ML20237H759
| ML20237H759 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/30/1987 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| SL-3061, NUDOCS 8709030378 | |
| Download: ML20237H759 (156) | |
Text
- _ _ _ _ _ -.
l l
tj i
?
GEORGIA POWER COWANY V0GTLE ELECTRIC GENERATING PLANT i
UNIT 1 l
SEMIANNUAL REPORT PLANT RADI0 ACTIVE EFFLUENT RELEASES MARCH 9, 1987 THROUGH JUNE 30, 1987
.O d
B709030378 070630
/(
PDR ADOCK 05000424 i.
p PDR
\\p, i
m____.__
EEEIkE EkEGIE1E REEEEAILEE Ek&EI EEEl&EEE&k EEEERI
. ($1~
EL&EI E&RIE&EIlYE EEELUggI gghgasgg j
'EEEIIEE IIILE E&EE 1.o.
k12EIR EEEkEEEIS 5
4
- 1. '1 REGULATORY LIMITS / TECHNICAL SPECIFICATIONS 5
-1.1.1 Effluent Radiation Monitoring Systen 5
1 1.1.2 Concentration Limits 5
l
)
1.1.3 Dose Limits 5
1.1.4 Liquid Processing 5-1.1.5 Outside Temporary Tanks 6
1.1.6 Reporting of Sealannual Releases (Unplanned) 6 1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS 9
1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL 9
RADIOACTIVITY I
O' As 1.4 LIQUID EFFLUENT RELEASE DATA 11 1.4.1 Methodology 11 1.4.2 Batch Release Data 14 1
1.5 RADIOLOGICAL IMPACT ON MAN DUE TO LIQUID 14 RELEASES 1.6 ABNORMAL RELEASES 14 I
)
2.0 gfgggg! glghygyIg 25 2.1 REGULATORY LIMITS / TECHNICAL SPECIFICATIONS 25 2.1.1 Process Effluent Monitoring Systen 25 2.1.2 Dose Rate Limit 25 2.1.3 Air Dose Due to Noble Gas 25 2.1.4 Dose to Any Organ 26 i
2.1.5 Ventilation Exhaust Treatment Systen 26 and Gaseous Waste Processing System O*
I 1
SECTION IIILE HAG {
(( )
2.1.6.
Explosive Oas Mixture 26 2.1.7 Activity In Gas Decay Tanks 26 2.1.8 Total Fuel Cycle Dose Commitment 27 2.1.9 Reporting of~Sealannual Releases (Unplanned) 27 2.2 RELEASE POINTS 32 2.3 SAMPLE COLLECTION AND ANALYSIS 32 2.4 DETERMINATION OF TOTAL QUANTITIES OF 33 RADI0 ACTIVITY, DOSE RATES AND CUMULATIVE DOSES 2.4.1 Fission and Activation Oae 33 2.4.2 Radiolodine. Tritium and Particulate 34 Released 2.4.3 Gross Alpha Release 34 2.5 GASEOUS EFFLUENT RELEASE DATA 35
(])
2.5.1 Methodology 35 2.5.2 Gaseous Batch Data 37 2.6 RADIOLOGICAL IMPACT DUE TO GASEOUS 37 RELEASES 3.0 SQk1Q [Aglg 47 3.1 REGULATORY LIMITS / TECHNICAL SPECIFICATIONS 47 3.1.1' Use of Solid Radioactive Waste System 47 3.1.2 Reporting Requirements 47 3.1.3 Changes to.....h e PCP 47 t
as s.
v.
3.2 SOLID WASTE DATA 48 l
4.0 EHfHgg! TQ Igg ygGTgg (({pTHIC 51 9EEEEAIIE9 ELAEI 99EE l
4.1 Changes in the Radiological Environmental 52 4
Monitoring Program
'i 5.0
(\\J ggS(( TO MEMBERS Og THE PggLig Ig}ID{
54 IEE E11E 299E9 HEX l
i j
sgq11gg IIILE gaQg 1
O ao uizan nasut< I tut tia in-
^25 "2.
&EE 19k1D BARE &EIE IEEAIEEEI EZEIEME 7.0 MEIEQBQLQQZ LIQ RE 1HQLQQEQ EQE IEE 58 i
EEERRI R&IER d&EEAEZ lt IEEE1 8O lE9EEE& eke L12 ele 9E G6EEEEE REEkEEHI 59 HRELIEELEQ IEEIREMEEI&Il2E 90 I48EE EEEEEQlEE EEELE EGEIEEI klELIE 82 AIIASHMEEIE ATTACHMENT A ODCM Changes 63 ATTACHMENT B ODCM Puture Changes 88 ATTACHMENT C Meteorological Data 99 O
l 4
l
- O 3
I l
YEEILE ELEEIELE EEEEE&IIEE Ek&EI
($l EEEl&EEE&k EEEERI i
1 i
RAELEsEI1EE EEELEEEI EELEAEE BEEEEI 1
I&akE LIEI EE IAELEE EAEE 1-1 Technical Specification Table 3.3-9 7
Radioactive Liquid Effluent Monitoring Instrumentation 1-2a Liquid Effluents - Summation of All 17 Releases - Unit 1 1-Sa Liquid Effluents - Unit 1 18 1
1-4a Individual Doses Due to Liquid 20 Releases - Unit 1 1-5 Lower Limits of Detection -
21 Liquid Sample Analysis 2-1 Technical Specification Table 3.3.10 28 Radioactive Oaseous Effluent Monitoring Ins'trumentation j
1
(~S 2-2a caseous Effluents - Summetion of All 38 l
$d Releases - Unit 1 I
2-3a Gaseous Effluents - Mixed Mode 39 Releases - Unit 1 l
2-4a Gaseous Effluents - Ground-Level 41 Release - Unit 1 l
l 2-5 Gaseous Effluents Dose Rates Site 43 j
i 2-6a Air Doces Due to Noble Oases Unit 1 44 2-7a Individual Doses Due to Radiolodine, 45 Tritium, and Particulate in Gaseous l
Release - Unit 1
)
l 2-8 Lower Limits of Detection - Gaseous 46 Sample Analyses I
3-la Solid Waste and Irradiated Puel 49 Shipments 5-1 Basic Data Assumed in Dose Assessments to 55 Members of the Public j
4
l
\\
1.0
'kkQELQ KilkyggTS
(
().
1.1 REGULATORY LIMITS / TECHNICAL SPECIFICATIONS l
l The
' Technical Specifications (T.S.)
presented in this subsection.are for Unit 1 and which states in part:
l.
1.1.1 Effluent Radiation Monitoring System (T.S. 3.3.3.9)
-The radioactive 11guld effluent monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with their
]
Alarm / Trip Setpoints set to. ensure that the limits of Specification 3.11.1.1 are not exceeded.
The Alarm / Trip Setpoints of these channels shall be determined and adjus-ted in accordance with the methodology and parameters in the l
OFF-SITE DOSE CALCULATION MANUAL (ODCN).
(Technical Specif-l 1 cation Table 3.3-9 is included in this subsection as Table l
1-1).
1 1.1.2 Concentration Limits j
j T.S.
3.11.1.1
{
The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.1-
)
l 1) shall be limited to the concentration specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble
()
gases.
For dissolved or entrained noble
- gases, the concentration shall be limited to 2.0E-4 microcurie /a1 total activity.
1.1.5 Dose Limits T.S.
3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in 11guld effluents
- released, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-1), shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 areas to the whole body and to less than or equal to 5 areas to any organ and, b.
During any calendar year, to less than or equal to 3
mreas to the whole body and to less than or
/
equal to 10 mreas to any organ.
1.1.4 Liquid Processing T.S.
3.11.1.3
. (
The Liquid Redwaste Treatment System shall be operable and appropriate portions of the system shall be used to 5
reduce releases of radioactivity when the projected i
doses due to the liquid effluent, from each unit, to
(])'
UNRESTRICTED AREAS (see Figure 5.1-1) would exceed 0.06 mrem to the whole body or 0.2 area to any organ in a
31-day period.
1.1.5 Outside Temporary Tanks T.S.
3.11.1.4 The quantity of radioactive material contained in each
- outside temporary tank shall be limited to less than or equal to 10 Curles, excluding tritium and dissolved or entrained noble gases.
1.1.6 Reporting of Semlannual Releases (Unplanned)
T.S.
6.8.1.4 states in part:
t The Sealannual Radioactive Effluent Release Reporte shall include a
list and description of unplanned J
releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
}
4 4
I 1
1 1
6
}
f i
(
TABLE 1-1
(
(FROM TECHNICAL SPECIFICATIONS)
EAR 12&EILEE klQEIR EEELEEEI HRE112ELEE LEEIEEEEEI&IIRE MINIMUM CHANNELS LEEIEEEEEI REEE& eke AGI12E 1.
Radioactivity Monitors Providing Alarm and Automatic Termination of Release a.
Liquid Radwaste Effluent Line 1
37 (RE-0018) l b.
Steam Oenerator Blowdown 1
38 I
l Effluent.Line (RE-0021) c.
Turbine Eldg (Floor Drains) Sumps 1
38 Effluent Line (RE-0848)
()
d.
Control Bldg (Floor Drains) Sumps 1
39 Effluent Line (RE-17646) 2.
Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a.
Nuclear Service Cooling Water i
39 Effluent Line (RE-0020A & B) 3.
Flow Rate Measurement Devices a.
Liquid Radweste Effluent Line 1
40 (PT-0018)
L b.
Steam Oenerator Blowdown 1
40 Effluent Line (PT-0021) c.
Flow to Blowdown Sump 1
40 (AFQI-7620 FR-7620 pen 1)
O 7
TABLE 1-1 (CONTINUED)
([)
ACIIOg gIAIggggIs ACTION 37 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:
a.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and b.
At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 38 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for radioactivity at a
lower limit of detection of no more than IE-07 miroCurle/ml:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than
{}
0.01 microCurle/ gram DOSE EQUIVALENT I-131, or b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurle/ gram DOSE EQUIVALENT I-131.
ACTION 39 with the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided
- that, il at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for radioactivity at a lower limit of i
detection of no more than 1E-07 microcurle/al.
ACTION 40 With the number of channels OPERABLE less than required by the Minimum Channel OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump performance curves generated in place may be used to estimate flow.
j 8
6
- l 3
1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS
' ( f:
The MPC values.used in determining allowable liquid radwaste release rates and. concentrations for principal gamma j
from-10 CFR Part 20, Appendix B, Table II, Column 2.
I
- l For dissolved or entrained noble gases in 11guld
- radwaste, j
the. MPC is obtained from Technical Specification 3.11.1.1 l
as 2.0E-04 uC1/ml.
For gross alpha in.11guld radwaste, the NPC is obtained from 10 CFR Part 20, Appendix B.
Note 2.d as 3.0E-08 uC1/ml,
- Further, for all the above radionuclides or categories of j
radioactivity, the overall-MPC fraction is determined in accordance with 10 CFR Part 20, Appendix B, Note 1.
1 The method whereby the MPC fraction is used to determine release rates and liquid radwaste effluent radiation monitor j
setpoints is described in Subsection 1.4 of this report.
]
1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADI0 ACTIVITY Prior to.
release of the contents of any tank containing J
liquid radwaste, and forlowing the required recirculations, samples are collected and analyzed in.accordance with O'
Technical Specification Table 4.11.
A sample from each tank planned for release is analyzed for principal gamma
- emitters, I-131, and dissolved and entrained noble gases by gamma. spectrometry.
Monthly and quarterly composites are 1
prepared for analysis by extracting aliquote from each
)
']
sample taken from tanks which are released.
Liquid radwaste temple analyees are performed as follows:
l l
l I
4 S
l O
9
l a
l I
L Etatuttatni Ettantasr Etihad
'{'}
)
1.
Gamma Isotopic Each Batch Gamma Spectroscopy
{
-with computerized data reduction
\\
2.
Dissolved or One Batch Gamma Spectroscopy 1
entrained noble per month with computerized j
gases data reduction 3.
Tritium Monthly Distillation and Composite liquid scintillation' counting L
4.
Gross Alpha Monthly Gas flow proportional Composite counting i
1 5.
Sr-89 and Sr-90 Quarterly Chemical separation l
Composite and gas flow propor-i tional or scintil-j lation counting l
6.
Fe-55 Quarterly Chemical separation Compocite and liquid scintil-l lation counting l
l
/~y Gamma isotopic measurements are performed in-house in
\\_/
the radiochemistry lab using germanium spectrometry.
This consists of four high purity germanium detectors with resolution between 1.75-1.80 kev.
The detectors are shielded by four inches of lead.
A one-liter 11guld radweste sample is poured into a
graduated cylinder to measure out one liter of sample which is then poured into a one liter bottle or into a 1 liter marinelli in preparation for a 2000-9000 second count.
A peak search of the resulting gamma ray spectrum is performed by the computer system.
Energy and net count data of all significant peaks are determined, and quantitative reduction or LLD calculations are performed for the nuclides specified in Table Notation f
3 of Technical Specification Table 4.11-1 Mn-54, Fe-59,
[
Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and l
Ce-144.
The quantitative calculations, corrections for counting
- time, decay
- time, sample
- volume, sample
{
- geometry, detector efficiency, baseline
- counts, branching ratio, and LLD calculations, are made based j
on the counts at the location on the spectrum where the peak for that radionuclides would be located. If present.
- Tritium, Gross Alpha.
Sr-89, Sr-90 and Fe-55 are, in l
some cases, performed off-site rather than in-house to more efficiently use the technicians time on other
()
- matters, i
l 10 i
s 4
't il The~ radionuclides concentrations determined by gamma' i
.(]J~
spectroscopic analysis of a sample taken from a
tank.
planned-for release and the most sytrent aggple analysis-results available for tritium, gross' alpha, Sr-89.
Sr-90 and Fe-55 are used along -with. the corresponding MPC values to determine a MPC fraction for the tank planned for release.
This MPC fraction 1 1s then used, with appropriate safety. factors, along with the expected dilution stream flow to~ calculate maximum permissible release rate and a liquid effluent monitor setpoint.
The monitor setpoint is calculated to assure that the limits of Technical Specification 3.11.1.1 are not exceeded.
A monitor reading in excess of the calculated setpoint therefore results in an automatic termination-of the liquid-radwaste discharge.
Liquid effluent discharge is also automatically terminated if the di'lution' stream flow rate falls below the' dilution flow rate used in the'setpoint calculations.and established as a setpoint j
on the dilution stream flow monitor.
a i
Radionuclides concentrations, safety factors, 'dllution stream flow rate, and liquid effluent radiation monitor calibrations are entered into the. computer and a
y prerelease printout is generated.
If the release is
'["}
not permissible, appropriate warnings will be included ss
'on'the computer screen.
If the release is permissible, 1
it is approved by the Chemistry Foreman on duty and
]
sent to the Operations Department for approval and a
processing.
When-the release is completed, the
.necessary data from the release (ex.,
release volume) q is. transferred from the Operations Deprrtment to the j
Chemistry Department.
These data are input to the computer and a post-release printout is generated.
The post-relese printout contains actual release
- rates, I
act'ual r:e l ea se5 concentrations and quantitles, actual dilution flow, and calculated doses to an individual.
1. 4 **
Liquid Effluent Re ease Data Regulatory Guide 1.21 Tables 2A and 2B are found in
'h this report as Table 1-2a and Table 1-3a for Unit 1.
l It should be noted that the First Quarter only covers the period from March 9,
1987 to March 31,
- 1987, because 'this report begins with the date of initial criticality per section 6.8.1.4 of the Technical l
' Specification.
l c
1.4.1 Methodology l
The values for the four categories of Table 1-2a are
()
calculated and are completed as follows:
11
I
~
1 i
1.
Fission and activation products o
f}
The total release-values (not-including
- tritium, i
v-
- gases, and' alpha) are comprised of the sum of.the measured' individual radionuclides activities.
This
)
sum la for eac'- Latch released to the river for the respectiva quarter.
Percent of applicable.
limits is determined from a mixed nuclide MPC fraction calculation.
The average concentration
-for each nuclide over all released-batches is divided by the corresponding individual'MPC value.
The. sum of overall nuclides of the C1/MPCI ratio times 100 is the percent of applicable limit. for
- . s
' effluent releases during the. quarter.
1 2.
Tritium The measured tritium concentrations in the monthly composite samples are used to calculate the total release-and average diluted concentration during each period.
Average 'dlluted concentration divided by the MPC
- limit, 3.0E-03 uC1/m1, is converted to percent to give the percent of applicable 11 ult.
3.
Dissolved and entrained gase*
.O.
Concentrations of dissolved and entrained gases in liquid.
effluents are measured by germanium spectroscopy on each one liter sample for each l
11guld radwaste batch.
The average concentration
-i
'of dissolved or entrained ~ noble gases for all released batches is divided by the! MPC value stated in Technical Specification 3.11.1.1 (2.0E-04 uC1/al) to determine the NPC fraction.
The 4
result x100 is the percent of applicable limit for noble gases in 11guld effluent releases during the quarter.
. Radioisotopes of lodine in any form are
- [
"[ ils'o ' determined during the isotopic analysis
~
for
[,
e{ch [batjj[:' 'therefore, a separate analysis for possible gaseous forms is not performed because it would not provide additional information.
4.
Gross alpha radioactivity
,n%,,.
The measured gross alpha concentrations in the monthly composite samples are used to calculate the total release of alpha radioactivity.
l 5.
Total Error Measurement The total or maximum error associated with the efflueet measurement will include the cumulative
()
errors 'resulting from the total operation of sampling and measurement.
Because it may be very 12
difficult to assign error terms for.each parameter affecting the final measurement, detailed
()
statistical evhluation of error is not suggested.
The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released ~1n liquid effluents.
Estimated errors are based on errors in counting i
' equipment calibration, counting statistics.
dilution flow rates, sample and tank flow. rates.
1.
Fission and activation total release was calculated fron' sample analysis results and release point flow rates Sampling and statistical error 10%
)
1 Counting Eculpment Calibratio..
10%
Tank Discharge Flow Rate Volumes 20%
Total Error 40%
2.
Total tritium release was calculated from sample analysis results and release point volumes.
{}
Tank or system flow rate, volumes 20%
Sampling and statistical errors 10%
Counting equipment calibration 10%
Total Error 40%
3.
Dissolved and entrained gases were calculated from sample analysis results and release point volumes.
Tank or system flow rate, volume 20%
Samplirg and statistical error 20%
Counting Equipment Calibration 1Q%
Total Error 50%
4.
Gross alpha radioactivity was calculated from sample analysis results and release point volumes, f
Tank or system volumes, flowrate 20%
Sampling and statistical error 10%
l Counting Equipment calibration lot 13 b
i Compositing sample error 5%
()
Total error 45%
5.
Volume of waste prior to dilution was calculated from level indicators on the tanks and pump discharge flow rates and times.
Level indicator error 10%
Operator interpretation of gauge 5%
l Total error 15%
1 6.
Volume of dilution water used was calculated from l
flow rate indicators and pump discharge flow rates l
and times, i
Flow rate indicator error 10%
Operator interpretation of gauge 5%
Total error 15%
1.4.2 Batch Release Data Other data pertinent to continuous and batch releases of
()
radioactive liquid effluent from Unit 1 are listed in Table 1-6, 1.5 Radiological Impact on Man Due to Liquid Releases i
Doses to an individual, due to radioactivity in liquid
- effluent, were calculated in accordance with Technical i
Specification 3/4.11.1.2 using the methodology presented in the Plant Vogtle Offsite Dose Calculation Manual.
Results are presented in Table 1-4a for Unit 1.
l 1.6 Abnormal Releases l
1.6.1 Itemization of the Location / Source of the Unplanned Releases 1.6.1.1 Waste Gas Decay Tank #2 (5/16/87) j 1.6.1.2 South Waste Water Retention Basin (5/22/87) 1.6.2 Description of Unplanned Releases f
2.6.2.1 Waste Gas Decay Tank (WGDT) #2 During a waste gas release of WGDT 84.
valve #1-1902-04-073 l
was found open.
This valve was left open due to peraonnel f
O error in swapping in-service waste 'tas decay tanks thereby causing the inadvertent partial reicase of WGDT
- 2.
The quantity and activity of gas released are docusented in 14 1
9
Gaseous Release Permit
- 870035-G.
(Reference Deficiency Card # 1-87-1318, Significant Occurrence Report #100).
O 1.6.2.2 South Waste Water Retention Basin (SWWRB)
Backleakage of the contents of the crud tank contaminated the demineralized water system in the auxiliary building.
The demineralized water feeds into a number of clean systems which exit the auxiliary building to the turbine building clean hold-up tank via a " clean sump".
