0
.H 1 $U.ta.00.t0.00.00
.H
.00.00
.H
.C0.to
.H
.00.00
.H
.H
.H
.H
-i.t!.14.05.09.t5.09.09.11
.H
.t9.C5.01.05.00.14.!D 1.25 1.25 3$5.t5
.H
.05.00.00.00
.H.ti.00.00.ti.00.t5
.H
.15.!!
.46 48 R$
C5
.H
.t5.50.00
.H
.t5.00.t5.00
.00
.H
.00.00.C5.t0
.23
.23
($.00.00
.H
.H
.t0.00.00.00.05.00
.29.00
.H
.t5.00.!D
.tl
.11 2.1?
ED.00.00
.H
.H
.00.00.00
.H
.H
.00
.H
.t0
.H
.00.00.10
.H
.00 KU
.H
.t0
.H
.00.00
.H
.05
.H
.00.00
.H
.00.to.14.00.t5
.23
.23 4$U.00.05.00.00.00.05.tl.t5.t5
.00
.to.19.14.05
.H
.3
.55
.!5
-t
.14
.il.31.32.28.60.!3.23.32.23 19.31.37.13.74.!1 1.22 7.22 7$$.19.00.D0.14
.t5
.H
.00 11
.14
.09
.to
.H
.14.29.05.!! 1.20 1.20 R$.09.00.00.00.00.00.00.t5.00
.H
.05.00
.H
.H
.08
.H
.37
.37
($.t!.00.00
.H
.00
.H
.05
.H
.H
.00.00.01
.3
.H
.H
.3
.11
.11 f.t>
fu.11
.14
.It.00.00.tB.00.t0
.H
.00.t0.00.00.09.t5
.14
.50.50 W.25
.H
.t5.00.C5.00.14.to
.H
.D0.t0
.H
.11.23.tl.fi 1.06 1.06 8$U.t5.00.14
.00.19
.14.00.05.00.05.29.11
.H
.H
.11.23 1.39 1,38
-t
.it.79 1.48 1.14.19 1.44 1.20.il 42.50
.74.321.201.!71,48.if 15.44 16.44 1 IS 45.37.23 45
.H
.11.51.74 46 42.32.11.32.23 E.!! 5.13 5.13 2K!.t5
.H
.C5.05.00.00.tl.00.00
.H
.Cl.23.32 14
.21..!! 1.33 1.31 l$.25.00.00.00.t0
.H
.t3.t0.00.00.!!.11
.14.09.tl 10
.55 21.l 10 45.28.09
.H
.00.00.25.00
.H
.00.ta.00.00.00.00 32 1.20 1.20 1FU.14
.t5.29.09.tl.05.05.00
.H
.50
.H
.t5
.H
.00
.H
.il
.75
.71 3 $U.!!
.14
.C5.C5.05
.14.00.00.00.09.C0.11.00.32.11.!1 1.71 1.11
- t 1.30 1.06.il 1.02 1.16 1.54.Il.il.it 1.31.!!.!$ 1.48 1.05 3.!1 f.it 22.27 22.27 1$5.28.32.23.05.65.!5 1.06.!!.11.!! 1.39.83 1.16.60.28.11 f.H 1.13 8RS.00.00
.H
.00.t0.tl.37.23.23.22.!i.37.19.28
.14
.H 2.73 2.73 IS
.0
.00.00
.H
.00.00.00.00
.H
.H
.14.11
.H
.H
.3
.H
.32
.32 38 3
P tit: HIS0il STAlltt.
Jinary4trca 1912 300 ft. VIH $Fif0 and IIH IIRIt1101 300-35 ft. tiffiRIETIAL Tit?!Uinf
51A111111 CLASSE! -
SFif0
- FIk0 IIREti! H 01Assis - -- - ---
ELAS$ I AXI XI !!!