This " clean sump" became contaminated and discharged, via the turbine i
- building, from the SWWRB to the river.
The release was quantified on the basis of a sample which was collected by the WWRB discharge compositer which was in-service during the release.
The quantity and activity of water released are documented in Liquid Release Permit
- 870340-L, (Reference Deficiency Card
- 1-87-1396, Significant Occurrence Report #112).
O t M '
O 15
10:06 AM Wednesday Auoust 12, 1987 I
EM-3A-RP Page REPORT j Georgia Power Company Vogtle Electric Generating Plant ABNORMAL DELEASE
SUMMARY
l Stat'ttna :
9-Mar-1987 Endine :
30-Jun-1987
'l i
t LIQUID REl.GSES l
hhhhhPOFREh,bkhEh 1
T1TAL TIME FOR ALL RELEASES 235.98 MINUTES MAXIM'M TIME FOR A RELEASE i
235.98-MINUTES AVERAGE TIME FOR A RELEASE 235.98 MINUTES l
MINIMUM TIME FOR A RELEASE 235.98 MINUTES l
TOTAL ACTIVITY FOR ALL RELEASES 8.508e-05 CURIES GASEOUS RELEASES O ABER OF RELEASES 1
COTAL TIME FOR ALL RELEASES 187.98 MINUTES MAXIMUM TIME FOR A PELEASE 187.98 MINUTES AVERAGE TIME FOR A RELEASE 187.98 MINUTES MINIMUM TIME FOR A RELEASE 187.98 MINUTES TOTAL ACTIVITY FOR ALL RELEASES :
1.822e-02 CURIES
~MOId5ft[ 7f0ff liIlliRT ~ ~5Mf61W ~ ~ ~ "#TIWORRifSi ~ ~ ~fDF 'F ~ ~ ~ DOT INCES TIME IN DEGREES 10M 45N 60M 10M 45N 60N O
1400 6.5 7.7 6.2 166 166 166 63 57
-2 0
1500 7.4 6.7 9.0 189 192 176 82.4 59.6
- 1. 5 0
100 7.3 7.2 8.9 174 183 196 84.0 56.3
-1.8 0
1700 6.1 6.1 7.6 177 185 178 84.'O 54.3
-1.9 j
0 1800-6.1 7.2 7.9 169 177 181 85.0 54.7
-1.6 l
1' l
%^
O
- o
TABLE 1-2a V0CTLE ELECTRIC GENERATING PLANT SEMIANNUAL ETTLUENT RELEASE REPORT LIQUID ETTLUENTS - SUMMATION OT alt. RELEASES March 9 THROUGH _ June 30,19 87 UNIT 1 Unit Quarter 1 Quarter l Est. Total i
Error Z A.
Tission & Activation Products 1.
Total Release (not Ci 40 including H-3, mases. aloha) 2.66E-3 2.338E-1 2.
Average diluted uC1/mi concentration durine naried 2.337E-9 1.76M-R 3.
% of application limit 4.82E-3 5.09E+0 8.
Tritius O,
1.
Total release C1 2.14E-1 4.992E+1 40 2.
Average diluted uC1/mi concentration 1.881E-7 3.764E-6 3.
I of applicable limit E.27E-3 1.254E-1 C.
Dissolved and Entrained Cases 1.
Total relamee C1 1.199E-4 3.78E-3 50 2.
Average Diluted concentration 1.051-10 2.850E-10 durina seriod uci/mi 3... 1 of applicable limit
}
5.268E-05 1.425E-4
. ~,.
D.
Gross Alpha er Radioactivity
- 1.
- Total release ci
< 1.127E-4
< 4.281E-4 45 E.
Volume of Waste 3.506E+5 1.523E+7 15 (prior to dilution)
Liters F.
Volume of dilution water used during period.
Liters 3.002E+8 3.487E+9 15 O
17
TABLE 1-3a (Pr.ge1of2)
O voorte itzcr=Ic crxi=ATINc Ft4NT r
l SEMIANNUAL LIQUID EFFLUENTS RELEASE REPORT March 9 THROUGH June 30, 19 87 ITNIT 1 Continuous Mode Batch Mode l
1 Nuclides Unit Qua rte r1 Quarter 1 Quarte r_1, Quarterl Released H-3 Ci
- OE0
- OE0 2.14E-01 4.99E+1
_Cr-51 Ci
- OE0 4.11E-4 1.40E-5 2.72E-2 16 54 C1
- OE0 2.3E-06
- OE0 1.37E-03 Fe-55 Ci
- OE0 9.49E-2 2.36E-3 9.02E-3
.Fe-59 Ci
- OE0
- OE0
- OED 4.10E-3 Co-58 Ci
- OE0 2.9 X-3 1.00E-4 6.17E-2 Co-60 C1
- OED
+ orn
- OE0 1.10E-3 2n-65 Ci
- OE0
- MO
- DEO 2.95E-05 Sr-89 Ci
- mo 1.7af-03
< s Aw nc
< 2.01E-06
$r-90 Ci
- OED
- OED
< 7.89E-06
< 2.01E-05 Zr-95 C1
- GEO
- DED Ln9r-Os 9 9w n1 Nb-95 C1
- DEO
- DED a 3RE-07 1.30E-03
. Mo-99 Ci
- OE0
- OE0
- OE0 6.42E-04 Tc-99s Ci
- OE0
- OE0 5.69E-06 7.68E-04 O-
- I-135 Ci
- E0
- MO
- nrn 4.8 E-05 I-131 Ci
- OE0
- OE0
- OE0 5.15E-04 h-56 Ci
- OE0
- OE0
- OE0 4.20E-05 Be-140 Ci
- E0
- OE0
- OE0 2.05E-5 La-140 Ci
- OE0
- OE0
- OE0 9.17E-04 Au-198 Ci
- OE0
- KO
- DEO 1AW7 Be-7 ci
- OE0
- DEO
- DEO 1.1 w ?
Co-37 Ci
- E0
- Orn
- nrn
- 4. 4 E-6 Cs-1B ci
- E0
- MD 1_a11-5 G.ALMet Ci e nrn
- E0
< 1.1X-4
< 4. M-4 I-132 ci
- OE0
- DED
- OE0 2.4E-6 1-133 C1
- GE0
- GEO 5.ast-06 8.59E-04 Zeros in this table ladicate that no radioactivity was present above detectable levela. See Table 1-5 for typical lower limits of detection for liquid sample analyses.
O.
n
s-TABLE 1-3a (Page 2 of 2)
V0GTLE ELECTRIC CENERATING PLAlff SEMIANNUAL LIQUID EFFLUENTS RELEASE REPORT March 9 THROUGH June 30, 19 87 UNIT 1 Continuous Mode Batch Mode l
Nuclides Unit Quarte rj Quarterl Quarterl QuarterL Released Na-24 Ci
- OE0
- OE0
- 2. 4M-05 4.24E-03 Ni> 97 Ci
- OE0
- GE0-7.0 L OS 1 nar.na
' h-239 C}
- gen
- nrn
- nga
- 1. M na Itu-105 Ci
- OE0
- oEn
- nrn 3.75E-06 sb-122 Ci
- OE0
- GEO
- GEO 3.49E-05
$b-174 Ci
- OED
- gen
- OE0 3.48E-04 Te-132 C1
- GEO
- Gro
- DED 1_ aw ns W-181 C1
- GEO
- nrn 2.17E-05 5.RX-03 Zr-97 Ci
- OE0
- oEn 1.05E-04
- 1. 2X-04 Xe-133m Ci
- GED
- nrn e nra 2 aor-os Ee-132s Ci
- nrn
- OE0 e nrn 4.20E-6 Xe-133 Ci
- OE0
- GEO 4.EaE.oS 1 A7F_n1 Ee-135 Ci
- cro
- nrn 7 aar-es i anr_n1 Ci O
ci ci Ci
-..m gg
.cl u rt w
CL gt gg
., g : v
.. ct C1
.j ei j
i Zeroe is thisstahls tedicate that no radioactivity was present above I
detectable levels. See Table 1-5 for typical lower limits of detection for 11 W inNishifess.
h Time rx u mm nm ::.
was um m u~
. u t, -,.
arv i
1 l
l l
1 l
O l
c
.19
I
.O TABLE l-4a VOCTLE ELECTRIC GENERATING PI. ANT SEMIANNUAL EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RFLEASES March 9 TRROUGH June 30, 19 87
~
UNIT 1 Cumuletive Does Per Quarter j
Organ Tech Unite Quarter 1
% of Quarter 2 Spec Tech' Tech Limit Limit Limit Bona 5.0 aren/str 6.57E-08
< 0.01 8.03E-05
< 0.01 Liver 5.0 ares /qtr 1.58E-07
< 0.01 3.52E-04 0.01 T. Sody 1.5 area /etr 2.saE-07
< 0.01 3.6 K-04 0.03 Thyroid 5.0 ares /etr 4.19E-07
< 0.01 5.00E-04 0.01 Kidney 5.0 ares /qtr 4.20E-08
< 0.01 5.11E-05
< 0.01 Lung 5.0 ares /etr 3.57E-na e n.nl 4.1m-os
< n n1 GI-LLI 5.0 ares /qtr 2.24E-05
< 0.01 2.75E-02 0.55 Cumulative Dose Per Year 3rgan Tech Units Year To Date I of Tech Spec Limit Spec Limit i
Bone 10.0 mram/se, 8.0 1-05
< 0.01 Liver 10.0 aren/etr
'3.52E-04
< 0.01 T. Body 3.0 mesm/ste 3.62E-04 n at rhyroid 10.0 mram/str 5.00E-04 n ni Kidney 10.0 ares /etr 5.14E-05
< 0.01 Luan 10.0 aren/etr 4.20E-05
< 0.01 GI-LLI 10.0 ares /qtr 2.75E-02 0.28 1
b
-s=
0 1
20 b
3 o
i 1
TABLE 1-5 (Page1of3)
LOWER LIMITS OF DETECTION - LIQUID SAMPLE ANALTSES V00YLE ELECTRIC GENERATING FLANT March 9 THkOUCHM. 1987 SITE The values in this table represent spriori lovar limits of detection (LLD) which are typically achieved in laboratory analyses of liquid radweste i
samples.
Radionuclides LLD Units Hn-54
-9.87E-09 uCi/mi Fe-59 7.91E-10
$1Al Co-58 1.12E-08 4141 Co-60 1.03r-os ei *1 Zn-65 7,3g g, y m, Mb99 6.94E-08
- N1 O
C-i>4
- 1.,,-08
< ms Cs-137 1.iar-on
- i
Co-141 1.73E-06 Co-144 7.37E-os
- i"'
I-131 1.21E-08 dWI Ie-133 2.93E-06 dMI Ie-135 1.05E-08 MCihl Ye-SS 1E-06 nacihl" St-49 e mi '
sr.s Sr-90 7g.g
< < mi E-3 2E 06
- WI Gross Alpha 7E-8
'~ Wihl O
21 i
b
4 O
l TABLE 1-5 (Page 2 of 3)
LOWER LIMITS OF DETECTION - LIQUID 5A30U ANALY$ts V0G"LE ELECTRIC GENERATING FLAlff Mareh fBROUG8 June 34 19 87 E
The values in this table represent spriori lower limits of detection'(LLD) l which are typically achieved in laboratory analyses of liquid radweste samples.
t.
l Radionuclides LLD-Units i
Au-19s e 77r no uCi/ul 84-140 4.86E-8' sif.3 l
, Se 7 8.27E-8 mCf/el Co-57 7.46E-9
- 4/m1 Cr-51 9.18E-8 uct/m1 i
Cs-138 5.37E-8 uti/mi I-133
- 1. 3M-g
.ei e-i 1
1-135 4.59E-8 sa at La-140
- m. eft-e si e-1 b 56 7.2M-a di An1 l
Ra-24
- 1. sm a
.e4 e.,
- 1/=1 ub-es
- 1.1K-a 4
I di/m1 l
le>-97 1.2 1-8 l
lip-239
- 2. 62E-8 di/el l
Itu-205 5.24E-8 pC1/el 56-122 1.79E-8 pCi/el Tc-99s 8.93E-9 uC1/mi TE-132 1.01E-8
,Isci/el l
O l
l e
i TABLE l-5 (Page 3 of 3)
LOWER LIMITS OF DETECTION - LIQUID SAMPLZ ANALYSES vocTLE ELECTRIC cturmATING FLANT March 9 THROUcH June 30. 19 87 The values in this table represent spriori lower limits of detection (LLD) which are typically achieved in laboratory analyses of liquid radweste samples.
Radionuclides LLD Unite W-187 4.3w-s uCi/mi Ie-131s 3.57E-7 uCf/al Ie-1338 7.39E-8 iti/n1 Zr-95 2_37E-a uct /m1 Zr-97 9.73E 9 di/mi Sb-124 1_7or.n
'N=1 O
i l
w i
i ya%
e i
i O
l 3
l i
l I
I l
O i
l
{
Effluent Manstement Systes Sesi-annual Reports
{
l l
1 l
BATCH REI. EASE
SUMMARY
--LIQUID AND CASE 00$
TABLE 1-6 Georgia Power Company Vogtle Electric Generating Plant BAICE RELEASE
SUMMARY
OF AIL RELEASES Starting:
March 9, 1967 Ending_ June 36. 1987 O
LIQUID RELEASES I
NITrGER OF R E 9 ' M 348 TOTAL TIME FOR ALL RELEASES :
28401 MINUTES NAZUEN TIME FOR A RELEASE :
265 MINUTI3 AVERAGE TIME FOR A art.nAst :
81.61 MINUTES MININEN TIME FOR & RELEASE :
AVERAGE STREAM FLOW 5
MD NTES 58.59 GPM i
GAssoas RELEASES NIDGE. OF mmES 17 TOTAL TIME FOR ALL art zAMES :
138844 MINUTES MAIDEN TIME FOR A RELEASE 24138 MIN 7TES AVERAGE TIME FOR A EELIASE :
8167.29 MINUTES MDEIMtk TDS FOR & EELEASE :
7 MINUTES t
O a
f:
l l
l j
f 2.0 ge! Egg! EgghyggIg 1
()
2.1 REGULATORY LIMITS / TECHNICAL SPECIFICATIONS The Technical Specifications presented in this section-are L
for Unit l'
and are stated in part.
The instrumentation required may be found in Table 2-1 of this report.
2.1.1 Effluent Monitoring System T.S.
3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels.shown in Table 3.3-10 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specifications 3.11.2.la and 3.11.2.5 are not exceeded.
The Alarm / Trip Setroints of these' channels meeting Specification 3.11.2.la shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
2.I.2 Dose Rate Limit T.S.
3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond
("T the SITE BOUNDARY (see Figure 5.1-1) shall be limited i'
to the following:
a.
For noble gases:
Less than or equal to 500 arems/yr to the whole body and less than or equal to 3000 arems/yr to-the skin, and b.
For Iodine-131 and Iodine-133, for
- tritium, and for all radionuclides in particulate. form with
-half-lives greater than 8 days: less than or equal to 1500 arems/yr to any organ.
2.1.3 Air Dose Due to Noble Gas T.S.
3.11.2.2
,a.
The'nair dose-due to noble gas released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 5
mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
('
b.
During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 meads for beta radiation.
25 ww-----_-
r I
L l
L
)
2.1,4 Dose to Any Organ T.S.R3.11.2.3 The dose to a MEMBER OF THE'PUBLIC from Iodine-131.
Iodine-133,
- tritium, and all radionuclides in f
particulate form with half-lives greater.than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall i
be limited to the following:
I a.
During any calendar quarter:
Less than or equal to 7.5 areas to any organ and, b.
During any calendar year:
Less than or equal to 15 areas to any organ.
4 2.1.5 Ventilation Exhaust Treatment System and Gaseous Waste Processing System T.S.
3.11.2.4U The VENTILATION EXHAUST TREATMENT SYSTEM and the GASEOUS WASTE PROCESSING SYSTEM shall be OPERABLE, and appropriate portions of these systems shall be used to reduce releases. of radioactivity when the projected
}]
doses in 31 days due to gaseous effluent releases, from i
each
- unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) would exceed:
a.
0.2 mrad to air from gamma radiation, or b.
0.4 mrad to air from beta radiation, or c.
0.3 area to any organ of a MEMBER OF THE PUBLIC.
2.1.6 Explosive Gas Mixture T.S.
3.11.2.5 The concentration of oxygen to the GASEOUS WASTE PROCESSING SYSTEM shall be limited to less than or equal to 2%
L-volume whenever the hydrogen concentration exceeds 4% by volume.
2.1.7 Activity in Gas Tanks T.S.
3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 2.0E5 Curies of noble gases (considered as Xe-133 O
equivalent).
1 26 m.____________
2.1.8 Total Fuel Cycle Dose Commitment
)
T.S.
3.11.4 The annual (calendar yeas) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrens to the whole body or any
- organ, except the
- thyrold, which shall be limited to less than or equal 15 mrems.
AEELicesILIIy agI1gy:
At all times.
a.
With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2a, 3.11.1.2b.
3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b.
calculations shall be made including direct radiation contributions from the unit (including outside storage tanks etc.) to determine whether the above limits of specification 3.11.4 have been exceeded.
T.S.
6.8.1.4 states in part:
O The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other uranium fuel cycle resources within 8 km, including doses from primary effluent pathways and direct radiation, for the previous. calendar year to show conformance with 40 CPR part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation".
Acceptable methods for calculating the dose contribution from 11guld and gaseous effluents are given in Regulatory Guide 1.109 Rev.
1, October 1977.
2.1.9 Reporting of Sealannual Releases (Unplanned)
T.S.
6.8.1.4 states in part:
j
\\
The Semiannual Radioactive Effluent Release Reports 1
shall include a
list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and 11guld effluents s
made during the reporting period.
O VEGP unplanned releases are described in section 1.6 of this report.
27
1 TABLE 2-1 (Sheet 1 of 4)
([)
IAELE asa-12 L
ReR19&EIlyg geSgggS gggggggI gggliggigG ingIgggggIgitqn MINIMUM CHANNELS l!!IBMMEHI 9EEBeakE AEEk1EA!!LIII AEI19E 1.
GASEOUS WASTE PROCESSING a.
Noble Gas Activity Monitor-Providing Alarm and Automatic l.
Termination of Release (ARE-0014) 1 45 j
b.
Effluent System Flow Rate Measuring Device 1
46 (APT-0014) 2.
GASEOUS WASTE PROCESSING SYSTEM Explosive Gas Monitoring System a.
Hydrogen Monitor 1/recombiner 50
()
b.
Oxygen Monitor 2/recombiner 49 3.
CONDENSER AIR EJECTOR AND STEAM PACKING EXHAUSTER SYSTEM a.
Noble Gas Activity Monitor (RE-12839C) 1 47 b.
todine Sampler (RE-128398) 1 51 c.
Particulate Sampler (RE-12839A) 1 51
- d. Flow Rate Monitor 1
46 (PT-12839) (FIS-12862)*
e.
Sampler Flow Rate 1
46 Nonitor (FI-13211)
O 28
l TABLE 2-1 (Sheet 2 of 4)
($)
IARLE aca:12 g&Q12&Ellyg gaggggS gggggggi squiigging igSIgggggIgI1gg MINIMUM CHANNELS IE!IBEMEHI!
9f!Ee!LE eEELISea111IX AEI195 l
1 4.
PLANT VENT A.
Noble Gas Activity Monitor (RE-12442C or RE-12444C) 1 47, 48 b.
Iodine Sampler / Monitor (RE-12442B or RE-12444B) 1 51 c.
Particulate Sampler /
Monitor (RE-12442A or RE-12444A) 1
$1
- d. Flow Rate Monitor (RE-12442) 1 46 e.
Sampler Flow Rate
[~)
Monitor (FI-2.
' :? or FI-12444) 1 46 Ie!LE E9IAI19EE At all times.
During GASEOUS WASTE PROCESSING SYSTEM operation During radioactive releases via this pathway During Emergency Filtration r-o O
29
I TABLE 2-1 (Sneet 3 of 4)
IAEkE 2 2:12 LQggtJgugdl ASI19E EIAI!!! HIE ACTION 45 With the number of channels OPERABLE less than requirtd by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to inftlating the i
release:
a.
At lenst two independent samples of the tark's.
contents are analyzed, and i
b.
At least two technically quallfled members of the facility staff independently verify the release rate calculations and discharge valve lineup.
Otherwise, suspend release of radioactive affluents via-this pathway.
ACTION 46 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 47 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l ACTION 48 With the number of channels OPERABLE less than required l
by the Minimum Channels OPERABLE requirement, immediately suspend containment purging of radioactive effluents via this pathway.
ACTION 49 a.
With the outlet oxygen monitor channel inoperable, operation of the system may continue provided grab samples are taken and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and'the o x y g e n c o n c e n t r a t'l o n 'r e m a i n s less
~
t h i n~ 1 " p e r c e'n t'.
e ut e rs l
b.
With the inlet oxygen monitor inoperable, operation may I
continue if inlet hydrogen monitor is inoperable.
4 30
1 TABLE 2-1 (Sheet 4 of 4)
([)
IARkt 1 1:10 1Een11nnadi IARLE E9I6I12EE LEen11auedl c.
With both oxygen channels or both of the inlet oxygen and inlet hydrogen monitors inoperable, suspend oxygen supply to the recombiner.
Addition of waste gas to the system may continue provided grab samples are taken and analyzed at least once per 4
hours during degassing operations or at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations and the oxygen concentration remains less than 1
percent.
ACTION 50 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiner.
Addition of waste gas to the system may continue provided grab samples are taken and analyzed at least once per 4
hours during degassing operation or at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations and the oxygen concentration remains less than 1 percent.
O ACTION 51 With the number of channels operable less than required by the Minimum channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.
9 i
l
([)
1 31
2.2 RELEASE POINTS OF GASEOUS EFFLUENTS Gaseous Effluents at Vogtle Electric Generating Plant are currently confined to two paths:
plant vent (Unit 1),
and the condenser air ejector and steam packing exhauster system (Unit 1).
Waste gas decay tanks are batch releases and both the waste gas decay tanks and containment purges are released through the Unit 1 plant vent.
2.3 Sample Collection and Analysis Both of the paths can be continuously monitored for gaseous radioactivity.
Each is equipped with an integrated-type sample collection device for collecting particulate and lodines.
Sample collection is in accordance with Technical Specification Table 4.11-2.
During this release
- period, there were no radioactive releases through the condenser air ejector and steam packing exhauster system vent.
Unless required more frequently under certain circumstances specified in Table Notations to the above mentioned tables, sam,les are collected as follows:
1.
Noble gas samples are collected by grab sampling monthly.
()
2.
Tritium samples are collected by grab sampling monthly.
3.
Radiolodine.sampleo are collected by the sample stream through a charcoal cartridge over a 7-day period.
4.
Particulate are collected by the sample stream through a particulate filter over a 7-day period.
5.
The 7-day particulate filters above are analyzed for gross alpha activity.
6.
Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the quarterly composite sample is analyzed for Sr-89 and Sr-90.
Batch releases are analyzed for lodines, particulate and noble gases, and H-3 before each release.
In addition, the containment atmosphere is analyzed for tritium on at least a monthly basis.
Sample analyses results and release flow rates from the two release points form the basis for calculating released quantitles of radionuclides specific radioactivity, dose rates associated with gaseous releases and cumulative doses
()
for the current quarter and year.
This tank is normally l
performed with computer assistance.
32
l' The noble gas grab sample and analysis (from principal gamma esitters) results are used along with maximum expected l
I) r61 ease flow rates from each of the vents to calculate
{
monitor setpoints, for the gaseous effluent monitors serving j
the two release
- points, to assure that the limits of l
Technical Specification 3.11.2.la are not exceeded.
Calculation of monitor setpoints is described in the Vogtle Electric Generating Plant ODCM.
l With each release period and batch release, radioactivity, dose rates and cumulative doses are calculated.
Cumulative dose results are tabulated, along with percent of Technical Specification limits (3.11.2.2 and 3.11.2.3), for each release for the current quarter and year.
After each calendar quarter (13 weeks),
a summary of waste gas releases from the two vents and batch processes is complied for preparation of the Semlannual Radioactive Effluent Release Report required by Technical Specifications 6.8.1.4 and NRC Regulatory Guide 1.21.
2.4 DETERMINATION OF TOTAL QUANTITIES OF RADI0 ACTIVITY, DOSE RATES AND CUMULATIVE DOSES The methods for determining release quantitles of radioactivity, dose rates and cumulative doses are as followas O
2.4.1 F1_asion,and Activation Oas The radionuclides-specific released radioactivity is determined from sample analyses results collected as described above and average release flow rates over the period represented by the collected sample.
(Instantaneous dose rates due to noble. gases and due to
'radiolodines, tritium, and particulate are calculated (with 4
-desputer-assistance).
Calculated dnse' rates are compared to l
'the" dose rate limits specified in 3.11.2.la for noble gases; j
a'n d fav44 J#.1 b f or > r a d i o l o d i n e,
- tritium, and particulate, i
Dose'* rate calculation methodology is presented in the ODCM.
I tc-.-
1 Il}WE[FTocationIn* '" nd gamma air doses due to noble ases are calculated a
Y$r t h e -u ri r e s t r i ct e d (r e-w i t h the potential j
for the highest exposure due to gaseous releases.
Air doses are calculated for each release period and cumulative totals
{
are kept for each unit for the calender quarter and year.
Cumulative air doses are compared to the dose limits specified in Technical Specification 3.11.2.2.
Current percent of the technical specification limits are shown on the printout for each release period.
Air dose calculation l
methodology is presented in the ODCM.
l l
l 33 1
2.4.2 Radiolodine. Tritium and Particulate Releases
/~(,T Released quantitles of radiolodines are determined from the
)
weekly samples and release flow rates for the two release points.
Radiolodine concentrations are determined by gamma i
spectroscopy.
Release quantitles of particulate are determined from the weekly (filter) samples and release flow rates for the two release points.
Gamma spectroscopy is used to quantify concentrations of principal gamma emitters.
After each calendar month the particulate filters from each i
vent are
- combined, fused, and a strontium separation is performed.
If Sr-89 or Sr-90 is not detected.
LLD's are calculated.
Strontium concentrations are input to the i
composite file of the computer to be used as
- release, dose rate and individual dose calculations.
)
l Tritium samples are obtained monthly from each vent by
{
bubbling the sample stream through a water trap.
The tritium j
concentration in water is converted to tritium concentration In air and this value is input into the composite file of the computer to be used in release, dose rate, and Individual dose calculations, j
l Dose rates due to radiolodine, tritium, and particulate are
()
calculated for a
hypothetical
- child, exposed to the inhalation pathway, at the location in the unrestricted area where the potential dose rate is expected to be the highest.
{
Dose rates are calculated for each release point, for each release
- period, and the total dose rate from both release points are compared to the dose rate limits specified in Technical Specification 3.11.2.lb.
~
1 Individual doses due to radiolodine, tritium and particulate are calculated for the critical receptor, which for Vogtle Electric Generating Plant is an infant exposed to the vegetation, inhalation, and ground-plane pathways, Individual doses are calculated for each release period, and cumulative totals are kept for each unit for the current calendar quarter and year.
Cumulative Individual doses are compared to the dose limits specified in.
. Technical Specification 3.11.2.3.
Current percent of technical specification limits are shown on the printout for each release period.
2.4.3 Gross Alpha Release The gross alpha release is computed each month by counting the particulate filters offsite for each week for gross alpha activity in a proportional counter.
The four or five weeks' numbers are then recorded on a data sheet and the activity O
is summed at the end of the month.
This concentration is input to the composite file of the computer and is used for 34
release calculations.
()L 2.5 GASEOUS EFFLUENT RELEASE DATA 2.5.1 Methodology Regulatory Guide 1.21 Tables 1A, 1B, 1C are found in this report as Tables 2-2a.
2-3a and 2-4a.
Data is presented on a quarterly basis as required by Regulatory Guide 1.21.
To complete Table 2-2a, total release for each of the four categories (fission and activation
- gases, lodines, particulate, and tritium) was divided by the number of j
seconds in the quarter to obtain a release rate in uC1/second for each category for the second quarter.
For the first quarter they were divided by the number of seconds since the day of initial criticality.
- However, the percent of applicable Technical Specification limits are not applicable because we have no curie 11alts for gaseous releases.
Noble gases are limited as specified in 3.11.2.la.
The other three categories (tritium, radiolodines, and particulate) are limited as a group as specified in 3.1.1.2.'1b.
Dose rates due to noble gas releases and due to radiolodine,
- tritium, and particulate are presented in Table 3-5 along with percent of technical specification limits.
Gross alpha radioactivity is reported in Table 2-2a as Curles released in each quarter.
Limits for cumulative beta and gamma air doses, due to noble
- gases, are specified in Technical Specification 3.11.2.2.
Cumulative air doses are presented in Table 2-6a along with percent of technical specification limits.
Limits for cumulative individual doses, due to radiolodine,
- tritium, and particulate, are specified in Technical Specification 3.11.2.3.
Cumulative individual doses are presented in Table 2-7a, along with percent of technical specification limits.
"" T h'e "~t o t a l t
or maximum error associated with the effluent measurement -will include the cumulative errors resulting h1fromcy M%M&e&y'Mf tMuit' tUs@g the total operation
..o f. samplin A(yt,,dge/. arms measurement.
M',hh nt err for
- "'sTa tYs t i c a'i.e (e.r a f f e c t i n g ed arge' ' evaluation of error are not suggested.
The the final measurement, detailed objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in 11guld and gaseous effluents and solid waste.
Estimated errors are based on errors in counting equipment calibration, counting statistics, vent flow
- rates, vent sample flow rates, non-steady release rates, chemical yield
()
factors and sample losses for such items as charcoal cartridges.
35
1.
Fission and activation total release was calculated
()
from sample analysis results and release point flow rates.
Sampling and statistical error 104 Counting equipment calibration 104 1
Vent flow rates 10%
Non-steady release rates gol
)
Total Error 50%
l 2.
I-131 releases were calculated from each weekly sample:
l Statistical error 10%
Counting equipment calibration 104 Vent flow rates 10%
Vent sample flow rates 10%
Non-steady release rates 10%
[}
Losses from charcoal cartridges 1Q1 Total error 60%
3.
Particulate with half lives greater than 8
days releases were calculated from sample analysis results and release point flow rates.
Statistical error at LLD concentration 10%
Counting equipment calibration 204 Vont flow rates 10%
Vent sample flow rates 10%
i
Non-steady' release rates 10%
Total error 50%
4.
Total tritium releases were calculated from sample analysis results and release point flow rates.
Water vapor in sample stream determination 10%
()
Vent flow rates 10%
36
Counting calibration and statistics 104
()
Non-steady release et+es 103 Total error 40%
2.5.2 Gaseous Batch Data Other data pertinent to batch releases of radioactive gaseous effluent from Unit 1 are listed in Table 1-6.
2 '. 6 RADIOLOGICAL IMPACT DUE TO GASEOUS RELEASES Dose rates due to noble gas releases were calculated for the site in accordance with Technical Specification 3/4.11.2.la.
Results are presented in Table 2-5.
Dose rates due to radiolodine,
- tritium, and particulate.in. gaseous releases were calculated in accordance with Technical Specification 3/4.11.2.1b.
These results are also in Table 2-5.'
l Cumulative air doses due to noble gas releases were calculated for each unit in accordance with Technical l
Specification 3/4.11.2.2.
These results are presented in Table 2-6a.
Cumulative doses to
'a n individual due to radiolodine, tritium, and particulate were calculated in accordance with O.
Technical Specification 3/4.11.2.3.
These results are presented in Tables 2-7a.
Dose rates and doses were calculated using the methodology presented in the Vogtle Electric Generating Plant Offsite Dose Calculation Manual.
4
,e
- wsu4 1
CA. in tui - s A b u :. c.
- . a:, s * ;
W.
g.:caen t,
. t L$6
- w.
44
(.,
.g'-*
naay 1
G O
37 1
1 l
I I
l I
O TABLE 2-2a I
VOCTLE ELECTRIC GENERATING PLA)rt SEKIANNUAL RADI0 ACTIVE ETTLUENT RILEASE RZPORT CASE 005 EFTLUENTS - SUNHATION OF ALL RELEASES l
March 9 THROUCH_ W, 1p 87 j
UNIT 1 I
Unit Quarter l Quarter 1 Est. Total Error !
A.
Fieeion & Activation gases l
l 1.
Total Release C1 1.669E-05 1.282E+1 50
)
2.
1Y5753e release 1
ete for seriod uC1/see 4.215E-06 7.66E-01 3.
I of Tech Spec l
limit u
u B.
Iodinee l.
Total Indina-131 ci
- 0.00E+0 E.56E-06 so O-2.
Average release rate for seriod uC1/see
- 0.0er+c 1_n?nr-n7 3.
I of Tech Spec limit if u
u d.
Partic'ulatee
~
1.
Partic1 slates with half-lives greater 1
th== A dava c1 1.301E-07 4.158E-06 50 2.
Average release rate for seriod uti/see 3.?86E-08 2.485E-07 l
- 3.
I of Tech Spec limit u
u 4.
Gross alpha radioactivity Ci
- 0.00E+0
- 0.00E+0 D.
Trities l
- 1.
- Total release ci
- 0.00E+0 4.996E-01 40 l
2.
Average release
{
rate for stI12sl uCi/see
- 0.00E+0
? QRSF-o?-
3.
1 of Tech Spec limit.
I M
M
- Yalues are less than LLD. see Table 2-8 for LLO values.
l E
m -
g.
j Y
'l' I
d 5
l TABLE 2-3a (Fage 1 of 2) 4, VOCTLE ELECTRIC GElfERATIlec P!AllT SDf!AleNUAL RADI0 ACTIVE EFFLifENT RE! ORT GASEOUS EFFLtTENTS - HIEED N0DE March 9 TRROUCR June 30 19 L e
y UNIT 1 4
Continuous Mode latch Mode 1
Nuclides Unit Quarter 1 Quarter 2 Quarterl Quarter t b
Released
)
1.
Fission Cases k' '
sU Kr-85e Ci
- OE0
- OE0 1.18E-G
- 0E0 Kr=47 Ci
- OE0
- OE0 2.88E-7
- 0E0 Kr-44 Ci
- DEO
- DEO 1.nar-8
- 0E0 I6-135 Ci
-
- OE0 3.50E0 8.5aE-6 2.10E-1 Ar-41 Ci
- DEO 5.82E0 3.36E-6 2.94E0 Ft131m C1
- OE0
- OE0
- nro 6.48E-4 a
3 10TAL FOR PERIOD Ci OE0 9.34E0 1.67E-5 3.46E0 9
i Q.
Iodises I
l hI-131 Ci
- OE0 5.56E-6
- OE0
- OE0
'I-133 C1
- OE0 2.56E-5
- OE0
- OE0 TOTAL FCE P RIOD Ci 0E0 3.11E-5 OE0 OE0 l
j s-i O
1 i
)
b' O
V TAet,E 2-3a (Page 2 of 2)
YOCTLE ELECTRIC GENERATING PLANT 3DtIANNUAL RADIDAC"IIVE EFFLUENT REPORT GASECUS EFFLUENTS - MIXED MBE March 9 THROUct June 30, 19 87 UNIT 1
\\
Continuous Mode Batch Nede s
r
(
Nuclides Unit Quarter _1 Quarterj Quarter 1 Quarte e_2 Released I
4 I
lI d).
Particultees a*
3 s
?
Co-58 Ci
- OE0 4.14E-6i
- OE0
- OE0 t
i e
Rb-88 iCi
- OE0
- OED 1.30E-7 OE0
~~
~
n-3 ici
- OE0
- 05,0 OE0 4.98E-1 I
4
\\
s4 i
O. >
t
\\ f.
,\\
w.
,g k
g i
1,
\\nD
~
1 g
jy !(
s 3
j 4
bi s
s a
j
.c r
p
.x,
TCffAL FOR 7E12(B.
Ci N OED
, 4.14E-( t 1.30E-7 4.98E-1 4
L,,
i.
"J
, r. 3. -
u,,
mts z r. i s'
- L % roes ~,ta this. tabla @ dicate that no radi'oset'trdcy was present above i
.Lf detecW41e levels.- pe -Table 2-8 for typical lower limits of detection-fos t
t 7,ogseeonaremple analyp m
)
r
, j 3
Ealf 1.1 Pas greater thas 8 days.
N s
i t.
i
'h s
\\
'~.
'i i g 4
s'
\\
g
(
y y
f
't y
(,
\\
\\
r 1
i..>
k i
\\
\\
t
\\
),'
s 40 t,
t
'I i_
\\'
]
d
'l TA8LE 2-4a (Fa8e 1 of 2) l i
1 V0GTLE ELECTRIC GENERATING FLAlff f
SENIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - GROUND LEVEL
- March 9 THROUGH
.s-m. 1E UNIT 1 1
Continuous Mode 1
Batch Mode l
Nuclides Unit Quarterj Quarte rl Quarter;t, Quartern t
Released 1.
Fission Gases i
Kr-85 C1 Kr-8$s C1 i
1 Kr-87 Ci Kr-88 C1 Ia-133 Ci N'
Xe-135 C1 U-Ke-13Se Ci Ie-l38 Ci Ie-133e Ci l
3-1 l
TOTAL 101 PERIOD Ci 2.
Isdines*
i 1-131 ci I-133 C1 4
I-13$
Ci 1
TOTAL FOR PERIS Ci j
4
- No releases during this period.
1 6..
1 th A1
)
J O
1 TABLE 2-4e (Page 2 of 2)
'{i
{
VOCTLE ELECTRIC CENERATING FLANT SENIANNUAL RADI0 ACTIVE EFFLITENT REPORT G&SEOUS EFFLITENTS - CROUND LEVEL March 9 THROUCE. June E, 191 UNIT 1 i
l Continuous Mode Batch Mode q
Nuclides Unit Quarterl Quartera Quarterj Quarter 2 Released 3.
Particulate h-54 Ci i
Fe-59 Ci Co-58 C1 Co-60 C1 Za-65 Ci
$r-89 C1
(
Eb-95 Ci I
Co-134 C1 Cs-137 Ci Sa-140 C1 1
La-'140 C1 Ca-1&&
C1 Co-141 Ci 1
TOTAL FOR PERIOD Ci Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
Also there were no releases during this period.
Esif lives greater than 8 days.
6 _.
O 42 a
O TABLE 2-5 V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - DOSE RATES March 9 T11ROUCE June 30, 19 87 UNIT 1 Dose Rates Due To Noble Gases Organ Tech Units Quarte r
% of Quarter Spec 1
Tech 2
Tech Limit Limit Limit T. Body 500 ares /yr 1.1E-2 2.2E-35 1.95E+0 3.90E-015 Skin 3000 ares /yr
- 1. 7E-2 5.67E-45 3.01E+0 1.00E-015 Dose Rates Due to Radioiodine, Tritium and Particulate Organ Tech Units Quarter
% of Quarter Spec 1
Tech 2
Tech Limit Limit Limit O
Bone 1500 ares /vr OE0
<.011 5.15E-6 3.43E-75 Liver 1500 aren/vr OED
<.011 1.aarn 9.87E-M f.~Rody 1500 ares /yr OE0
<.015 1.48E0 9.87E-25 Thyroid 1500 mres/yr GED
<.011 1 amrn 9_ a7E-M Ridney 1500 ares /vr CEO
<.015 1.48E0 9.87E-25 Luna 1500 area /yr OE0
<.015 1.48E0 9.87E-25 GI-LLI 1500 ares /yr OE0
<.015 1.48E0 9.87E-25 __
1 l
l w.
O 43
i (3
v TA3tE 2-6a V0GTLE ELECTRIC GENERATING PLANT SD(IANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT A:n DOSES DUE TO NOBLE GAS RELF.ASES March 9 THROUGE June 30, 19 87
~
UNIT 1 Type Of Tech Units Quarter
% of Quarter Radiation Spec 1
Tech 2
Tech Limit Limit Limit 3
Gaasa 5.0 arad 1.62E-7
< 0.15 2.02E-1 4.035 Beta 10.0 mrad 9.48E-8
< 0.15
- 8. 63E-2 0.865 Cumulative Doses Per Year (Year To Date)
Gamma 10.0 arad 2.02E-1 2.025 g>
Beta 20.0 arad 8.63E-2
.435 IW i.