$5r tr r!r I
rEr rr til iciAt 10 RU 50 t
R$
El TOTAL t
IU.00
.H
.00.00.50
.H
.00.00.00.00.00.00.00.00.00.00
.to
.H 1H.t0.00.00.00
.H
.00.00.00.00.14.11.05
.H
.00.00.05 42 42 1 $U.09.00.00.05.Cl.00.00.00.00.05.05.tl.05.05.00.11
.61
-X
.31.37.51.!i.23.Il.31 11.ti 1.05.14.50.!!.33 1.30 1.18 11.ti 11.06 2$$.05.00.00
.H
.H
.28.ti.19
.46.33.93.37.05.23.C0.tl 3.52 3.!!
4KS.00.00.00.00.00.05.t5.00.05.05.23.09.00.C0.00.00
.51
.!1 IS.00.00.00.C0
.00
.H
.00
.H
.H
.05.00.05.05
.H
.tl
.H
.14
.14 15.34 ;
EU.00.00.00.00
.H
.H
.H
.H
.00.00.00.00.00.00.00.00
.00.00 i
60
.H
.H
.H
.00.00.00
.H
.H
.50
.14
.00
.H
.00.00.C0.00
.14
.!4 I Sil.00
.H
.00.00
.H
.00.00.00.t5.55
.19
.H
.H
.f5
.H
.14
.4!
46 I.28.23.00.00.tl.00.00.t0.31.28.t5.14
.14.!3 1.16.54 4.21 4.21
!St.00.00.00.00
.H
.00.00.tl.37.09.!5.14 H.00
.H
.00
.14
.74 4R$.00
.H
.00
.H
.00.00.00.00.00.50.00.00.00.00
.H
,H
.H
.H ES.to.00
.H
.H
.H
.00.00
.H
.H
.00
.H
.00
.H
.H
.00
.H
.00
.H 5.56' 10T 5.46 4.12 4.01 4.11 3.19 1.57 5.!! 4.49 5.15 6.25 f.22 5.74 6.H 10.0510.19 7.64100.t0 1.11 2.
100.00; rid tire: tin by Ste ility I
H!
!! INE I 151 SE 55E
!!V
!V !!V f
Ekt El tu TDIAL
-!IA!!LIlfCLASSES-
'55 '42
'tl 00 00.00.t5.00.00.00
.H
.00
.H
.09.ti 45 1.H E Utult MIR
'11 '05
'14 09.14.05.23.t0.00.!!.11
.09.11.31
.H
.H 2.H Nerateh MtMe stittly!!tstable
'42 '11
'11 $H.32.32.tl.tl.tl 23.32.I5 19 5g,37.71 4.11 l
t"l2 3'38 3 06 1.14 2.!! 4,55 3.29 1 II 2.56 3.El 2.13 2.18 4.07 7.31 !.43 5.H 12.45 Luuli 1
15
.14 1.11 1.!! 2.13 2.22 2.31 2.13 1.62 1.11 1.4 1.H
.H 21.H WWI M
^
h 1't2 "ll ll
'bl C5
.H
.14.56.21.32 32.53
.H
.50.42
.56
.H 5.23 Mitatil Midt l
[g
',00 7
g 00.00.00.00.tl
.H
.05.05.32.51
.11
.14
.09
.H 1.41 titrenly $tthie find Directin ty titi !;eed I
khi E! BE I !!!
SE !!E 5!V It rit V
nr n ur 70'At
-VII: SrfitttA!$f5-l f
.to
.H
.H
.H
.H
.H
.H
.to.00
.H
.to.00.00
.H
.tB
.H
.00 TALE
.14
.14
.14.tl.t5.tl.14.23,11
.H
.!!.C9.09.I5.37.05 2.13 1.0 - 3.5 sth
.45.33.31 46.32.!! 1.02.51.51.32.23
.74
.74 1.20.!!.60 f.16 3.6 - i.5 rH 1.12 1.30 1.54 2.45 1.06 1.16 1.54 1.48.!! 1.H 1.34 1.11 2.18 2.45 2.75 2.08 27.45 7.6-12.5r;h i
2.45 1.!$ 1.11 1.20 1.34 2.87 2.31 1.11 1.81 2.H 3.Cf 2.27 2.!! 4.26 4.21 2.H 31.fi 12.6-11.5r;h
.51.37.51
.H
.32 1.2!.41.31 1.4! 2.15 2.13 1.25.51 1.20 1.30 1.48 ti.34 11.5 - 24.5 0h
.2
.23
.H
.tt.tl
.H
.00.09.fi.56.28.21
.14
.!! 1.16.11 5.56
>24.5rph
OttoIRISDEXSTATICI Aml-Jue 1!!!
25 ft. fik0 $ PIED ud tito DIRfC11 t 11M5ft.DIfifi!illAl1[RFiKATHE EUKlil0FDilliVAlltts: 2113 VALUES API FIR lli Dtt' Iitti J
-- $1AlIllif CLA$!!$ ------
VINDDIE!C1ItsCLAS$ls
$ PIED CUS$ R kKE hi iki ESI Si $$i 3
$$f $f ::t a
its tr Lkr iciAl EU KU
$U R
X$
E$ TOTAL fU.00.00.00
.H
.H
.50.00.00.00.00
.H
.00
.H 00
.H
.00
.H
.00 H.00.00
.H
.00.00.00.00
.H
.00
.H
.00
.H
.H
.00.00.to
.00
.00 C $U.00.00
.H
.00.50.t0
.H
.H
.H
.00
.H
.H
.H
.00.ta
.H
.00 Ai.50
.H
.00.00.00.00
.H
.00.00.00.00
.0
.00
.0
.H
.H l$$.00.00
.H
.H
.00
.H
.00.00.00
.H
.00.00.00.00
.H
.00
.00 NR$
.H
.H
.00.00.00.00
.H
.00
.H
.00.00
.H
.00.t0.to.to
.H
.00 15.00.00.to
.H
.H
..H
.H
.H
.00.00.t0.ts
.H
.00.00
.H
.0
.00
.H EU.05.00
.0
.00
.H
.00.00.00.t5
.H
.t5.t0.00
.H
,00.00
.14
.14 H.05.C0.00.05.00.05.00.00.00
.H 12.00.!5.00
.0 C5
.41
.41 1H
.H
.05
.H
.H
.H
.t!
.H
.00
.H
.00.05.14
.00.t0
.H
.0 41
.41
-t
.14.46.21.11.32.23.25.t5.14.tl
.H
.5
.H
.09 14 it 2.43 2.43 3$$.50 12.19.73
.41
.41
.14
.32 18 14.11
.14.ti.00.27 1! 5.11 5.11 XS.41. 14
.41
.09 45.32.tl.11
.23.25.14.t!
.14.18.50 41 4.*!
4.t!
ES 45.22.tl.t5.tl.t1.05.ti.09.05.05.00.14 14.50.50 2.75 2.75 15.39 IU.!5.58 1.24.73.it 1.60 1.01 46.23.50.5:
.41 41 18 41.!D 10.44 10.44 H.23.14.50.21.22.18
.14
.H
.18.14.09.t!.00.05.!!.it 2.41 2.47 4 $U.14
.14
.41
.32
.14.18
.00.05
.H
.05
.H
.t5.05.05.61.C5 1.if 1.11
- 8 1.05 1.51 2.24 3.57 2.!!.92.!!.00.11
.H
.tl
.14
.t!
14.31.73 13.51 11.17 1$$.32.!0 1.10 1.24 1.17 1.74.32
.it.50.!!
41.t5.t5
.14
.50.!! 11.31 11.31 0
18.05.00.00.41 1.37.00 18.t5.05.23
.0
.1!.tl.t5.23 3.11 3.11 l$.00
.H
.05.00
.H
.32.00
.H
.00
.H
.00
.H
.H
.H
.t!.t5 4f 46 l
43.!I I fu.73 1.05 1.74
!D.!! 1.01.92 45.18.il.37.id
.tl.32
!. 5 1.!3 11.77 11.17 H.14.18.29 18.21 18.tl.09.01
.H
.t5,tl.tt.23.t!.14 1.17 1.17 8$U.14
.H
.14
.t5.23.11
.05.09.09.05.05
- l
.t5
.0
.!!.!5 1.42 1.4!