' aJ s f
J f
s s
l l
1 I
}
l I
J b-1 l
O 44
O TABLE 2-7a l
l V0GTLE ELECTRIC GENERATING PLANT 4
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADI0 IODINE. TRITIUM AND PARTICULATE IN GASEOUS RELEASES l
_ March 9 THROUGH June 30. 19 87 UNIT 1 Cumulative Dose Per Quarter t
'I Organ Tech Unite Quarter 1 of Quarter I
Spec 1
Tech
.2 Tech Limit Limit Limit i
Bone 7.5 ares CEO
< 0.15 3.62E-7
<.015 Liver 7.5 ares CEO
< 0.15 8.14E-5
<.015 T. Body 7.5 ares CEO
< 0.15 8.75E-5
<.015 Thyroid 7.5 ares OE0
< 0.15 1.08E-4
<.015
-Kidney 7.5 aren OED
< 0.11 8.74E-5
<.015 Luna 7.5 area OEO
< 0.11 8.76E-5
<.015 GI-LLI 7.5 mrom CEO
< 0.1g 8.76E-5
<.015 Cumulative Dose Per Year 1
Organ Tech Unitt Year To Date Z of Tech Spec Limit Spec Limit 1
n~
Bone 15.0 area 3.62E-7
<.015 Liver 15.0 area 8.74E-5
<.015 T. Sody 15.0 ares s.7EE-E
< _011 Thyroid 15.0 area 1.0aE-4
<.011 Kidney 15.0 aree a,74E. s
.,.01s Lung 15.0 area e,ysir_s
< _ott GI-LLI 15.0 mrom 8.76E-5
<.015 bW pJ 45
l p
TABLE 2-8 1
LOWER LIMITS OF DETECTION - CASEOUS SAMPLE ANALYSES V0GTLE ELECTRIC CENERATING PLANT March 9 THROUGH _ June 20. 19 87
{
UNIT 1 j
1 The values in this table represent apriori lower limits of detection (L1D) which l
are typically achieved in laboratory analyses of gaseous radvaste samples, j
l l
l (RADIONUCLIDES LLD UNITSj Kr-67 1.03E-07 uci/mi l
I Kr-86 4.77E-08 di/e1 l
Xe-133 2.47E-GR diMI l
Xe-133s 7.6 1-08 di/el i
Ka-135 1.2nE-os dih1
{
Ie-138 7.36E-05 dih1 l
I-131 4.54E-15*
gt/mi j
Mn-54 7.12E-15*
gi/mi I
Fe-59 1.6E-14*
dih1 Co-58 1.23E-14*
dih1_
Co-60 1.41E-14*
diam 1 Zn-65 1.34E-14*
dih1 No-99 s 27E.:1a*
di41_
i Co-134 5.52E-15*
dihl Co-137 1.19E-14*
dihl 1
Ce-141 s_seE-15*
21/mi
]
Ce-144 2 aar la*
di/m1, l
Sr-49 t r_ i s*
din l
5r-90 1E-13*
di/8 l
5-3 9E-0B*
di/el GROSS ALFEA 1E-13*
$1/mi t
- Based on an estimated sample volume of 5.7E8 mis, j
l f.
- 9 i L' l
\\
l
(
i I
1 O
1
. 3.' O 1 0,,k J.R M A ! T E
()
3.1 REGULATORY LIMITS / TECHNICAL SPECIFICATIONS i
The Technical Specifications presented in this section are for. Unit end are stated in part.
3.1.1 Use of Solid Radioactive Waste System l
T.S.
3.11.3 Radioactive wastes shall be solidified or dewatered in accordance with the. PROCESS CONTROL PROGRAM to meet shippir; and transportation requirements during i
t r a n r. i t,
and disposal site requirements when received d
at ::he disposal site.
l 3.1.2 Reporting Requirements T.S.
6.8.1.4 The Semiannual Radioactive Effluent Release-reports shall include a
summary-of the quantitles of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory l
Guide 1.21.
" Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of O
Radioactive Materials in Liquid and Gaseous-Effluents j
from Light-Water-cooled Nuclear Power.
Plants",
l Revision 1,
June
- 1974, with data summarized on a
quarterly basis following the format of Appendix B
thereof.
For solid wastes, the format'for Table 3 in Appendix B shall be supplemented with three additional categories:
class of solid wastes (as defined by lo CFR Part 61), type of container (e.g. LSA. Type A, Type
'B, Large Quantity) and SOLIDIFICATION agent or absorbent (e.g.,
cement, uren formaldehyde).
3.1.3 Process Control Program (PCP)
-n T.S.
6.12.1 l
The PCP shall be approved by the Commisssion' prior-to implementation.
.e o
T.S.
6.12.2 i
Licensee - initiated changes to the PCP:
a.
Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made.
This submittal shall contain:
47 l
t
__,.,.,__.-_v-
' - - - - ' - ' " ' ' - - - ' ' ' ~
1 I
1)
Sufficiently detailed information to totally support the rationale for the change without.
()
benefit of additional or supplemental information:
1 2)
A determination that the change did not i
reduce the overall cotivraance of the solidified waste product to eristing criteria for solid wastes; and
~
3)
Documentation of the fact that tha change has 1
been reviewed and found acceptable by the I
- PRB, b.
Shall become effective upon approval by the GMVNO.
For this reporting period there were no. changes to the PCP.
The Staffs. Safety Evaluation Report (SSER)
Chapter 11 Indicates that our,
"...PCP meets the criteria of BTP ETSB 11-3 (NUREG-0800) and.of the current (1979) guidance.
The PCP is therefore.found acceptable, and confirmatory item f
39 is satisfactorily resolved".
)
3.2-SOLID WASTE DATA Regulatory Guide 1.22,' Table 3 is found'in this report as Table 3-la.
However. It should be noted that there were no
(}
solid waste shipments made during this period.
O 48
O TABLE 3-la (Page 1 Of 2)
VOCTLE ELECTRIC CENERATING PLANT March 9 THROUGH June 30 e 19 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT
]
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNIT I Solid Weste Shipped Offsite For Burial Or Disposal (Not irradiated fuel)
{
l i
I 1.
Type of Waste UNIT 6 month Est. Total i
Period-Error %
l s
0.00E-01 0.00E-01 a.
Spent resins, filter studges, a
evaporator bottons, etc.
Ci 0.00E-01 s
b.
Dry compressible waste, contaminated a
0.00E-01 0.00E-01 equipment, etc.
Ci 0.00E-01
(
c.
Irradiated components, control n'
O.00E-01 0.00E-01 S.
rod etc.
Ci 0.00E-01 d.
Other (describe) oily trash, a
0.00E-01 0.00E-01 j
s speedi-dry six equipment, etc.
Ci 0.00E-01 Solidified oil, CRD filters 2.
Estimate of asfor nuclide composition (by type of waste)
ISOTOPE.
i PERCINI Curies f
s.
2n-65 1
Cs-137 i
Co-60 1
A11 others b.
In-65 s.
Co-60 O
c -ia7 All others
- No solid waste (uring this report period.
49
- p. s _..
1 t
f-b O
i TABLE 3-la (Page 2 Of 2)
V0GTLE ELECTRIC G DERATING PLANT March 9 THROUGH__ June 30__.
19 87 I
EFFLUDff AND WASTE DISPOSAL SEMIANNUAL REPORT
]
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNIT I ISOTOPE PERCST Curies c.
None shipped this period I
d.
All others O.
3.
Solid Waste Disposition
- No solid seeste during this report period.
1 Number of' Shipments Mode of Transportation Destination 0
4.
Irradiated Fuel Shipments (Disposition)
Numbor of Shinnento Mode of Transportation Deetinaeion l
0 b
e-O i
50
i l
\\
1 4.0
.EH&EEEE IQ IHE EQQILE ELEGIElE GENER&IlHE Ek&EI QQqH o
T.S.
6.8.1.4 Technical Specification 6.8.1.4 requires, in part, that changes to the Offsite Dose Calculation Manual (ODCM) be reported to the Commission in the next Semiannual Effluent Release Report.
l There was one change to the Vogtle Electric Generating Plant ODCM for the period March 9 thru June 30, 1987.
l T.S.
6.13.1 states in part:
The ODCM shall be approved by the Commission prior. to 1
implementation.
T.S.
6.13.2 Licensee-initiated changes to the ODCM:
f a.
Shall-be submitted to the Commission in the Semlannual Radi'oactive Effluent Release Report for the period in which the change (s) was made
)
effective.
This submittal shall contain:
1)
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.
Information submitted should
-consist of a package of those pages of the ODCM to be changed, with each page numbered, dated and containing the revision
- number, together with appropriate analyses or evaluation justifying the' change (s);
2)
A -determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and 3)
Docume'ntation of the fact'that the' change has been reviewed and found' acceptable ~' by the PRB.
b.
Shall become effective upon approval by the GMVNO.
Revisions 0 and 1 were poi implemented during this report period.
Revision 2
of the ODCM was implemented and was approved by the NRC as described in the letter from Director B.
J.
Youngblood to Mr. James P.
O'Reilly dated January 13 Os 1987.
A copy of this letter is in Attachment A.
51
l l
7 Revision 3
of-the ODCM was reviewed by PRB on 4/1/87 at i
l meeting number PRB-87-79.
The GMVNO approved the revision I
7")
on 4/2/87.
A copy of the Licensing Document Change Request, the Safety Evaluation, and the pages changed for Revision 3 q
are included in Attachment A.
The change did not reduce the j
[
accuracy or reliability of dose calculations or setpoint l
determinations.
l l
T.S.
3.12.1 states in part:
The Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.12-1.
Table Notation (1) states in part:
It is recognized that, at times, it may not be possible or practicable to continue to obtain.. samples of the media of choice at the most desired location or time.
In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions, if available, will be made within 30 days in the Radiological Environmental Monitoring Program given in the
- ODCM,
. Pursuant to specification 6.13, submit in the next Sealannual Radioactive Effluent Release Report
/
documentation for' a change in the ODCM including a
revised figure (s) and table for the ODCM reflecting the (3
new J, cation (s),
if any, with supporting information
()
Identifying the cause of the unavailability of samples l
for the pathway and justifying the selection of the new location (s) for obtaining
- samples, or the unavailability of suitable new locations.
1 T.S.
3.12.2 states in part:
i A Land Use Census shall be conducted
(
The Action Statement for this requirement states in part:
i a.
With a Land Use Census identifying a location (s) l that yields a calculated dose or dose commitment I
greater than the value currently being calculated in specification 4.11.2.3, pursuant to specification 6.8.1.4, identify the new location (s) in the next Semiannul Radioactive Effluent Release Report.
l 4.1 CHANGES IN THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l
l
(])
The first Land Use Census since initial criticality which occurred on March 9,
- 1987, was conducted on April 27-28.
l I
52 l
1
1987.
A garden greater than 500 square feet producing broad leaf vegetation was identified in the WSW Section at 1.3
()
miles.
The calculated dose comajtment for this location is greater than 20% of that for any of the other locations at j
which vegetation is currently sampled.
This new location i
for collecting vegetation has been added to the Radiological
(
Environmental Monitoring Program (REMP) and subsequently will be inscribed in Section 3.0 of the ODCM.
The various sampling locations for the REMP are delineated in Section 3.0-1 of the ODCM.
Location 91 (Coleman's) in
}
Table 3.0-1 is listed as a milk sampling location in the WNW Sector at 2.8 alles.
Hilk was collected at this location from a family cow for use in the preoperational phase of the REMP from December 1985 through April 1986 at which time the
(
cow went dry.
The Coleman's had the cow moved from the area to be bred and thought at that time that it would be returned in about a year when it was producing milk again; this did not come about.
The Coleman's no longer want to have a cow to milk.
Location 91 is to be deleted from Table 3.0-1 and Figure 3.0-2 of the ODCM.
No allk animals were i
found in the Land Use Census conducted on April 27-28, 1987.
1 Several other changes will be made to Section 3 of the ODCM during the next report period.
Attachment B describes the changes and provides the justification for the changes.
l l
()
)
J l
\\
I l
1 l
1 l
I l
53
1 1
i L
5.0 poggg Tg Mgggggg pg Igg EggLIC Iggigg Tgg $171 ggggpAgY k
1':1 T.S.
6,8.1.'4
~ states in part:
^,
i L
The same report.shall also include assessment of the L
radiation doses from radioactive 11guld and gaseous effluents to MEMBERS OF THE PUBLIC due to their j
activities inside the Site Boundary
(_ Figure
'5.1-1) during the report' period.
All assumptions used.in making these assessments, i.e.,
specific
- activity, exposure. time, and location, shall be included in these i
reports.
l
(
The locations of concern within the site boundary are the Visitors Center and Plant'W11 son.
There will be no radiation dose.at these locations due to radioactive 11guld effluents.
Delineated in Table 5-1 for'each of these' locations are the I
values of the. basic data assumed in the dose assessment due to radioactive gaseous effluents.
Listed in this table are:
{
the distances and directions from a point midway between the 4
center of Unit 1 and the Unit 2 reactors:
the dispersion and deposition factors for any releases from the plant vent 3
(mixed mode) and from the turbine building _
(ground level);
J and the estimated maximum occupancy. factor for an individual and the assumed age group of this individual.
v"3 Not listed in Table 5-1 la the source term.
Listed in Table
\\J 2-4a for the ground level releases and in Table 2-3a for the mixed mode releases are the noble gases, radiolodines, and particulate with half lives greater than eight days; these-are tabulated by radionuclides and by quarter.
The tritium releases in units of curies were as follows:
I Quarter 1
g 1
l Mixed Mode gga gug8g-1
(
The maximum doses in units of arem. accumulated by an individual MEMBER OF THE PUBLIC due to their activities inside 'the site boundary during the first half of the year were assessed to be as follows:
ELEllaEE EEEIEE Ek&EI Elk 12E Total Body luq5g-5 1261g-g (direct radiation from plume) l Maximum Organ (Thyroid) 158E-8 1;&gg-5 (inhalation and gtound-plane) l l
l 54
j:
TABLE 5-1 y'
Basic Data Asstased in Dose Assessments To EDEBERS OF THE PUBLIC Item Visitors Center Plant Wilson 1
Distance (meters) 447 1420 Sector SE ESE X/Q (sec/m2)'
1)
- 1. 05E-4 2.20E-5 Depleted X/Q (sec/m2) 1)
9.90E-5 1.98E-5 D/Q (m-a) 1)
7.32E-8 1.63E-8 X/Q (sec/m8)
(2) 8.53E-6 2.75E-6 DepletedX/Q(sec/m2) (2) 8.04E-6
~2.40E-6 0/Q (m-a)
(2)
- 9. 49E-9 5.02E-9 Occupancy factor (hrs /yr) 0.00046 0.228 Age group Child Adult (1) Ground Level Release (2) Mixed Mode Release Visitors Center Plant Wfison Quarter 1 Quarter 2 Total Quarter 1 Quarter 2 Total Total Body 8.88E-12 1.05E-5 1.05E-5
- 1. 42E-9 1.67E-3 1.67E-3 Organ Oose Bone 0
3.10E-10 3.10E-10 0
6.77E-8 6.77E-8 Liver 0
6.58E-8 6.58E 0 1.10E-5 1.10E-5 T8ody
- O
- 6. 58E-8 6.58E-8 0
1.10E-5 1.10E-5 Thyroid 0
8.56E-8 8.56E-8 0
1.29E-5 1.29E-5 Kidney 0
6.62E-8 6.62E-8 0
1.10E-5 1.10E-5 Lun9 0 '"
,,,6. 62E-8 '
, 6.62E-8 0
6:58E-8 6.58E-8 0
1.10E-5 1.10E-5 55
F.
i 1
i 6.o MA29R CH&gq[g IQ kigg1Q& QASEQQE QB EQklD RAQM&gTE TggATHEET j
l EXEIEME J
fl) l T.S.
6.8.1.4. states in part:
l The Semiannual Radioactive Effluent Release Report
]
shall include any major change to 11guld, gaseous, j
or solid radwaste treatment systems pursuant to i
Specification 6.14.
T.S.
6.14.1 Licensee-initiated major changes to the Radwaste Treatment Systems (11guld, gaseous, and solid);
a.
Shall be reported to the Commission in the l
Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PRB.
The discussion of each change.shall contain:
1 1)
A summary of the evaluation that led to the determination that the change could be made in accordance'with 10 CFR 50.59; l
2)
Sufficient detailed information to totally N
support the reason for the change without i
benefit of additional or supplemental information; 3)
A detailed description of equipment.
components, and processes involved and interfaces with other plant systems; l
4)
An evaluation of the change, which shows the l
predicted releases of radioactive materials in 11guld and gaseous effluents and/or quantity of solid waste that ~ differ from those previously predicted in the License Application and amendments thereto; 5)
An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the Unrestricted Area and to the i
general population that differ from those previously estimated in the License Application and amendments thereto, t
6)
A comparison of the predicted releases of radioactive materials, in 11guld and gaseous effluents and in solid waste, to the actual
()
releases for the period prior to when the change is to be made; 56
1 i
1 I
i
' )'.
7)
An estimate of the exposure to plant
(
operating personnel as a
result of the change; and j
1 8)
Documentation of the fact that the change was reviewed and found acceptable by the PRB.
(
b.
Shall become effective upon approval by the GMVNO.
There have been no major changes to the Liquid, Gaseous or Solid Radwaste Treatment Systems during this report period.
f l
0 i
O i
1 l
1 l
l 1
l r
O 57
\\
l
7.0 M{T{gRghggig3L ggIf
}
T.S.
6.8.1.4 states in part:
The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year.
This annual summary may be either in the form of. an hour-by-hour listing on magnetic tape of wind
- speed, wind direction, atmospheric stability, and precipitation (if measured),
or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.
The meteorological data is included in ATTACHMENT C.
e i
- ,;,e..
'l l
.1 s...
bas h,
Y a-ms.u..
Vi; s t.sn C G V 1
58 L
l l
i 8.0 INOPERAghg klQUID QR QAgg0ME
((PkMENT MONITQg1NG INSTRUMENTATION T.S.
6,8,1.4 states in part that:
The Semiannual Radioactive Effluent Release Reports shall also include the following:
an explanation as to why the inoperability of 11guld or gaseous effluent monitoring instrumentation was not corrected within the time specified in Specifications 3.3.3.10 or 3.3.3.11 respectively.
NOTE:
The specifications are actually 3.3.3.9 and 3.3.3.10 and a Technical Specification Change Request is being processed.
T.S.
3.3.3.9 states in part:
i The radioactive 11guld effluent monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE
)
Action b.
states:
With less than the minimum. number of radioactive 11guld
/%
effluent monitoring instrumentation channels operable.
()
take action shown in Table 3.3-9.
Restore the inoperable instrumentation to operable status within 30 days and if unsuccessful, explain in..the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.8.1.4 why-this inoperability was not corrected in a timely manner.
4 i
T.S.
3.3.3.10 states in part:
The.
radioactive gaseous effluent '
monitoring instrumentation channels shwon in-Table 3.3-10 shall be
~
/
nOPERABLE o
. u.- :
ma s _...,,,.
m e
e"
'*'* Action-b states:
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels i
- operable, take the action shown in Table 3.3-30.
Restore the inoperable instrumentation to operable status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to specification 6.8.1.4, why this inoperability was not corrected in a timely manner.
()
Inoperable Tech Spec monitors are tracked on Limiting Condition of Operation (LCO) Forms.
The operators declare 59
l l
1
{
equipment operable and inoperable and Monitors are
()
considered inoperable 'If there are open Lc0's for that
~}
monitor.
LCO 1-87-114 was written on 1/13/87 on Monitors RE-12442A and C.
It was closed on 1/15/87 after cleaning part of the instrument.
However, LCO 1-87-1311 was written on the same I
day 1/15/87 for RE-12442 A,B,4 C.
A Laboratory Standing Order (LSO) 87-3 was written to allow a different way to source check the detectors instead of using the solenoid actuated check source built into the skid.
This allowed RE-12442A&B to be declared operable on 1/16/87 by closing this LCO.
RE-12442C was still inoperable and LCO 1-87-146I was written on 1/16/87.
This LCO was not closed until 2/13/87.
The time between LCO 1-87-114 started on 1/13/87 and LCO 1-87-1461, which ended on 2/13/87, is 30 days.
RE-12442C was a monitor identified in all three of these LCO's and thus was included in this report.
MWO 1-87-00961 was written to correct the problem and work was delayed until parts could be obtained.
The work on the MWO was complete on 1/21/87 and the MWO was closed on 1/24/87.
There was an additional MWO started on 1/29/87 and it was finished on 1/31/87.
The MWO was closed on 2/9/87 and the LCO was closed on 2/13/87.
LCO 1-87-162 was written on 1/19/87 on FT-12442.
The 4-hour flow estimates were started and NWO 1-87-01146 was written.
fg The MWO was completed on 1/30/87, well within the 30 day
(_/
- limit, but the paperwork was not cleared up until 2/26/87, well after the 30 day limit.
LCO 1-87-155 was written on 1/18/87 on 1-RV-0018, FT-0018 and 1RE-0018.
The duplicate samples and valve lineups were done and MWO 1-87-01133 was written.