-E
.id.!5 1.24 41 1.13 1.10 41.!1.55.21.50.23 I!.37.50.72 10.31 10.35 1$$.09.1!
.H
.00.55.31.21 46 1.42.62.23
.14
.23.tl
.14 32 4.53 4.10 26.00.00
.H
.H
.00
.H
.H
.H
.00
.H
.H
.H
.05.00
.50..tB
.t5 is.t0
.H
.H
.00.00.t0
.H
.H
.00
.H
.00
.H
.00
.H.:
.0
.t!
.H 30.46 4
EU.18 11
.H
.00.05.. H.23.27 45 41.14 45
.14
.t5 45
.s
- 3. ! 3.16 1H.05.t0.to.00
.H
.H
.0
.H
.14
.H
.00.25.to
.H
.H
.0
.50
.!D 3$U
.H
.to.00.00.50
.H
.05.05
.H
.01.14 11
.H
.H
.H
.H
.i!
!D
-E
.H
.H
.to.00.t5.25
.41
.!!.it.21.!D
.t!.00.Il H 3.33 3.30 1 $$.00.00
.H
.00.00
.H
.09.37.18.23.27.Cl.t3.05.00.!: 1.33 1.33 8R$.00.00
.H
.00.00
.H
.00.00.00
.H
.H
.0
.ID.00
.H
($.00
.H
.H
.t0.t0.00.00
.H
.H
.00
.H
.0
.00.tt.t0.t2 0
.00 f.13 '
I j
J
o Cito CRI3til stATItt Asrfi-Jse1tf2 35 ft.111 SFIED and IIH IIRECTIER 150-35 ft. DITTERitTIAL TIKPIRAHRE
$1AIILIlf CLA!!!$ ------
$Fif0 IIH IIRitiitt flASSIS ---
CLASS I thi 11 Iki E !!!
$ $$t
!! V;I t
HV ft RKV 101A1 10 0 $U R
KS ES ICIAL fil
.H
.00
.H
.H
.00.t3.00.00.t5.11.09
.H
.H
.00.00.00
.32.32 1H.00.00.00.00.00.ta.00.00.00.05
.H
.00.00.00.00.00
.ti
.ti
!50
.H
.t3
.H
.H
.00
.H
.05.00.00.tl.00.50.00
.H
.00
.H
.14
.14
-X
.H
.H
.00.00
.H
.H
.H 18.23.18.18
.H
.H
.00.00.00
.78
.78 2$$.00.00.00.00
.H
.H
.00
.H
.00.05.t5
.H
.C0.00
.H
.H
.f9
.01 4KS.00
.H
.H
.00
.H
.H
.00.00.00.00
.H
.00
.H
.tl
.H
.H
.00
.H ES
.50
.H
.H
.00.00
.H
.to
.H
.00
.H
.00
.H
.H
.00
.H
.H
.00
.H 1.31.
Ell
.H
.00
.H
.20.00.00.00.00
.H
.H
.18
.H
.H
.00.00.00
.18.11 EH
.H
.H
.H
.00
.H
.H
.H
.H
.00.00.55.00.00
.H
.00.00
.05
.05 i 5 11.t0.00.00.00
.H
.H
.00.00
.H
.H
.H
.H
.H
.00.00.00
.0!