The MWO was finished on 1/20/87 after it was verified that the valve RV-0018 and the radiation monitor RE-0018 operated per design.
NWO 1-8 7 -013 3 9 -~ wa s written on 1/24/87 and the flow transmitter board was replaced on 1/30/87.
This completed the work on thole instruments also well within the 30 day time limit but the'papetwork was not closed out until 3/1/87, well after the l
c. QQ)nk himit,
a..e
.u :.. _. n
~
wr '
~< '
ueup JnSbh)7fl96 was written on 1/25/87 on ARX-0014 which made RE-0014 inoperable.
MWO A8700261 was issued on the sanne day.
This MWO was completed before 2/21/87 and replaced a computer board to get ARX-0014 communicating again.
In
- addition, MWO 1-87-02431 was written on 2/13/87 to check communications between the Data Processing Modules (DPM's) and the mini-computer.
This MWO was complete on 2/21/87 and the LCO was closed on 2/28/87 based on MWO 1-87-02431.
Here again the closing out of the paperwork is the main reason for exceeding the 30 day limit.
()
LCO 1-87-209 was written on 1/27/87 for monitor RE-12442A, B,&C and RE-12444 A.B,ac.
The mini-computer was declared 60
{
l
l l
l Anoperable and the Tech Spec Action Statements for grab l
sampling were initiated.
MWO 1-87-01447 was closed on
'()
2/9/87 after the primary calibrations were completed.
MWO 1-87-01824 was closed on 2/15/87 after replacing a
sample pump.
The computer was repaired and the monitors were back i
in operation on 2/15/87.
However, the paperwork for the LCO was not completed until 2/28/87.
LCO 1-87-210 was also written on 1-27-87 and closed on 2/28/87.
It was for monitors RE-12839A,B,&C. RE-0014, AFT-l 0014 and FT-12839.
The mini-computer was declared l
Inoperable and the Tech Spec Action Statements were initiated where applicable.
MWO 1-87-02098 for FT-12839 was completed 2/18/87.
NWO 1-87-02508 for 1RE-12839 was completed 2/19/87.
The computer was repaired and the monitors were ready.for operation by 2/19/87.
Here again the time between 2/19/87 and 2/28/87.was the time to properly process the paperwork to close the LCO.
i LCO 1-87-215 was written on 1/29/87 for RE-12839C because it failed its source check.
MWO 1-87-02506 was closed on 2/19/87 and the monitor was ready for operation at that time.
However, the time between 2/19/87 and 2/28/87 was the time spent to properly process the paperwork to close the l
LCO.
LCO 1-87-4371 was written on 3/31/87 for RE-12839D because
(~g it failed its source check.
This also made RE-12839A,B,& C
()
Anoperable.
MWO 1-87-03833 was already written on 3/13/87 1
and was completed on 4/1/87.
The detector tube for RE-12839D was replaced.
Once again, the proper processing of the paperwork took from 4/1/87 to 5/19/87.
1
- g.. m -
e.h. I m, we
..N,...
.mt
.DU w
d mm
'.0
. Jabt J_
s mm l
i l
l 61 1
1 l
8.0 IAHE! EXEEEE1EE EHE11 E9EIEEI klM1Is O1 T.S.
6.8.1.4 states in part:
The Semiannual-Radioactive Effluent Release Reports shall~'also include the following,
"...and description-of the events leading to liquid holdup tanks or gas
)
storage tanks exceeding the limits of specification
(
3.11.1.4 or 3.11.2.6, respectively.
I
-T.S.
3.11.1.4 The quantity of radioactive material contained in each outside temporary tank shall tne limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases.
Action A' states i
With the quantity of radioactive material in any of the outside temporary tanks exceeding the above
- limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank a
contents to within the limit, and describe the events
]
leading to this condition in the next Sealannual i
_O-Radioactive Effluent Release
- Report, pursuant to specification 6.8.1.4.
T.S.
3.11.2.6 I
The quantity of radioactivity contained in each gas' decay tank shall be limited to less than or equal to
{
2E5 Curies of noble gases (considered as Xe-133 equivalent).
Action A states:
0 v
With the quantity of radioactive material in any gas decay tank exceeding the above
- limit, immediately
_.-suspend -all ad'ditions of radioactive'aiterial to the n._ tank.
Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tanh contents to within the limit, and describe the~ebents leading to this condition in the next Sealannual Radioactive Efficent Release
- Report, pursuant to specification 6.8.1.4.
There were no outside temporary liquid tanks for radioactive liquids during this reporting period.
The radioactive material contained in each waste gas decay tank did not exceed 2E5 curies of noble gases (considered as Xe-133
()
equivalent).
62
J ui. 2 s ' e r e s 43 ee7 sa: su: oss
- .e2 ATTACHMENT A
i 1(7 - 0 1 1 UNITS 0 87ATss NUCLEAR REGULATORY COMMISSION 3
wasmh0 TON,0. C. 20006 Cocket hos.:
50-424 10 N E and 50 425 Mr. Janus P. O'Reilly Senior Vice President - Nuclear Goerations Georgia Power Company P. O. Box 4545 Atlanta, Georgia 30302
Dear Mr. O'Reilly:
Subject:
Staff Acceptance of Vogtle Units 1 and 2 Offsite Dose Calculation Manual The' staff has completed its review of the Vogtle Units 1 and 2 Offsite Dese Calculation Manual (00CM) submitted by letter dated December 9,1985, and supplemental submfttals dated hovember 18, 1986, December 16, 1986, and des t,
j uary 8, 1987. Pased on our review of these submittals and Georgia Power comoany's connitment to include the proposed changes in the December 16, 1986, O
and January 8,1987, letters into the next revision of the 00CM, we cerclude
\\
that the Vogtle Units 1 and 2 00CM is acceptable.
Sincerely, B.
ungblood, Director PWR Project Directorate #4 Division of PWR Licensing-A cc:
See next page a
suL 2,.or esi44 eer anc suc ops P.83 ATTACHMENT A i
[
UNITS 0 sfATes
\\
NUCLEAR REGULATORY COMMl88lON h(
h
{
wasmof ow, n. c. noses
\\.....
m a.7 c-Tl@IRYl{W{
i o*"*:n!!.1 1
.)UL 181987
.Mr. James P. 0*Re111y Senior Vice President - Nuclear Operations
-.P. UROLLY l
Georgia Power Company P. O. Box 4545 i
Atlanta, Georgia 30302
Dear Mr. C'Reilly:
i
Subject:
Staff Review of Vogtle Units 1 and 2 Offsite Dose Calculation Manual.
Revision 3 i
I 28, 1987 Georgia Power Company (GPC) submitted Revision 3 By letter dated April to the Vogtle Units 1 and 2 Offsite Oose Calculation Manual (00CM). The staff i
has reviewed this submittal to ensure that changes proposed and consitted to GPC letters dated December 16. 1986, and January 8,1987. have been incorgerated as requested in NRC letter dated January 13. 1987. Based on our review, wt l
conclude that GPC has satisfactorily included the required information. Most of i
O( /
the other minor changes in Revision 3 are also improvements. However in equa-l tiens 38 and 39, an upper. case sigma has been omitted prior to the "zk" subscript.
With this minor correct sn, we conclude that Revision 3 to the 00CM is acceptable.
GPC should initiate this correction to the 00CM is a timely menner.
Sincerely,
?!b Melante A. Miller, Project Manager Project Directorate 11-3 Division of Reactor Projects, I/II cc:
See next page
++
e O
g O
I d
4 M
i ATTACHMENT A PROCEDURE NO.
REVISION PAGE NO.
00402-C 3
11 Of 16
, /V i
LICENSING DOCUMENT CHANGE REQUEST LDCR No. XO[700 D 4.1 Originator
- 81 M
/
A
- 7 Priority Level 2--
~
Print Name Q
Date Affected Document: '
[)bf k Ispected Document (s):
Change:
hpft_'re DWM $ lit 0 & 5 brTii, 2.I.2 d t jalnde l
i % WtYal+ A H Y rEEn Wer.A. b tbet CalPn)nk i
Juaeification:
Y & Anu/Ed Y h &_EngJad$AffG & w awamu. C Ake7/n oben accA4 6 Alft v
(1) Constitutes'an Unreviewed Safety Question YESl I
NO M
~ (2) Constitutes a reduction in QA Program YESl l'
'NO k Commitment (3) Constitutes a change in Technical Specif1 cations YESI l'
NO NRC Approval'is Required prior to implementation if Ites 1, 2, or 3 is YES originating Dept. Head Approval
/<.3/2/
l Signature Date Concurrence:
4.2 LDCR Coordinator:
/
/ 7NSAC Mgr h 44 /b 7
l l
81gnature' daw
/ Signature Date 4.3 PRB Meeting No. PG-6 7-N PRB Chairman (/M CCM -
/ Fh// 7 Approval 4
W
/k7 i
Signature Date/
j Comments:
I i
1 4.4 Document Change Review:
Change: As Requested l l
Not As Requested W i
Follow-Up Action:
O Change Implemented: Document no. & Rev.
LDCR Coordinator
/
Signature
- Date EXAMPLE, FIGURE 1 OS
2
.. ~A ATTACHMENT A FRocEDUAE No.
ItEVISloN -
PAGE No.
q 00056-C.
3 15 of 16' I
SAFETY EVALUATION SHEET 1ofd Document ID'No, h 30M Rev.
_JP 3
!N I
SECTION 1.0 1j 1.1 D neription of proposed change, tept, or 1xperiment.
ad w />tZe.b AubsoiL A,t 2. l.1 thd added anox bAddA Aff' Ni &
kr k JL k enhvik %
I t
.1. 2 Rea on (or proposed change,. test, or experiment'*
u Mww aAe NNum G sush, 4 Obe/tt dend/S 2$ N2('
)
v.
v 1
5.3' Does the proposed change involve a. change to Technical j
Specifications?
Yes No //
Explanation:
A d # I m o d A l - w a r /o' A n l. / w 2,
/
1 n
~l
'V 1.4 Does~the proposed change involve a change in the facility as described in the FSAR?
Yes No X A]r p
, t $$ ' Y/h aookknbdtd1/u &
E on:'
i 1
1.5 Does the proposed change involve a change in procedures as described in the FSAR?
Yes No1 A}s ehe e,pendmn, eu. AmMlbwl w'Yb fSAP ion:
1.6 Does the proposed change involve a test or experiment not described in the FSAR?
Yes No1 i
Explana, tion
//e Ye7+ #fMMM MO td 3fs2.
G T A R d Ass +r b 4 ):
^
i Evaluator
[/t 2/m /
Date 7-2/-#2 3 k[
Supervisor h
Date FIGURE 1 kb m.n 1
- _ - _ _ _ _ _ _ ~ ~ ' ' ' ' - ' - - - -
/ # H'a.ek t-PROCEDURENO.
REYlSCN PAGE NO.
00402-C 3
11 of 16
.m
^
LICENSING DOCUMENT CHANGE REQUEST 0
- l LDCR No.
4.1 Originator
f hc'h
/ 7-MOPriority Level 2
Print Name Date Aff acted Document: OhC.M Impacted Documene(s):
I Change:
keutN O hC 1M fr AL0tB hstn) ar& /gm) WO v' /em s
I Justification:
/V f0 Ylh M k O M el Lut$ /M1AmiA N/0 Att &
\\
f
/
i (1) Constitutes an Unreviewed Safety Question YESl l
NO y (2) Constitutes a reduction in QA Prograa YESI l
NO y Commitment (3) Constitutes a change in Technical Specifications YESl i
NO @
NRC Approval is Required prior to implementation if Iten 1. 2, or 3 is YES i.
Originating Dept. Head Approval
/3/,2d((2 l
"$1gnsture
'Date
=
Concurrence:
/ 2,1/P'/
4.2 LDCR Coordinator: /
//
SAC Mgr 3
Signature' D at(e fignature Date 4.3 PRE Meeting No.[/26- /~7 -4 f PRB Chairman (/f-N %
/J L'7-fg i
s ///-f dignat te Date A
GMVNO Approval bbek/
/ 4/23 !3 Signa ture D4te /
Comments:
l j
l 4.4 Document Change Review:
(
l Change: As Requested l l
Not As Requested l l
{
Follow-Up Action:
l l
I l
Change Implemented: Document no. & Rev.
LDCR Coordinator fignature
~. - Date EXAMPLE, FIGURE 1 M
- -_------ -- _ -- _-- -_- i
~
a.'
(\\
n ATTACHMENT
-A ' ' f $i j
,7/
renoctoon uc 6 REW5&oN g
l PAGE NO (i
00056-C 3
Y 15 of 16 u --
. p, i
g g-SAFETY EVALUATION SHEET 1ofd Doctament ID No.
O Dt f4 -
Rev.
)
O</
SECTION 1.0
\\
k#
1.1 J
Deshriptiqn of proposed. change, j
test, or
.%wA f1/0) Vahus Du ddenna w@ experiment:
NRC
\\
y
_(!
t 1.2 Reason for proposed change, test, MPO di):md acwe or experiments-ull m ddouhh ad de& /deh 4u ww
\\
n & r n ',&5h s- % Nac
'n p e L M.
t I
.l '
j 4
\\
1.3 Specifications?Does the proposed change involve a change to Technica
/
Yes
' No /
H,< )'
Explanation:
Alg e s w Y) Db Gwc uE,/>qf AjJt ft ff),
i.
i
)
1.4 Does the posed change involve a change in the facility as descri e in the FSAR7 Yes No
~
Explanation:
}ln clYkst Z 26 lpabil 1uhm) s 1.5
\\
described in the FSAR7Does the p oposed change involve a cha Tes No /
Af s}se w w DA & l4vc QA dwS ol,
ations u
1.6 "ms the proposed change involve a tesc or experiment not described in the FSAR7 Yes
- No /
Explanation:
72e M2dwhlvd w fAa fl&w d 4+#4Me d/fr m ret /
ar.vAM
}'Wn s a u s.,r ir Url IIE r U K M B II H M H ER
~
Evaluator
[/I Mw/
-......,,,.w o man Date 2- /-O Supervisor Date _
/b l
FIGURE 1
~
09
ATTACHMENT A
g iI
~
1
)
OFFSITE DOSE CALCULATION MANUAL FOR GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT
~
REVISION 3 MARCH 1987 l
l U
G9
ATTACHMENT A 8.
Estimating Acquatic Dispersion of Effluents from Acci, dental and Routine Reactor Releases for the Purpose of Implementing,
Appendix I, U.
S. "RC Regulatory Guide 1.113, Rev. 1 (April 1977).
9.
Vogtle Nuclear Plant, Units 1 and 2,. Waste Water Effluent l
Discharge.eructure Plume Analysis; Georgia Power Company; April 1981.
10.
Direct communications with Water Resources Division; U.S.
Geological Survey; U.
S.
Department of Interior; February i
1985.
i 11.
Water' Resources Data, Georgia, Water Year 1983; U.
S.
~
Geological Survey, Water - Data Report GA-83-1; W.
R.
Stokes, III, T. W.
Hale, J.
L.
Pearman, and G.
R. Buell;
. June 1984.
()
12.
Vogtle Electric Generating Plant Land Use Survey - 1986; Georgia Power Company; April 1986.
13.
Letter:to Georgia Power Company from Pickard Lowe, and 2,3 Garrick, Inc.; Washingtor., D.C.; December 16, 1906.
14.
Kahn, Bernd, et. al; " Bioaccumulation of P-32 in Bluegill 2
and Cat fish"; FTUREG/CR-3981 (February 198 5).
15.
Sagendorf, et.al; "XOQDOQ: Computer Program for the 3
Meteorological Evaluation of Routine Effluent Releases at i
Nuclear Power Stations"; MUREG/CR-2919 (September 198 2).
I
?
I l
VEGP 00CM, REV 3 3/87 x
10
t l
l ATTACHMENT A
I 1
1 SECTION 2 CASCOU,5 EFFLUENTS l
l At Plant Vogtle there are five potential points where l
l radioactivity is released to the atmosphere in gaseous I
discharges.
These five potential release points are:
Unit 1 plant vent; Unit 2 plant vent; Unit 1 and Unit 2 turbine building vents,.which are not normal release pathways until a primary to secondary leak exists; and the radwaste solidification building vent.
The turbine building vent serves as the discharge point for the condenser air ejector and steam packing exhauster system.
The fuel handling building is common to both units; however ventilation from this area is through the Unit 1 plant vent.
Certain components of the Caseous Waste Processing System are shared between the two units and releases from this system are through the Unit 1 plant vent.
Containment building releases are through the respective plant vents.
Gaseous releases from the turbine building vents and the radwaste solidification building vent are considered to be ground-level releases.
Gaseous releases from the plant vents are considered to be mixed-mode releases as determined by the wake-split model.
(See NOTE in Subsection 2.1.1). All five release 3
points are considered to be continuous releases.
In the absence of confirmed primary to secondary leak (s), the turbine building vents are not release points.
l
-1 Gaseous effluent monitor setpoints are required only for noble gas monitors serving the five release points.
Methodology for calculating noble gas monitor setpoints is presented in Subsection 2.1.
Although setpoint calculations are not required for radiciodine and particulate monitors, the I
methodology for assuring the potential organ dose rates due to l
radiciodines, tritium, and particulate in gaseous releases from the site do not exceed the limits of Technical Specification i
3.ll.2.l(b) is presented in the NOTE in Subsection 2.2.1.2.
t ATTACHMENT A
j l
(57Q) the~ highest annual average relative
'=
)
concentration at the site boundary.
(h f desired, the annual average ~ relative concentra tier. at the site boundary for the particular release point-may be'used.)
The
]
release points addressed in this' Subsection are ground-level releases.
i 3
!(
6.83 x 10-5 sec/m in the ENE. sector.
i ~ !2.3
(?75) g
=
~!
K
=
i total body dose factor due to gamma emissions 3
from radionuclides 1 (mrem /yr per uCi/m ) from Table 2.1-1.
i q
'=
Qig rate of release of noble gas radionuclides i l
(uci/sec) from the vent release pathway under 4
consideration -(ground-level), 'which is the product of Xiy and F, where X y
iy is the
)
()
concentration of radionuclides 1
for the particular release and F is the maximum y
expected release flow rate for this release point.
(Xiy in uCi/ml and F in ml/sec.)
y 1
ss dose rate limit to the skin of the body of an l
'D
=
individual in an unrestricted area which is 3000 mrem / year.
R
=
relationship between monitor response and the s
dose rate to the skin for the conditions of i-the release under consideration.
m J - ( (57E} G [(L+1.1M)
R i
s/=
C i
i g
Qtg )
(4)
O VEGP ODCM, REV 3 3/87 2-5 1A
i ATTACHMENT A i
where (O
i
_,/
L skin dose factor due to beta emisg) ions from
=
i radionuclides 1 (mrem /yr per uC1/m from Table 2.1-1.
i
- 1..'
mrem skin dose per mrad air dose.
=
Mi air dose factor due to
=
gamma emigsions from radionuclides 1 (mrad /yr per uCi/m )
from Table 2.1-1.
i 2.1.2 Unit 1 Plant Vent and Unit 2 Plant Vent Monitors:
RE12442C (Unit 1) and 2RE1244 2C (Unit 2)
Gaseous releases from the plant vent (s) are regarded as mixed-mode releases in that under certain conditions of vent exit velocity and meteorological conditions, the plume will behave as an elevated release.
Under other conditions of vent exit
. velocity and meteorological conditions, the plume will behave as a ground-level release.
Using the - wake-split model, dispersion values have been calculated utilizing expected annual average
()
conditions. (See NOTE below).
However, since setpoints for plant vent monitors must l,
l be established to ensure that the limits of Technical Specification 3.11.2.1.a will not be exceeded at any point in time, the ground level dispersion value used in Subsection 2.1.1 1
is also used in the calculation of setpoints for plant vent monitors.
NOTE:
Default recirculation values are utilized for 3
determination of dispersion and deposition f actors for calculation of the offsite effect of gaseous effluents.
Ground-level release parameters are used for plant vent releases in the east and east-northeast sectors (sectors in which the cooling towers are located) to account for any potential cooling tower wake effects.
/C' VEGP 00CM, REV 3 3/87 2-6 13
t I
ATTACHMENT A
l l
r')
The setpoint calculation methodology presented i,n k/
Subsection 2.1.1 applies to these monitors with the exception j
that Qig must be replaced with Q m where Qin is defined as i
follows:
Qig rate of release of noble gas radionuclides 1
=
(uci/sec) from the plant vent release pathway under consideration (mixed-mode), which is the product of Xiy and F where X y,
iy is the concentration of radionuclides i for the particular release and F is the maximum y
expected release flow rate for this release point.