.H I.00.00.00.00.00
.H
.00.00.to
.H
.t5.00.00.00.00
.H
.55
.ti 2 $$
.H
.H
.H
.H
.00.00.00.00.00.00
.H
.H
.00.00
.H
.H
.00
.00 4FS.00.00
.H
.H
.00
.H
.H
.00
.H
.t0
.H
.H
.H
.00.00.00
.H
.C0 ES.00.00.00
.00.00.t0.00
.H
.00
.H
.00
.H
.00.00.00.00
.H
.00
.n 8.3811.2210.40 4.63 5.18 f.tl 4.15 4.fi 3.34 1.19 2.24 5.!! 7.191H.00 21.02 5.54 4.26 30.8122.11 f.!! 3.21 10 101 5.09 7.24 !0.31 tiridfire:ticaty!!stility i
i ni ni iki ESE SE SSE 51 try I
tkV Lt hit IDIAL
-51AIItny CLA!!I5-1.511.122.!!1.241.02.112.151.19
.H 1.2t 1.33 1.51.f4.55 1.91 2.47 26.02 Extrerely Imstable 48
.H
.60.50.50 41
.H
.H 41.32.31.23
.H
.31.14.37 5.54 Rettretely hstable
.27.n.55.37 46 46
.14
.18.18
.N
.23 48.09.t5.18.09 4.26
$liptly hstable I.fi 2.52 3.76 4.17 5.08 2.29.55 1.17 1.88.!! 1.31.50.14
.l01.191.!530.11 lettral
.!! 1.51 1.18 1.17 2.43 2.52.82 1.83 2.29 2.11 1.15.41
.H
.H 1.01 1.33 22.f1 Sif#tlyStat!e
.H
.37.41
.H
.t1 1.il.11.37.n.Cl.37.14.37
.H
.55
.f4 7.2f eterstely Stable 45,32.14
.05.tl
.41
.25.05
.H
.05.t5.00.14
.14.!5.f4 3.21 Extrerely $ table tied Ifrettica ty tied Intd t kki kE Eki i I!!
!! SSE
$5V If t!t V
HW tt kki 70ill
-t'H SPE[D tiASSES-C0
.H
.00.00.00.20.00.00.00
.H
.00.C0
.H
.H
.H H
H E8II 1'10 1'li 1.47 1.10 1.31 1.19.41
.!D
.0
.32
.H
.H
.H 41 1,42 1.42 15.H U-Md 02 5.!4 5.14 6.il I.32 1.16 1.37 1.24 1.10 1.H.I3.13.14 UO 2.N 43.0 3 I ~ IU "N' 2'47 3[06 3.30 1.15 3.01 2.14 7.6 - 2.5 $
12.i - },u is 1.74 2 1.74 1.91 2.34 1.42 1.19 1.9 46 ut u23.H H.d a
.H.a.a.n i.a us u5 u5 i.H.n.a.a 14 8.H
'n 'n [M
[t3 '
tc.00.00
.H
.25
.13.n
.S
.H
.00
.H
.H
.H
.H 1.H H.S - M M H
.H
.H
.H
.H
.H
.H
.H
.H
.H
.n
.H
.H
.H
.H
.H
o i.
tito CRIS0it stall;#
Arn1-kre '912 300 ft. IIG SFif0 ud IIto Cititil t 30H5 f t. IIFift[111Al IEKFERATURE IJIIR li !!![EVA110X$ : 2183 Vi! LIES 4tfFERCIETDttLTEit:E
- STOILITY CLA3515 -----
SPilD
- t!LO DIRit1 ICE CLA!!Es CLASS E eke il IKE I
ILV IV LIV TOTAL IU FU SU i
SS KS ES TOTil EU.00.00.00.00.00.00.00.00.to.tl.!D.00.00.00.50.to
.00.00 XU.00.00.00.00.00.00.00.00.00.00.00.00 00.to.00.00
.00
.00 C SU.00.00.00.C0.00.00.00.00.00.00.00.00.00.00.00.t0
.00
.00 iI.00.00.00.00.00.00.00.00.00.00.00.00.00.00.t!.tt
.00
.00 iSS.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00
.00
.Dil N R$.00.00.00.00.00.00.00.00.00.00.to.00.00.00.00.00
.00
.00
[3.00.00.00
.0
.00.00.00.00.c0.00.00.00.00.00.00.t0
.00
.00
.00 fu.00.00.00.00.00.00.to.00.00.00.00.00.00.t3.00.00
.00.00 NU.00.t0.00.to.00.00.00.00.00.00.!O
.00.00.00.!0.00
.00
.00 1 SU.00.00.to.05.00.00.00.00.00.00.t0.00.00.00.50.t0
.05
.05
-I
.05.00.00.05.09 23.tl.01.tl.18.!5 09.tl.05.00.08 1.24 1.24 3 55.00.05.05.00
.14
.05.14
.t9.tl.t9.t0.00.C0.to.00.to
.14
.f4 RS.05.05.00.00.05.00.00.00.00.tl.IQ.05.00.00.00.to
.27 E3
.00.00.05.00.c0.00.t5.00.00.00.;0.00.00.00.00.t:
.01
.tl 2.22 EU.09.tl 18.00.00.00.00.05.00.00.00.00.00.00.00.C:
41.41 RU
.14.01 46 14.14
.18.32.05.00.05.!D
.18. 05.05.00.00 1.!)