(Xty in uC1/ml and F in ml/sec.)
y 2.1.3 Gaseo'us Waste Processing System Discharge and Reactor Containment Purge Monitors:
ARE0014, RE-2565C (Unit 1) and 2RE-2 56 5C
(~
(Unit 2)
V]
The Gaseous Waste Processing System discharges to the Unit 1 plant vent, Unit 1 containment purge discharges to the Unit 1 plant vent, and Unit 2 centainmene purge discharges to the Unit 2 plant vent.
The plant vents are aquipped with continuous final effluent monitors as discussed in Subsection 2.1.2.
However, due to the potential significance of releases from these sources, the setpoint methodology is presented for the system effluent monitors also.
The system monitors have the control 1
logic to terminate the release at alarm trip point.
The final
~
monitors have no trip logic.
Sampling and analyses are completed and monitor setpoints determined prior to release.
These setpoints must take into account simultaneous release pathways; the combined allocation factors for contributing pathway monitors must not
(~N exceed the allocation factor for the final release pathway monitor to which they contribute.
ATTACHMENT A t
V Downstream monitors must also take into consideration th,e combinations of source terms for the particular release pathway.
i
- 2.1. 3.1.
Gaseous Waste Processing System Monitor:
ARE-0014 The Gaseous Waste Processing System discharges through the Unit 1 plant vent; therefore, the Gaseous Waste Processing System effluent. monitor is not the final monitor for releases from this system.
However, because of the significance of this release pathway and because the Unit 1 plant vent monitor
)
setpoint has to accommodate releases from the Gaseous Waste i
Processing System, and the trip logic is associated with this 3
monitor the set' oint methodology for this monitor is presented.
[
p j
The methodology presented in subsection 2.1.2 applies to this monitor with the following five exceptions:
Exception 1:
[
Kt" # t=C
((X/C)g i Ki gi)
(5) g Exception 2:
Cm monitor response of the Gaseous Waste
=
Processing System monitor for radionuclides concentrations to be discharged (sample taken and analyzed prior to discharge).
(See 1
Subsection 2.1.4 for further discussion of monitor response).
Exception 3:
)
qi rate of release of noble gas radionuclides i
=
k (uci/sec) from the Gaseous Waste Processing VEGP ODCM, REV 3 3/87 2-8 q '5
ATTACHMENT A 2.2
. (m GASEOUS EFFLUENT DOSE RATE AND DOSE CALCULATIONS.
1 l
2.2.1 Dose Rates at or beyond Site Boundary l
'2.2.1.1 Dose Rates Due to Noble Gases For the purpose of implementing Technical Specification 3.11. 2.1 (a), the dose rate'in areas at or beyond the site boundary due to noble gases shall be calculated as follows:
D
=
t total body dose rate at time of release (mrem /yr)
(X/Q)G ng i IOig'ng
/CI IO I
(14I
=
Mn i
im nm Ds = skin dose rate at time of release-(mrem /yr)
[ [ IL Eb (X/C)G ng i i + 1
- 1M ) IC ig)ng+[
=
I M nm i Ibi + 1'1M ) I0im)nm Ilb i
w Where'ng is the number of simultaneous ground-level vent releases and nm is the number of simultaneous mixed-mode vent releases.
Other terms were defined previously in Subsection 2.1.
)
The dose rate limits are site limits at any point in time; therefore, dose rates are summed over all gaseous releases occurring simultar2ously.
For Plant Vogtle, Unit 1 turbine building vent, Unit 2 turbine building vent, and radwaste solidification building vent are ground-level releases.
Unit 1 plant vent and Unit 2 plant vent are mixed-mode releases.
However, since the limits of Technical Specification 3.11.2.1 apply at any point in time, ground-level dispersion values are 2
used in lieu of mixed-mode values as discussed in subsection 2.1.2.
(See NOTE in Subsection 2.1. 2).
3 O
VEGP 00CM, REV 3 3/87 2-17 i
l
l'
[-
' ATTACHMENT A l
.m P
= K ' (BR) DF (17) gg gg and where 6
K' constant of unit conversion, 10 pC1/uci
=
breathing rate for child age group; 3700 SR
=
3 m /yr from Table 2.2-10 DFio =
inhalation pathway dose factor for child age group for organ o and radionuclides i, from Table 2.2-2)-
NOTE:
In order to assure that potential dose rates (pre-release) to an organ due to I-131, I-133, tritium, and particulate in simultaneous gaseous releases from the site do not exceed 1500 mrem /yr as
[
specified in Technical Specification 3.11. 2.1(b),
the potential organ dose rate D must be I1:ited o
as follows:
De f ( AG) (SF) 1500 mrem /yr
'18) where AG and SF are assigned the same values as were used in i
Subsection 2.1 for the gaseous discharge pathway under f
consideration.
To further ensure.that dose rate limits were not exceeded (post-release), dose rates from simultaneous I
releases should be summed, as shown in equation (16) above.
1 2.2.2 Air Doses and Doses to a Member of the Public at or beyond the Site Boundary I
I i
(See NOTE in Subsection 2.1.2).
3 i
'11 l
ATTACHitENT A
2.2.2.1 Air Doses at or beyond the Site Boundary' f
For the purpose of implementing Technica11 Specification
~
3.11.2.2, air doses in areas at or beyond the site boundary shall be determined as follows:
9,,,,
=
air dose due to gamma emissions from noble gas D
-radionuclides (mrad)
-8(f
'?
~
T
^
~
3.17 x 10 (X/Q)g yMg tg,+ (X/Q)g. L
=
Q MQ,,
(19)
L i where 3.17 x 10-8 the fraction.of.one year per one second
=
Q'i g cumulative release of noble gas radionuclides
=
i over the period of interest (uci) from the vent release (ground-level) under consideration.
him cumulative release of noble gas radionuclides a
i over the period of interest (uci) from the vent release (mixed-mode) under consideration.
-M i defined previously in Subsection 2.1.1
=
(X/Q)g defined previously in Subsection 2.1.1
=
6.83 x 10-5,,ej,3~in the ENE (X/Q)g l
=
sector
- 2 i
1 l Dbeta air dose due to beta emissions from noble gas
=
radionuclides (mrad).
-8f '( X /Q ) g yN gQgg, I
+[(X/Q)g[g I
~ -
=-3.17 x 10
~
N Q,
(20) 2 g
g VEGP ODCM, REV 3 3/87 2-20 i
"l%
ATTACHMENT A where Ni air dose factor due to beta emissions from
=
noble gas radionuclides 1 (mrad /yr per 3
-uci/m ),
from Table 2.1-1.
2.2.2.2 Dose to a Member of the Public at or beyond the Site Boundary Doses to a member of the public due to.I-131, I-133, tritium, and radioactive materials in particulate form, in gaseous releases, will be calculated for the purpose of implementing Technical Specification 3.11.2.3 as follows:
(NOTE:
The member of the public expected to receive the highest dose in the plant vicinity is referred to as the controlling (or
' critical) receptor.
The dose received depends on the location, age-group, and exposure pathways present.
For Plant Vogtle, the
( )
controlling receptor (s) for which doses must be calculated, and the. applicable exposure pathways,.are presented in Table 2.2-12.)
i Dj.
dose to an orgah j of an individual in age-
=
group a from radiciodines, tritium, and I
radionuclides in particulate form with half-lives greater than eight days (mrem).
~0 3.17 X 10 alpj INbP
$9
+NkP im)
(2l)
=
p}
R I
where i
3.17 x 10-8 fraction of one year per one second.
=
pi for all pathways and all isotopes 3
=
W6p pathway-dependent relative dispersion or
=
(
deposition at the location of the controlling VEGP ODCM, REV 3 3/87 2-21 14
ATTACHMENT A TABLE 2.2-12
?
CONTROLLING RECEPTOR (To support subsection 2.2.2.2)
)
The location and exposure pathways associated with the controlling receptors are determined during the annual land use Dispersion and deposition values were calculated based census.
. ib VEGP site meteorological data collected for the period February 1, 1984 through January 31, 1]S6.
2 i
1
\\
Sector:
USW Distance:
1.3 miles Age Group:
Child j
3 3
1 Dispersion:
(X/Q')gp = 9.490-6 sec/m (k/Q ') gy = 1. 0 70-6 sec/m
-2 Deposition:
(D/Q')gp= 6. 73E-9 m
( D/Q ' ) ggp = 2. 5 3 E-9 m '
3 Exposure pathways:
Inhalation, ground plane, and vegetation NOTE:
A milk cow was observed during the 1985 Land Use fs Survey.
The owner indicated that the cow was on an
(
irregular milking cycle, and is dry for long periods of time.
However, because of the potentially significant dose associated with this pathway, dose calculations must be performed during periods in which the cow is being milked for human consumption.
A garden is also present at this location.
Under certain conditions, the individual exposed to these pathways could become the controlling receptor.
The determining factor is likely to be the number of months the cow is milked in a year.
Calculated dose results should be compared to the receptor presented above to determine which is the controlling receptor.
Sector:
WNW Distance:
2.8 miles Age group:
Child 3
3 Dispersion:
(X/Q ') gp = 1. 3 6E-6 sec/m (X/Q ')gp = 1. 55E-7 sec/m Deposition:
(D7Q ') gp = 8. 40E-10 m (D/Q ') gp = 2. 64E-10 m
~
-2 Exposure pathways:
Inhalation, ground plane, vegetation, and milk cow i
't
)* Reference 12; Reference 13 i
I VEGP 00CM, REV 3 3/87 2-64 60
ATTACHf1ENT A TABLE 2 2-14 POTDiT* AL ' RECIPTOR LOCATIO!'S AIID' PATH G Y3 (To S uppot t S ubsection 2 2 2 3) i Distance i
S oc to r (tli le s) 3 P a th way* * *
-Ace Group fj N
tit'E 1
NE CIE E
ESE SE 33
,53 Vege ta tion C hild SSE 46' 74 Vege tat ion Child S
45 72 Vegetation / Meat Animal C hild SSW 47 76 Mea t Aninal Child 2.
SW 31 50 Meat An} mal Child NS W 13 21 V egetat ion Child W
42 68 Veg eta tien Child WtiW 23 37 V ege tat ion Child 2~8****
45 Vegeta tion /t? ilk Cow Child.
NW.
39 63 V ege tat ion C hild -
NGW a
i Savannah River Plant Property (closed to public) j No receptor identified wi/ thin five miles Inhalation and ground plane pathways are assumed at all j
locations where ingestion pa thways exist.
i A milk cow has been observed at this location.
- However, discussions with the owner revealed that she is on an irregular 2
milking cycle.
The pathway will exist during periods when the cow is being milked.
O' R ef e re nc e 12 VEGP 00CM REV 3 3/87 2-70 71
q
, ATTACHMENT A j.
l' TABLE'2.2-15 DISPERSION AND DEPOSITON PARAMETERS
.(To Support Subsection 2.2.2.3) l Distance Ground-Level Release Mixed-Mode Release i
Sector (Miles)
Km X/O sec/m3 D/Q m-2 X/O sec/m3 D/O m-2' j
N'
.NNE NE ENE
. E i
ESE SE-3.3 5 '. 3 6.80E-7' 6.15E-9 7.05E-8 1.58E-10 SSE 4.6 7.4 4.37E-7 2.15E-10 4.49E-8 8.26E-ll S
4.5 7.2 4.48E-7 2.88E-10 5.35E-8 1.12E-10 i
SSW 47 7.6 3.70E-7 2.32E-10 5.30E-8 1.56E-10 SW 3.1 50 1.53E-6 1.02E-9 2.19E-7 4.53E-10 WSW.
l3 2,1 9.49E-6 6.73E-9
- 1. 07 E-6 2.53E-9 W
4.2
~6 8 6.20E-7 3 36E-10 7.41E-8 1.38E-10 WNW 2.3 3.7 2.03E-6 1.27E-9 2.16E-7 3.80E-10 2.8 4.5 1.36E-6 8.40E-10 1.55E-7 2.64E-10 NW 3.9 63 7. 2 5E-7
'3.72E-10 7.99E-0 1.25E-10 NNW I
l I
i l
Savannah River Plant property (closed to public)
No receptor identified within five miles Reference 12; Reference 13.
g VEGP 00CN, REV 3 3/87 2-71 I-h1
Y l
ATTACH!1ENT. A 12.3 METEOROLOGICAL MODEL i
(Reference 7, 13,15 and Section 2.3.5 of Referen'ce.5)
<~
a 2.3.1 Atmospheric Dispersion i
Atmospheric dispersion (long-term)-may be calculated 1
using the appropriate form-of the sector-averaged straight line
. flow Gaussian model.
Gaseous releases are considered to be either ground-level ~or mixed-mode.
Considered as ground-level are. releases from the turbine building (s) vents and the radwaste I
solidification building vent.
Releases from reactor building (s)
I (plant) vent (s) are considered to be mixed-mode.
(See NOTE in Subsection 2.1.2).
3 2.3.1.1 Ground-Level Releases
~
(X/Q)g the ground-level sector-averaged relative
=
' concentration for a given wind direction 3
(sector) and distance. (sec/m )
[
n
=(RCF)2.032d (38) 3 p jk Nu 3
x g,zk i
H where i
(2/7f)bi divided by the number of radians in a 2.032
=
22.50 sector (0.3927 radians).
i dp plume depletion factor for all radionuclides l
=
other than noble gases at a distance-x shown in Figure 2.3-2 for ground-level releases; for noble gases the depletion factor is unit'y.
If an undepleted relative concentration is desired, the depletion factor is unity.
Only depletion by deposition is considered since depletion by decay would be of little
/
)
significance at the distances considered.
VEGP ODCM, REV 3 3/87 2-75 33 a-
ATTACHMEf4T A RCr open terrain recirculation factor.
Values for
=
-q specific distances are obtained from rig,ure
'Ams) 3.2 of Reference 15.
njk number of hours me teorological conditions are
{
=
observed to be in a given wind direction, windspeed class j, and stability class k.
!CTE:
If periodic data (hourly) are used instead of the joint frequency data, the summation over j and k is deleted and the summation is accomplished for all hours at all distances for each direction.
total hours of valid meteorological data N
=
throughout the period of interest.
~
ujk wind speed (mid-point of,windspeed class j) at
=
ground level (m/sec), during stability class k.
O distance from release point to location of x
=
interest (meters).
[szk=
the vertical standard deviation of the plume concentration distribution considsuing the
. initial dispersion within the bu'.1 ding wake.
(d$ + (b /'.K$)l/ 2 the lesser of or
=
E( %)
Cf zk =
the vertical standard deviation of the plume concentration distribution (meters) for a given distance and stability category k as shown in Figure 2.3-1.
The stability I
r-category is determined by the vertical
(~ T l
\\
j VEGP ODCM, REV 3 3/87 2-76 l
l sa i
i i
ATTACH!1ENT -A temperature gradient d.T/ dz (OC/100m).
7(=
'3.1416 maximum height of adjacent plant structure (55 b-
=
me ter s).
2.3.1.2 Mixed-Mode Releases (X/C)g the mixed-mode sector-averaged relative l
=
concentration for a given wind direction 4
3 (sector) and distance (sec/m )
1 I
i
[
"jk E
'3 i
- 2. 03 2 (RCF) d Nx
=
p jk ujk 2k 1
2
+
exp(-h 7
)
(39) j where dp plume depletion factor for all radionuclides
=
other than noble gases at a distance x shown in Figures 2.3-3 through 2.3-5 for elevated releases; for noble gases the depletion factor is unity.
If an undepleted relative concentration is desired, tha depletion factor is unity.
Only depletion by deposition is
(
considered since depletion by decay would be of little significance at the distances
(
considered.
Ujk wind speed extrapolated to the effective
=
release height; extrapolation is accomplished by raising the ratio of the two heights to the n power where n = 0.25, 0.33, and 0.5 for unstable, neutral, and stable conditions, respectively. (Re f erence 5, Section 2.3. 5).
f l
1 VEGP 00CM, REV 3 3/87 2-77 i
ATTACHMEtlT A 2.3.2 Relative Deposition (See NOTE in Subsection 2.1. 2).
3 2.3.2.1 Ground-Level Releases (D/C)c the ground-level sector-averaged relative
=
deposition at a given distance and for a given 2
sector (1/m ),
(RCF) {2.55D n
y k
k Nx (42).
3 i
where 2.55 =-
the inverse of the number of radians in a l
sector (277/16)-1 22.50 1
D
=
g deposition rate at a given distance, taken.
from Figure 2.3-6 for ground-level releases.
()
nk the number of hours the wind is directed into
=
the sector of intecest, during which time stability category k exists.
N
=
the total number of hours of valid meteorological data.
RCF open terrain recirculation factor.
Values for 3
=
specific distances are obtained from Figure 3.2 of Reference 15.
l
\\
l VEGP ODCM, REV 3 3/87 2-80 i
3b
ATTACliMEllT A 2.3.2.2 Mixed-!! ode Releases 1
i
(
)
(D/Q)g the mixed-mode sector-averaged relative-
=
deposition at a.given distance and for a given 2
sector (1/m ),
2.55 (RCF) ((E) (D ) + (1 - E) D,)
(43) 3-
=
x g
where i
relative deposition rate.for the ground-level i
D
=
g portion of mixed-mode releases from Figure l
2.3-6.
5 D,
relative deposition rate for the elevated
=
4 portion of mixed-mode releases from Figures 2.3-7 through 2.3-9.
fraction of releases considered as ground-E
=
level.
O.
Other terms were defined in previous Subsections.
I i
i l
l I
O VEGP ODCM, REV 3 3/87 2-81 21 iu_______________
ATTACHMENT B JUSTIFICATION FOR CHANGES TO SECTION 3.0 0F ODCM Page 3-2 I
Location 7: the distance to this location is corrected.
Location 12:
vegetation is now being sampled at this location.
Page 3-3 Location 30:
the TLD is being stolen regularly at its present location; it will be relocated nearby at the end of the second quarter to Nathaniel Howard Road in the same sector at 5.0 miles.
i Location 36:
this station is located at the GPC Waynesboro District Operating Headquarters which was moved recently to a new nearby location.
Locatis1 37:
with the deletion of location 38, the description deleted is redundant.
Location 38:
this location is deleted because it is not needed to satisfy technical specifications requirements and its proximity to Location 37 makes it redundant.
Location 80:
drinking water is sampled from the Augusta Water Treatment Plant not the North Augusta Water Treatment Plant; the distance is corrected accordingly; a table notation is referenced to describe where and how water is drawn from the Savannah River.
Locations 81 through 85:
the acronym RM for River Mile replaces mile in the descriptive location.
Location 81:
sample types R (river water) and S (sediment) are deleted since they are not required by the technical specifications at this location; a table notation is referenced for fish samples to clarify where they are q
collected.
j 1
Location 82:
sample type S (sediment) is deleted since it is not required by j
the technical specifications at this location.
{
l Location 84:
a table notation is referenced for sediment samples to clarify i
where they are collected.
{
Location 85:
the distance to this location is corrected; sample type R (river water) is deleted since it is not required by the technical specifications; a footnote is referenced for fish samples to clarify where they are collected.
Locations 87 and 88:
the distances to these locations are corrected; table notations are referenced to describe where and how water is drawn from the p
Savannah River.
'J Location 91:
this station is deleted since there is no longer a milking animal at this location.
18
-ATTACHMENT 8 Page 3-4 Table notations-#2 and #3 and replaced with Table Notations #2'through #6.
Page 3-6 4
Location 91 is deleted.
i Page 3-7 l
Location 38 is deleted.
j
.i Page 3-8 Upriver water is sampled at the Augusta Wai!er Treatment Plant not the North Augusta Water Treatment Plant.
t
/
4 i
O se
./-
TABLE 3.0-1 ATTACH!;EtlT 8 RADIOLOG.ICAL ENVIRONMENTAL SAMPLING LOCATIONS t.
LOCATION DESCRIPTIVE Os DIRECTION DISTANCE SAKp;E NUMBER -
LOCATION
_ (MILgs )
__7773 i
1 Hancock Landing Road N
1.1 D
i 2
River Bank NNE 0.8 0
1 3
Discharge Area NE 0.6 A
3 River Bank NE 0.7 D
4 River Bank ENE 0.8 D
i 5
River Bank E
1.0 D
6 Plant Wilson ESE 1.1 D
7 Simulator Building SE kr&- l,7 D,v,A L
'8 River Road SSE-1.1' D
9 River Road-S 1.1 0
10 Me t '.T ower SSW 0.8 A
I 10 River Road SSW l.1 D
11 River Road SW 1.2 0
2 iver Road WSW 1.1 DA WS V
- l. 3 L/
'L ve d
.O W
l.3 D~
1,/
14 River Road
^%
WNW 1.8 D
15 Harcock Landing Road NW l.5 D,V 16 Hancock Landing Road NMR 1.4 D,A 17 Savannah River Plant River Road N
5.4 D
1B Savannah River Plant D Area NNE 5.0 D
19 Savannah River Plint
{
Road A.13 1
NE 4.6 D
l 20 Savannah River Plant 1
i,}. Road A.13.1 ENE 4.8 D
21 5'avannah River Plant j
]
Road A.17 E
5.3 D
f 22 River Bank Downstream of I
Buxton Landing ESE 5.2 D
23 River Road SE 4.7 D
24 Chance Road SSE 4.9 D
3-2 40 1
___--_2-_____------
ATTACHMENT B TAB LE 3. 0-1 (Continued)
L RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS l
LOCATION DESCRIPTIVE DIRECTION DISTANCE SAMPLE
_ NUMBER _
LOCATION (MILES)
TYPE 25 Chance Road and Highway 23 S
5.2 0
26 Highway 23, mile 15.5 SSW 4.6 D
27 Highway 23, mile 17 SW 4.8 0
28 Claybon Road WSW 5.0 0
29 C axton-ively Road W
5.0 0
- .b$b..;rRoad 30 WNW
+rf-D
/$
Tl River Road'at Allen's Church Fork NW 5.0 0
32 River Bank NNW 4.8 D
33 Nearby Residence SE 3.3 0
34 Girard Elementary School SSE 6.3 D
35 Girard SSE 6.6 D,A 36 Waynesboro WSW
/494%.0 D,A
/4 37 Substation-(Waynesboro)
WSW 17.5 D,V (M0;th Sid; Of.";;d)
Sehetetion (Wey.. 5Lece)
Z%
17.5 D
S
(?:uth Side ef Reed) 43 Employees Recreation Area SW 2.2 0
80
-Ne;th Augusta Water gg Treatment Plant NNW 34,4 W(2) 81 Savannah River (
153.1)
N 2.2
--R,G, P (t.
Savannah River M 151.2) g 82 NNE 0.8 R WH-G+
Savannah River M 150.4) 83 ENE 0.8 R
Savannah River (db 149.5) 84 ESE 1.6 R,S( )
85 Savannah River 146.7)
ESE 5.0
%F(,b 87 Esaufort-Jasper Water Treat-g ment Plant; Beaufort, S.C.
SE 8+
W CO 88 Cherokee Hill Water Treatment 11 Plant; Port Wen twor th, Ga.
SSE et W Ol M --
C01;; r.:
'a 98 W. C. Dixon Dairy SE 9.8 M
99 Boyceland Dairy W
24.5 M
!,2 O
3-3 9l t
-_____________-___-_A
TABLE 3.0-1 (ContinNMJCHMENT B RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS TABLE NOTATION:
(1)
Sample Types l
A - Airborne Radioactivity D - Direct Radiation i
F - Fish M - Milk R - River Water S " River Shcrreline Sediment W - Drinking Water (at water treatment plant)
V - Vegetation m,s e.w...
,-- m 4
.s_
_i m.,._._. 4 m m.. _ m_ _
7-___.---
, 4. x, 3,__
. =
=
O '..
$ _[
[ ** ((
["
^
- * ^
eilee te ebte!= en adeq::t: fi:5 n.plc.
U f
(3)
These are apprerimate 1e::tiene fe: ::di=:nt :: piing.
"igh
= t= =y = = u = ==== = cu. = i= = m b1
- = um =
- dis:nt ::.p1in; t: b; =:= 11;b10.
i 8
ed s
'+:
+.;,
e l
A 3-4 9 e2.
ATTACHMENT B i
r
(
Table Notations (Continued) 2.
The intake for the Augusta Water Treatment Plant is located on the Augusta Canal.
The entrance to this canal is at River Mile (RM) 207 on the Savannah River.
The canal effectively parallels the river.
The intake to the pumping station is 3.6 miles down the canal and only a tenth of a mile across a narrow neck of land to the river bank.
3.
About a five mile stretch of the river is generally-needed to obtain adequate fish samples.
Samples are normally gathered between RM 153 and l
158 for upriver collections and between RM 144 and 149.4 for downriver collections.
4 4.
Sediment is collected at locations with existing or potential recreational j
value.
Because high water, shifting of the river bottom or other reasons
)
could cause a suitable location for sediment collection to become unavailable or unsuitable, a stretch of the river between RM 148.5 and 150.5 which is downriver of the discharge is assigned for sediment
]
collections.
In practice, collections are normally made at RM 150.2.
1 l
5.
The intake for the Beaufort-Jasper Water Treatment Plant is located at the
)
end of a canal which begins at RM 39.3 on the Savannah River. This intake is about 16 miles by line of sight down the canal from its beginning on the Savannah River.
I 6
The intake for the Cherokee Hill Water Treatment Plant is located on
/
Abercorn Creek which is about one and a quarter creek miles from its mouth on the Savannah River at RM 29.
l l
4 i
i OV l
93
ATTACHMENT B j
FIGURE 3.0-2 Terrestrial Stations beyond Site Boundary out to Approximately T'"- Miles and Aquatic Stations p
'\\,
~
q'd 44-g/,,4-s s.. -
g..
s n g,i,
,g s...-
{
e L
i s'
/h t
W.
/
adlLES
. Y.
/
7s
'h
\\
\\/y*
f
~
. eu. -
r?
)
.. f.W' &@ d ',
k..gf
.ks.
1 s,
~
l
(
0
.. ' ~
0 i
c
' n*
. ;;.,....; g ~ n g g,, s m.
2 rR
- t. f g,
s
& S ' at l
~.... s e s*> t.W
- s. a s. j f ~ /,,,3
.\\
4*
<g s' N g.,
'".' #. /
33
- TA.
e, i.
(
' a g,
)
j p.,
a
% i,, k Y
@'X$ "y~b g % r l
~.,s
- 9.y'J
\\
W.,f
. /.,-
t%
a:
v.z:...,...
x.,
\\
,u........
/1 O ";~'"y,,id' Ad e
C/:
M
,s.i d.. [. 4.
..,/
7 %
~
' '~ "N' 3-6
)
i i
a
y C
ATTACHMENT B 1
1 TIGURE 3.0-3 a
Terrestrial Stations beyond Five Miles 1
s we a.
./
.a ey Grea't**ille 278 North
/
vouets 25 MILE RAOlus i '
COLUMalcCD, y
,s="=<****
is AIKEN 7'
a y'AU A
278 e
f f
- * =, = '
l Ellenton 78 o %.
278 e
2,, /
.a
,R ICR i.
l.
NO CO.
/
s
,/
Blackvisse o.e,..
e S8'M c
Jackson River,Pfet j 278 t
F
. S.
se j
,/
8ARNWELL CO.
l
/
,/
l
,~
2s i.,,,,
g-
/ v.s.oov' *asa Barnwell
/ cuono,o.veve s
(
V s'
e 27
\\
f
,p 4 l
8 E CO.
SITE si l,
37,
.~
~
i.
{
a I
a aaaa=
?'
~
a
, j A8 88 i
i.
i,
/
6"**
t LLENOAL e
i
.i Q
j 2.
/ 2
~~
l*
/
x1
- "'** o I
i, s
W E)3
/ ' " g
,,,,, / is g
E
(,/
Millen
/,
6 JENKINS d*
--SCREVEN CO.
3 321
, /,,,/
g Y
bn W*ense E4till
- ====*a a g
/
i
- 2:
HAMPTON CO-t one.
(3 c.a.aea
'aaa f
\\
if sa.ae, s
.s
.(-
O.
3-7 45 o_
i ATTACHMENT B i
FIGURE 3.0-4 Driftking Water Stations g *esme aucust4 (80) "'7 8 " '" f"'"T *"7 lh, savat.Naw SOUTH CAROLINA maven j
PLANY l
VEcP W N
j Canal to $ wooly Rivec
~I W ter to Seeufort i
i
, y l
Seeufort. Jasper County
- ter Treatment Plant I
l gi"^uk{Ob croncia l
1 I
'S 0
s f
l e
ia--' =
s.
CMEmoWitwlLL WAffaimeATMENT y
4 1
4, p PkANT toont ws wrwon twi 4
G savaN=4
?
O O
3-8 1
1 i
ATTACHMENT B SECTION 5.0 (9
POTENTIAL DOSES TO MEMBERS OF THE PUBLIC V
DUE TO THEIR ACTIVITIES INSIDE TEE SITE BOUNDARY
~
For the purpose of implementing Technical Specification 6.8.1.4, an assessment of poten tial doses to MEMBERS' OF THE
~
PUBLIC due to their activities within the SITE BOUNDARY will be performed if circumstances have changed such that any of the limits of Technical Specit1 cations 3.11.2.2 or 3.11.2.3 are ex c,eed ed..The locations of interest within the SITE BOUNDARY at Plant Vogtle are the Visitors Center and Plant Wilson.
(Plant Wilson is owned and operated by Georgia Power Company, but f
individuals working at Plant Wilson are not directly associated with Plant Vogtle.
Therefore, those individuals are considered in this dose determination as a precautionary measure.)
The annual average atmospheric dispersion and deposition values for these two locations and the expected occupancy factors, by an individual during the, year, are as follows:
3 Location X/O(sec/m )
D/O (m-2 )
Estimated Occupancy Factor (by l.olf-4 7,o66 -p an individual during a year)
Visitors Center 2.50"-5 1.7CE 0.00046 (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
Plant Wilson 0.07E 5 2.90E 0.228 (2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />) j I
%H,E4 IS')& 4 i
In the event that any limit of Technical Specification
{
3.11.2.2 is exceeded, an assessment will be performed considering
{
direct radiation dose to an individual resulting from submersion in the plwne.
This assessment will take into consideration the annual average dispersion parameters and the estimated occupancy factor stated ~above, or a more precise value if available, for i
the locations of interest.
In the event that any limit of Technical Specification 3.11.2.3 is exceeded, an assessment will be performed considering the dose to an individual due to inhalation of airborne radioactive materials suspended in the plume and due to direct l
5 - 1.
41 L____-_-_-
~
ATTACHMENT B radiation from radioactive materials deposited on the ground.
This assessment will take into consideration the annual average dispersion and deposition parameters and the estimated occupancy factors stated above, or a more precise value if available for '
the location of interest.
If none of the limits discussed above is exceeded, potential annual doses to an individual at the Visitors Center are not expected to exceed N mrem to an organ due to If inhalation and ground-plane or 0.004 mrem to the total body due to direct radiation from the plume.
Likewise, potential q es to an individual at Plant Wilson are not expected to exceed 0
g a
mrem to an organ due to inhalation and ground plane or mrem to the total body due to direct radiation from the plume.
{
These values are based on annual average dispersion and i
deposition parameters and the estimated -occupancy 2 actors stated above.
The occupancy factor for the visitors Center is based on anticipated usage; the occupancy factor for Plant Wilson is based on a standard forty hour work week, assuming that an individual is assigned to the facility for the entire year.
I l
1 i
l l
O
)
l 5-2 j
. O 8
fo 1
D N
A D
m E
0 E
P 0 _
L _ 893O1 1 OO02S1 81 52 1
_6 S
6 _
A _
1 1
6 _
0 T _
T _
D 6 N
D _
O _
N E
O T _
IW R
. I E _
U
. T S _
4 _ 000O00OO00000000 _ 0 _
F T
. C P _
2 _
A O
7 R 8 E
A _
S E 9 R
L _
P E
1 I
M L
D B E R M_
T 4 _ 000O00OO00000000 _ 0 _
O
)A.A ET D
0 2 _
R N
1 _
T A A
R _
9 _
L U N
Q I _
1 C
E D
E D
D _
U T
E4 8 _ 71 0O00OO000441 20 _ 9 _
S Q
S E2 N _
)
1 _
_ 1 _
V R E
P1 O _ H R
I F mF S3 I _
P 3 _
0 T_U 3
1 _
1 T
D0 C
N N
N7 E _ D 2 _ 962O1 1 OO01 341 020 _ 0 _
IO O I8 R _ E 1 _
_ 3 _
I J
U ZI _ E T
DD__ P 8 _
_ 0 C
1 E
H8/
S
.R 2
C1 T I
A0DM_N
_ D 7 _ 21 1 OOOOO01 23301 2_ 6 _
E D E1 0
1 _
L B
0 1 _ I 4 _
O A
T7 D _ U T
A8 P _
)
AS_
_ S S
3 _ O1 OOOOOO 00000000 _
1 _ R R
i _
_ U D_
U eE _
1 _
_ OND E
O=
_ HO H
P
_ ( I D ; S __
_ MT R S'
_ LCI OS
_ AES CA
_ CRS EL I
RC
_ FDM
_ O FYN _
N _
E OTO _
O _
_ SLO II _
DI _
_ DB DLT_
NT _
_ A _ IIR I B V __
UE _
E E
E E
U U
U U_T
_ RRU O
RAE R _
NEN SES SUS NUN O _ EAO ETL _
I _ NNNEEESSSSSUUUNN _ T _ PVH PSE _
D _
8 fo 2
7 0
2 1
7 8
0 -
L _ 33304OOO31 634434 -
1
/
6 -
A _
1
- 5 1
T -
T -
N D -
O -
1
/
O T -
8 I
E -
0 T
S -
4 - 00000OOO00000000 0
)
C P -
2 _
d e
E A -
u R
L -
n I
i D
t M-4 - 00000OOO00000000 - 0 n
o D
0 -
2 -
c N
1 -
(
A R -
9 -
I -
1 -
2 D
D -
E E4 8 - 200O0OOO002281 02 - 7 L
Ed N-)
1 _
B
- 1 A
P?
O - H T
S3 I - P 3
3 TM 1
D0 C-(
N7 E - D 2-O1 OOO1 021 5231 - 9 1 1 1 I8 R - E 1 -
- 1 U
ZI - E DD - P 8 -
1 0
H8/
- S C1 T A0DM D
7 - O22O3OOO1 1 1 01 1 01 - 3 E1 0 - N
- 1 0
1 - I 4 -
O T7 D-W A8 P -
BS -
5 S
S 3 _ OOOOOOOO1 01 00000 - 2 R
R D-b U
wE-1 -
O=
bND HO H
Da kIG R
EL CRS L
RC II FDM T
b G
FYN -
N -
EF 0
OTO -
O -
V II -
DI -
SLO bB DLT-NT -
- L BAS OIA -
IC -
- A IIR E
IBV-UE -
E E
E E
U U
U UT bRU T
RAE -
R -
NEN SES SUS NUN - O EAO I
ETL -
I -
NNNEEESSSSSUUUNN - T PVH S
PSE -
D -
O 8
fo 3
7 0
2 1
7 8
0 _
L _ 8233O1 O23671 7852 _ 8 _
/
6 _
A _
1
_ 6 _
1 T _
T _
D __
1 N
O _
/
O T _
E_
8 I
0 T
S_
4 _ 0000O0O000000000_ 0 _
C P
2 _
)
d E
A _
e R
L _
u I
n D
i c.
M_
4 _ 0000O0O000000000 _ 0 _
O (t
D 0_
2_
N 1
A R_
9 _
I 1 _
2 D
D _
E4 8_
21 00O1 O000351 01 0 _ 4 _
E E2 N _
)
1 _
_ 1 _
L B
P1 O __ H A
S3 I
P 3 _
T_(M T
3 1 _
D0 C
N7 E _ D 2_
OOO022255320__
_ 1 1 1 1 5 _
I8 R _ E 1
2 _
U ZI _ E DD _ P 8 _
_ 0 1
H0/
_ S C1 T A0DM_D 7 _ 3O22OOO01 321 1 521 _ 3 _
E1 0
N
_ 2 _
0 1
_ I 4 _
0 T7 D _ U A8 P _
)
CS _
_ S S
3 _ 2OOOOOO201 000001 _ 6 _ R R
D_
_ U U
1 _
_ OND O=
.E_
_ HO
< P __
H
_ ( IG D 2$,
_ MTN R S?
_ LCI OS
_ AES CA
_ CRS E
EL II L
RC
_ FDM T
_ O G
FYN _
N _
EF O
OTO _
O _
_ SLO U
II _
DI _
_ DB D L T __
NT _
_ A _ IIR I B V __
UE _
E E
E E
U U
U E
_O U_O
_ T _ RRU T
RAE R _
NEN SES SUS NUN
_ EAO I
ETL _
D_NNNEEESSSSSUUUNN T_
I _
_ PVH S
PSE _
2
- b
11 !
O 8
f o
4 7
0 2
1 7
8 0 _
L_ 065254629958441 3 _ 3 _
/
6 _
A 7281 521 122348347__7 T_
T -
1 1 1 1
9_
1 N
D_
O-T-
/
O 8
I E_
0 T
S 4 - 0000000000000000 0_
C P -
2-
)
A d
E A_
eu R
L n
I D
i t
M_
4 - 0001000000000010 -
O (c.
2_
2_
i D
0 o
N 1 _
A R_
9 -
I -
1 _
2 D
D-8_4029200000293211 5_
E E4 L
E2 N_H
)
1 231 2
1 B
P1 O
1 _
AT S3 T_P 3_
I C_M 3
1 D0
(
N7 E - D 2
7621 1 44458677703 _ 2_
I8 R
_E 1 - 269521 1 1 1 3 13_2_
U ZI E
_ 4 _
DD_P 8-
_ 0 1
H8/
S 9
C1 T 4
A0DM_D 7_387649072941 2944 _
9_
E1 0
N
- - 33532 1
2 1221 23 7
0 1
I 4 _
3_
O T7 D_U A8 P -
)
D S __
_ S A
S 3
624581 21 2231
_ 5 _ R T
t, E _-
26S5_5_OND R
D
_ U A
U 1 _
O=
.t-
_ HO D pS _
PL
_(
IG H
_MTN RS LCI OS
_ AES CA
_ CRS E
EL II L
RC
_ FDM T
_ O G
FYN-N_
EF 0
OTO -
O
_ SLO V
II _
DI _
_ DB DLT-NT-
_ L_OAS OIR-IC -
AT_IIR E
IBU -
UE -
E E
E E
U U
u U_O__EAO RRU O
T RAE _
R -
NEN SES SUS UN ti I
ETL _
D _- NNNEEESSSSSUULNN I
T_PUH S
PSE -
)CN
[ LLlt l
Il
llI
!l i
~
~
O 8
fo 5
7 0
2 1
7 8
0 _
L __ 9993866501 224260 _2_
/
6 _
A 2
1 T_
T_236442322246831 1
1 N
D_
O_
_6
/
O T_
0 T
E_
8 I
S_
4 _
P_
2 __ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 _ 0 _
C
)
A d
E A_
e R
L u
I n
D oi M_
2__0000000000000000_0_
t 4 _
n D
0_
o N
1 c
A R _
9_
(
I _
1 2
D D_
. 001 E
E4 8_022501 0003600_0_
L E2 N_H
)
__2_
1 B
P1 O_P A
S3 I
3_
T T_M 3
1 D0 C
(
_ 3 _
N7 E_D 2_2246466364003025_9_
I8 R
E 1
122 1341 U
ZI _ E
_ P 8_
_1 H8/1DD_S
__0 9
C1 T 4
A0DM_N
_ D 7_113231
_ 636536631 3904104 _
0_
E1 0
21 11 233111 _
3 0
1
__I 4 _
0 T7 D_U 3_
A8 P
)
E S __
_S A
S 3_12771 34924324541 _
T 9_R R
D_
1
_ 6 U
A 3E_
1 _
_ OND UO=
t
_ HO D c # __
r
=
H
_ ( IG S_
_ MTN R S'
_ LCI OS
_ AES CA
__CRS E
EL II L
RC
_FDM T
O G
FYN_
N_
EF U
O T O __
O_
D
_ SLO II DI
_ DB DLT_
NT_
L_IIR
_ OAS OIA IC_
A IBV_
U E __
E E
E E
E U
U U
U_O_EAO
_ T_RRU o
RAE_
T R
NEN SES SUS NUN I
ETL D_NNNEEESSSSSUUUNN_T__PVH I _
S PSE_
Ob ILl l
ll
I
.\\l
~
O'
~-
8 fo
. 6
=
~
~
~
7
=
0 2
=
1 7
8 0_
L _444366?338338501 _8 _
/
6_
A 1
121221 1 1
_8 T_
T _
1 _
1 1
M D_
O_
=-
T_
/
?