1.!3 4 $U
.14
.05.32.32
.41.50 46.23.18.14.Cl.tl 14.00 to.05 3.11 3.11
-I
. 14.!?.50.!D.il.t1.32.18
.14.18.31.23.00.t5.Il.Il 4.72 4.12 i$$.05.09.23.21 45.18.32.41.14.18
.Il
.05.05.50.!O.0; 2.52 2.52 ES.tl
.14
.14
.14.09.09.09.41.09.09.C5.09.00.01.to.t5 1.15 1.15 f3.05.00.t0.05.05.09.00.09.18.00.to.05.00 00.01.00
.H
.f4 14.lf EU.05.21.73.23.09.00.05.00.00.00.t0.09.t5.t0.t0
.14 1.!! 1.il RU.18.14.it 46.14.21 18
.14.05.05.t5.32.09 14.14.tl 3.21 3.21 8 $U.23.00.32
.18.23.55.50.23.tl.14
.23.25.05.t0.14.11 3.11 3.11
-I
.ti 1.41 1.42 3.12 1.!5.!!.23.32.18.27.23.tl.23.27.32.li 't.73 12.13 135.27.ID.12 1.51.f4.54.37.23.05 45 46.32.t5.t0.t!
.14 f.!!
5.19 2KS.01.14.37.18.27.37.32.41.01.09 14.09.09.ti
.!:..ti 2.70 2.70 15.18.00.14
.00.00.09.23.23.00.to.:0.Cl.ti.t5.t:
.14 1.11 f.!!
31.P IU 46.13 1.t1.00.tl.ti.t5.00.00 -. 00.. I D.00.00.I5.27.!! 3.57 3.!!
1 FU.19.05 45
.14.14.18.32.32.00.00.:i
.13.00.:9
.f4.37 2.C 2.l3 3 $U.01.27.09.18.03.27.27.tl.25.tl
.:5.32.00.00.tl.23 2.20 2.20
-I
.li 1.24 1.47 1.33 2.34 1.51 45.El.78.31.78
.it.23.21.12.!7 14.f 4 14.f4 1 $$.50.23.37.00 1.42 1.11.50.41
.41.7)
.35.32.t!.14.21.!! l.47 8.4I IR$
.14
.!!.05.00 tl.50.13 41.25.09
.05.05.t5 la.1! 3.11 3.1I IS.to.ti.25.00.05.00.ti.Cl.00.t0.!!.00.00.tc.;
.t"
.37
.37 35.0
y o CEts02f! DER $1Alltt Astil.Ine1992 3t0 ft tIto SFIED and IIED DIRIC110t 200-35 ft. !!FfilitTIll TitFIRAIRf
STAi!Llif CLAS5t$
$7ffD VIEDCIFICTI01CLASSIS-CLAS$ t ni ti ill I
11 rit r
ut it trr TOTAL fu Rif SU t
KS ES TCIA!
IU.tl
.23.50.00.to.00.00.00.to.00.C0.00.t0.00
.14
.18
.54.64 1 fu.14
.tl.25.00.00.00.00.00.05.23.05.14.to.00.14.t0
.12 9 SU.05
.14.00.00.00.00.05.ta
.14.2T.t5.tl.09.00.05.00
.12
-t
.23.il.ti.05.t5.31.31.!!.to.it 41.58.14.21.18.Il 5.11 5.11 2$$.11.09.tl.00.00.14.31 18 1.33 1.15.41
.09.09.14. 05.18 4.41 4.49 4RS.09.05.00.00.00.09.tl.00.to.tl.t5.00.05.01.05.00
.54
.f4 il.00.00.00.00.00.to.00.02.00.00.00.00.t3.ti.00.00
.t5
.tl 13.C EU.00.00.00.00.00.00.03.00.00.00.00.tt.00.00.00.to
.t:.00 5K0.00.00.00.00.00.00.00.00.00.00.t5.to.53.00.00.t0
.t5 i !U.00.00.00.00.00.00.00.00.to.00.11.tl.00.00.00.C0
.11
.18 I.t5.05.00.00.00.00.00
.41
.37.37.31.05.00.00.23
.0 1.!!
1.18 2 $3.00.00.to.00.t0.00.00.18.01.14.11
.14
.05.05.00
.00
.82 4R$.00.00.00.00.00.00.00.00.00.t0.00.00.05.00.00.00
.05
.05 IS.00.t0.00.00.00.00.tB.00 00.00.t2.00.00.00.to.00
.t!
.00 2.t 101 5.73 7.13 ;0.11 1.48 9.31 1.30 1.01 6.11 5.18 6.14 5.51 4.40 1.74 1.92 3.34 5.36100.!0 6.32 1.34 f.57 4!.!! 23.14 8.47 2.34 C.)
Vir.d Directi:t ty Statility I
hk!
E! E!!
E!!
!! $5E I
!!! It rir V ftr Er Hr it!At
-ITAIIIITY CIA!$ES-
.19 1.33 1.92.23.18.tl.09.05.00.00.t3.!!.t5.05 41 1.11 1.32 Extremely Unstatle
.!5.32 1.74.73 41.14.!2.50.09.32.11.22.14.21
.41
.37 1.34 bderately Utstable SlfttifUtstatie
.50 46.73.73.73 1.33 1.28.55 41.64.50.55.27.00.27
.46 f.!T i
2.!! 3.11 3.54 5.f 3 4.81 3.!5 1.47 2.52 2.15 1.11 2.20 1.!C.69.52 1.74 1.53 41.32 neutral
$11t tly stable h
1.01 1.t5 1.65 1.79 2.60 !.20 1.19 1.51 2.06 2.75 2.11.12.32.32.31 1.15 23.14 45.92.10.32.50 1.05 1.24 1.24.23 46 41.27.23.27.C5.23 1.47 hderately Stable
.23.t!.23.25.El.11.32.41.18.00.Il.14.05.tl.09
.14 2.14 fitremely stable firid Directin tf tind !;eed t
ni kl !KE i
I$i 51 !!!
$!r it
- t r ny kr A(r itiAl
-tIND SFfED CLASS!!-
.00.to.00.00.00.00.00.t0.00.00.00.00.00.t3.00.ID CA1I
.Il.Il.09.El.21.21.21 11
.14.31.I!
.14
.Il.t5.00.Il 2.21 1.0 - 3.5 r;h
.19.73 1.!3 1.51 1.!31.521.511.42.73.it.it.il.23 18.18.11 14.!!
3.8 - T.5 r;h 1.ti 2.11 4.!1 6.1! 3.t2 2.19 1.!! 1.!6 46 1.31 1.10 1.05.!O.50
.14 1.37 31.33 1.5 - 12.5 p h 2.24 3.11 3.!3 1.15 4.21 3.71 2.47 2.t2 1.28 1.28 2.11 1.51.37.60 1.t! 3.25 3!.ti 12.5 - 18.5 nh
.!! 1.24.11.05.C5.50.!? 1.01 2.11 2.34.li.22.31.55.50 45 13.41 1!.6 - 24.5 r;h
.t5.25.t0.00.00.00.00
.(0 46.50.il 18.29.05.23
.00 2.51
> 24.5 p h i
-