8 E_
=
2_0000000000000000_0_
0 T
S 4 _
)
d C
P _
. ~
e E
A_
=
u R
L_
n I
i t
D n
M_
4 _
Qt 0000000000000000_ 0_
m D
0 _
2_
N 1 _
A R_
9_
+
2 I -
1 D
D_
E E4 8_0000000000000000_0_
L N __
)
B E2 1 _
A P1 H
O_P T
S3 I
3 _
3 T_M 1 _
D0 C_D
(
N7 E
2_ 0250000020030000_12_
I8 R _ E 1 _
U ZI _ E 8_
_ 0 D D __ P 1
H8/
S 9
C1T 4
A 0 D M __ D 7_3283545984954489_40_
m E1 0
N 1 1 1 1 1 0
1 _ I 4 _
8 T7 D_U
_1 _ :
A8 P
)
FS_
_ S A
S
_ 1 O1 O1 22434454122_6 _ R T
3_
R D_
_ 3
__U A
- e. (.
U OND 1 _
O=
_HO H
-a
( IG D
_ MTN R
__LCI OS AES CA
_CRS E
EL II L
RC
_ FDM e
T
_ O FYN_
G N _
EF OTO O _
_ SLO OU II _
DI _
_ DB DLT_
NT_
_ L _ OAS O I A __
_ A _
IBV_
UE _
E E
E E
U U
U U_T_IIR E
RRU O
T RAE_
R _
NEN SES SUS NUN _
O __ EAO I
ETL I _
D_NNNEEESSSSSUUUNN_T_PUH S
PSE _
$t (l
,1!fL i!
2 1
l l
-1
..O 1
\\
^1 1
-co i
1 so~
l N,
d N
i l
i I
I.
I N
I I
I l.
l l
r.
I I
'l
.j 00
@ l
'I I 'T v v r7) Lh LD CD fr) Ch - @ N Ch N @ m I (9 i N '
HI HI I e I i
@ l ei fu e w
,- v-I Lta - l '
ee E
c.. I O I I
I N
o I
F-1 I
i 00-M WI I
I H
t/)'I' v i (D (D (D CD (D (D CD (D (D (D G @ @ (D C C i @ l l
V AI NI i
I m
.c w
.CI AI I
I 47 g
Jl l
1 3
H I
i l
.3 Q
l 1
4 li1
~-
a EI
.T I @ @ @ (D 5) @ (D (D G @ W CD G G CD G I @_i 4
p O
@ l fu I I
I 3
.g w I i 1
'1.
t
'\\
S C
gi Ch I i-I:
H I g-1 I
I t
N O
Ql l
i Wv
- I C0 i @ @ @ (D @ (D G (D (D C @ @ @ @ @ @ l- @ 1 d
WN El a e l i
i a'j m
CL e-QI Z l I I
i u) m H I L
'm 1 I
i
>=
m HI E v-1 I
I C (D Uiw I
I EN-W8 O CU.
1 v-CD G (D (D (D C (D C (D v-tlD (9 @ @ @ l N. I H 00 2l W v I i
i t
3, INH I W l I I
i 1
-ocI CL 00 1
I @
Z@H N
I t/)
i I
Ch V,=
I I
I T
C CD C E I C N4 v - e 0= Cr) e v 00 N W N N Q Q t.D m i N I We CD I E I I e-v-
- - I @ l w-1 H T I I
e-I C
HN Ql 3 I
I *=
1 C 00 CL i e
i ^
a.
C t/) l I
I (/)
C m
- I ff) I e (9 m N N v e la N LD m to m e-T C I Ch i E H
E Ql 6
't iviO C
C 1
- = I l
1 QEQ oe I
I i Zo I
I I
I wHc Q **
I I
I EHE gW t
i I
juH Om I
i I Cwm UC 1
I I U 2 (M W
WJ l
i I
HH EV l
i 1 kQE l
- I i
1 C3 l
C LA.
EI
'EI I
I Wk j
C C
OI C l I
i ff) I o 1
D HH I CH I I
i o co i
OJHI
'E H I I
Jl O C (/)
i M co 3 i -
HU1 I cI HHg l
- w i
swi w
w w
w 3
3 3
3iHiuma H
EcwI 2 i
'. y rwr mwm m3m oI w er e rrrwwwmmmmm333"3rI H
WHJ l H I rriH i o. 5 I U)
CL t/) W l
.OI I
I LE-.___-_.____-.__-_.___
O 8
f o
8 7
0 2
1 7
8 0 -
L _ 871 09395784041 05 - 1 _
/
6 _
A _ 38871 66689372992 T -
T _ 1 1 21 1 1 1 1
2 1 -
1 N
D -
O _
1 /
O T -
8 I
E -
d 0
T S -
4 - 0000000000000000 _
)
e C
P -
2 -
0_
u E
A -
n R
L -
i t
I n
D M_
4 - 0001 00000000001 0 Oi D
0 -
2 -
N 1
2 A
R -
9 -
I -
1 E
D D -
L B
E4 8 - 544422001 0709043 - 5 _
A E2 N-1
_ 1 232 231
- 8 _
T P1 O -
1 -
S3 I -
3 -
T _-
3 1 -
D0 C
N7 E -
2 - 1 85871 0765401 299 - 3 I8 R -
1
- 5925221 1 236921 3 _ 0 _
U ZI -
1
- 7 _
DD _
8 -
1
_ 0 H8/
C1 T R0DM-7 _
1 773805707971 61 4 E1 0 -
- - 6507634365778457 _
0 -
0 1
4 -
1 0 -
O T7LD -
1 A8LP -
)
AS -
_ S S
3 -
1 8542041 06433359 R R
D _
- - 1 1 1 21 1 21 1 1 1 1 1 1 1
- U U
.E-1 - OND O =
_ HO H
( IG D
- MTN RS'
- LCI OS
- AES CA
- CRS E
EL II L
RC
_ FDM T
_ O G
FYN -
N -
E O
OTO -
O -
_ SLO U
II _
DI -
- DB DLT-NT -
- L _ OA OIR -
IC -
- A IIR E
IBU-UE -
E E
E E
U U
U UT _ RRU O
T RAE -
R -
NEN SES SUS NUN I
ETL -
I _ NNNEEESSSSSUUUNN _
O _ EAO T _ PVH S
PSE _
D -
_C
(
8 fo 1
D N
A D
m E
0 E
1 P
0 -
L -
1 897047S47593622 9 -
S 6 -
A -
1 1
1 1 1 43331 1 2 0 D 6 T-T - N N
D -
D -
E T-O IW R
_U I
E _
F T T
S -
4 - 0000000000000000 O A7 C
P -
2 -
R8 E
A -
E9 S
R L -
P1 E
L M I
ER D
BA TE M-4 - 0000000000000000 T T
AR D
0-2 -
TA N
1 YC LU A
R -
9 -
N EQ I _
1 -
D EU D
D D -
SN E4 8 - 01 000000071 1 8200 QE VO E2 N _
)
1
- R C
mE P8 O _ H F0S S3 I -
3 -
TF T
6 P
1 -
1 N
D0 C -
(
N N7 E - D 2 - 6301 01 3431 491 733 IO O I8 R _ E 1 -
1 1 1
1 I J
T U
ZI - E C
DD P
8 -
- 0 1
E
.R H8/
- S 3
C1 T I
E D A0DM D
7 - 4376922908993679 L E4 0 - N 1
1 21 21 B 0
1
- I 4 - O A
T7 D _ U T
A8 P -
)
AS -
- S S
3 - 1 1 2O1 1 221 1 1 01 1 20 R R
D-
- - U U
E -
1 -
- OND O=
E-
- HO H
P_
( I D:S-
- MT RS
- LCI OS
- AES CA
- CRS EL I
RC
- FD
- O FYN -
N -
E OTO _
O -
- SLO II -
DI -
- DB DLT -
NT -
- L - OAS OIA -
IC -
- A - IIR IBV_
UE -
E E
E E
U U
u UT - RRU RAE R -
NEN SES SUS UN - O - EAO i
ETL _
I - NNNEEESSSSSUUIJ NN - T PV PSE -
D -
O
D.'
8 fo 2
2 5
2 1
7 8
0 _
L - 33F38491 80540S1 8 __ 7 _
/
6 _
A _
1
. 31 1 1 4 _
T_
.T
_ 1 _
1 1
N D
O _
T_
/
O E __
8 I
4 _ 000000G800000O00 _
0_
0 T
S_
C P
2 _
E A _
)
d R
L _
e I
u D
Oi n
N_
4 _0000000000000O00 0 __
0 2
t D
1 n
N 1
o A
R _
9 _
c I _
1 _
(
D D _
3 E4 8 _ 0000001 001 001 081 _ 4 _
E2 N _
)
1 E
L P0 O_H B
S3 T_P 3 __
I _
A 6
_ M 1
C
(
T D0 N7 E _ D 2 _ 1 I8 R _ E 1 _ ' 001 22412?41 31 05 _ 4 _
_ 3 _
U ZI _ E 1 DD _ P 8 _
_ 0 H8/
_ S C1 T A0DM_D 7 __ 235252496899641 2 _ 7 _
E4 0 _ N 1
1
_ 9 _
0 1
_ I 4 _
0 T7 D _ W A8 P _
)
BS _
_ S S
3 _ OOOO1 OO104240000 _ 2 _ R" R
D __
_ 1 _ U U
E 1 _
_ OND O=
E_
_ HO H
P_
_ ( I D;S_
_MTN RS
_ LCI OS
_ AES CA
_ CRS E
EL I
L RC
_ FD T
_ O G
FYN _
N _
E 0
OTO _
O _
_ SL0 V
II _
DI _
_ DB DLT_
NT_
_ A _ IIR
_ L _ OAS OIA _
IC IBV_
UE _
E E
E E
U U
u U_T _ RRU E
O T
RAE R _
NEN SES SUS iUN _
T_EA O _
J I
ETL _
I _ NNNEEESSSSSUU( NN _
PU G
PSE _
D _
' gT
R 1
l.'
L 1
.m-i t.o-i I
m
.s.
i I
N I
i U.).
1 I
I I
N.
I I
l 1
I I
i i
i N
I L
l-
'00
@ l Jl Q Q m N N N N M N C0 v Lo 00 N N N I T I N
(.0 i C 3 N v-v-g - *-
w-1 (.D I
,=
HI HI i,- I r
Ql O I I
I N
O
.. I Hl i
1 00 H
Wi i
i H
U) I v i @ C (D G G G G @ C @ @ @ @ @ CD @ l @ l v,
n, 1 N
l.
I i
t W.
GI A I l
I 2
Ii I
I 1
I
.c Q
l I
I E#
v i (D @ (D G) @ CD CD G) G G) @ @ (D C (D (D i C 3
.C' o
CD I nj i i
I 3
.I
- t i I I
I c
Ei Ch i I
i H I
--8 I
I
'M Q
Ql 1
1 w
Wv
.. 1
,00 e CD (D @ @ @ @ C (D *- (D @ G) (D G) (D I NI I
a WN rin i
I i
CO CL C CI Z l i I
i 1
- C U) (v)
H I CL (Y) I I
I H'
q)
H.I E
,- 1 I
I QC Ul v
i l
IN WI C NI nj N nj @ m *- (Y) v-,- G),- w-N C (D Lo i w I
' H 00 EI W
+= 1 i NI 3 INH I W 8 i i
I i
- - C C I CL 00 I I
i @
Z G) N I (.0 1
I Ch
.VeH I
I I
(.D C (D C E I O NI N M N m N U) C4 N Lo v N v Lh t-N @ i 00 i Wv
@ l I 1 l
- - e
- - e e-4 - I v=
1 H vi 1
T=
4 HN Ql 3 i
I...
c 00 CL i l
i m U u).
i I
i U)
C y)
I mI e *- v v N - CD (D v-fr) v-CD v-CD (D v-I C1 2 H
2 gi i I i NI D C
3 Wl
- 1 I
L OEC Oe lAl i I
I ZC-I EI I
I vHc Q *
- U') i I
I E F-I E (A I
I I
IOM Q U)
I I
I C W US UC I
I I U E U)
W WI i
1 1
HH EU i
i I L. O E
- . I I
I Q W
b.,>=Z l
EI I
I W L.
O O F-O I O I I
I t.0 J O
)
HH I CH I I
I cc c J F-1 IHI i
,,.J l o c U)
OH hut W
M CD.S)C i 3W I W
W W
W 3
3 3
3iHi agO I cI HHg 8
H
%CW8
% I IWI u) W l.0 US 3 l.h I3I I CiWCO H
W>J l H I E E I W W W to U)U)U1U) 3 3 3 E I I F-I CL 3 I U)
CL U) W 8 O1 I
i
)OCi
7 8
fo 4
2 5
2 1
7 8
0 _
L _ 3258901 447592827 _ 6 _
/
6 _
A _ 22333353453231 3
_3 1
1 T _
T _
_ 5 _
1 N
D _
O _
/
O T _
8 I
E_
0 T
S _
4 _ 0000000000000000 _ 0 _
)
d C
P _
2 __
e E
A _
u R
L _
n I
i t
D M __
4 _ 0000000000000000 _ 0 _
n s
u D
0 2 _
N 1
t A
R _
9 _
3 I _
1 D
D _
E E4 8 _ 21 4001 0000001 01 0 _ 0 _
L B
E2 N _
)
1 _
_ 1 _
A P0 O _ H T
S3 I _ P 3 _
6 T_M 1 _
D0 C __
(
N7 E
D 2 __ 6028587357572326_2
_ 6 _
I8 R _ E 1
1 1 1
1 1
U ZI _ E 1 _
1 DD _ P 8 _
_ 0 H0/
_ S C1 T A 0 D M __ D 7 _ 2877991 424281 67 _ 8 _
1 E4 0
N 1
1 221 323421 1 1 1 _ 2 _
0 1 _ I 4 _
_ 3 _
O T7 D _ U A8 P _
)
DS _
_ S S
3 _ 3323523776848434 _ 2 _ R R
D _
_ 7 _ U U
E _
1 _
_ OND O -
E _
_ HO H
P_
_ ( I D : S __
- MT RS
_ LCI OS
_ AES CA
_ CRS E
EL I
L RC
_ FD T
_ O G
FYN _
N _
E O
OTO _
O _
_ SLO U
II _
DI _
_ DB DLT _
NT _
_ L _ OAS OIA _
I C _
_ A _ IIR E
IBV_
UE _
E E
E E
U U
U U_O
_ T _ RR J
T RAE g,
R _
NEN SES SUS NUN
_-EAO r.
I ETL _
I _ NNNEEESSSSSUUUNN _ T PUH S
PSE _
D _
D
'((
8 fo 5
2 5
2 1
7 8
0 -
L _ 6828494791 542551 _ 0 _
/
6 _
A _
1 2233787653321 2 _ 3 _
T _
T _
_ 6 _
1 N
D _
O _
1
/
O T_
8 I
0 T
E_
S 4 _ 000O000000000080__ 0 _
C P _
2 _
)
d E
A_
e R
L _
un I
D i
t M_
4 _ 0000000000000000 _ 0 _
pC (t
/
i.
D 0
2 _
N 1
A R _
9 _
3 I _
1 _
D D_
E E4 8 _ 0000000000000001 _ 1 L
E2 N _
)
1 _
B P0 O _ H A
S3 I _ P 3_
T T _ (M 6
1 D0 C
N7 E _ D 2 _ 1 21 203201 2030320_3
_ 2 _
I8 R _ E 1 _
1 U
ZI _ E 1 DD _ P 8 _
_ 0 H0/
_ S C1 T A0DM_D 7 _ 2026405343896894 _ 3 _
E4 0
N 1 1 1 22544431 1 1 1 _ 8 _
0 1
_ I 4 _
_ 3 _
O T7 D _ W A8 P _
)
ES _
_S S
D _-
3 _ 3690067446726446 _ 4
__R R
1 1 1 1 431 1 1 1
_U U
E_
1 _
_ 2 OND O=
E_
_ HO H
P_
_ ( IG dss _
_ MTN R $'
_ LCI OS
_ AES CA
_ CRS E
EL II L
RC
_ FDM T
_ O G
FYN _
N _
E 0
OTO _
O _
_ SLO V
II _
DI _
_ DB DLT_
N T __
_ L _ OAS OIA -
_ IIR E
IBV_
UE _
E E
E E
U U
U U_A T _ RRU
/
T RAE _-
R _
NEN SES SUS NUN _ O _ERO
((
~
I ETL I _ NNNEEESSSSSUUUNN _ T_PUH S
PSE _
D _
2~
O 8
f
' o 6
2 5
2 1
7 8
0 _
L _ 4959951 20881 6531 _ 6 _
/
6 _
A _
1 1 1 231 231 1 1 _ 4 _
T _
T _
_ 2 _
1 N
D_
O _
1
/
O T _
8 I
E _
0 T
S _
4 _ 0000000000000000
_0 C
P _
2 _
)
d E
A _
e R
L _
u I
n D
i M_
t 4 _ 0000000000000000 _ 0 _
O (c
n D
0 2 _
o N
1 _
A R _
9 _
I _
1 _
3 D -
D _
E4 8 _ 0000000B00000000 _ 0 _
E L
E2 N _
)
1 _
l B
P0 O _ H A
S3 T __ P I _
3 _
T 6
M 1 _
D0 C_
(
N7 E
D 2_ 021 000001 0000000 _ 4 _
I8 R _ E 1 _
U ZI _ E DD _ P 8 _
_ 7 1
H8/ - _ S C1 T A0DM_D 7 _
1 2621 53990025489 _ 6 _
E4 0 _ N 1 1 21
_ 1 _
0 1
_ I 4 _
_ 1 _
O T7 D _ U A8 P _
)
FS _
_ S S
3 _ 3587808308891
_ 6 _ R 52_
1 R
D_
1 1 1 1 1 2 _ U U
E_
1
_ 1
_ OND O=
E_
_ HO H
P __
I
(
D:S_
_ MT RS
_ LCI OS
_ AES CA
- CRS E
EL I
L RC
_ FD T
_ O G
FYN _
N _
E 0
OTO _
O _
_ SLO V
II _
DI _
_ DB D L T __
NT _
_ A _ II I B V __
UE _
E E
E E
U U
U U_T _ RRU ET O
RAE R _
NEN SES SUS NUN _ O _ EAO I
ETL _
I _ NNNEEESSSSSUUUNN _ T _ PVH S
P S. E _
D _
- p fl
_ O 8
f o
7 2
5 2
1 7
8 0 _
L _ 37531 1 6581 983328' _ 3 -
/
6 _
A _
1 1
_ 9 1
T _
T _
1 N
D __
O _
T _
/
O 8
I E _
0 T
S _
4 - 0000000000000000
_0
)
d C
P _
2 -
e A __
E u
n R
L i
I L
t D
n M_
4 _ 0000000000000000 _ 0 Oow 0 __
2 _ -
DN 1
A R _
9 _
3 I _
1 _
E D
D _
L E4 8 _ 0000000000000000 0 _
B E2 N _
)
1 _
AT P0 O _ H S3 I _ P 3 _
T_ M 1 _
6 C
(
D0 N7 E _ D 2_000000000001 0000 _
1 _
I8 R _ E 1
U ZI _ E 1 DD _ P 8 _
_ 0 H8/
_ S C1 T A0DM D
7 _
1 021 0021 36732224 _ 6 E4 0 - N 1
_ 4 0
1 _ I 4 _
O T7 D _ U A8 P _
)
GS _
_ S S
3 - 27321 04 _ 6 _ R 4455241 1
1 R
D_
_ 4 _ U U
E_
1 _
_ OND O=
E __
- HO H
P_
_ ( IG D ;S _
_ MTN RS
_ LCI OS
_ AES CA
- CRS E
EL II L
RC
_ FDM T
_ O G
FYN _
N -
E 0
OTO _
O -
_ SLO V
II _
DI _
- DB DLT_
NT -
_ A _ IIR IBV_
UE _-
E E
E E
U U
U U_O E
_ T _ RRU O
T RAE R -
NEf SES SUS iUN i
_ EAO A
I ETL _
I - NNNEEESSSSSUU( NN _ T _ PUH S
PSE _
D -
~
2 #
l
0 8
fo 8
2 5
2 1
7 8
0_
L _ 63458007021 04979 _ 5 _
A _ 5711 008704973751 _
6
/
_1 1
T _
T _
1 1 1 1 1 1 221 1 1 1
1 _
1 N
D_
O _
_ 2 _
T_
/
O 8
I E_
)
d 0
T S_
4 _
00080O0008000000_ _ 0 _
e C
P_
2 _
u E
A_
n R
L_
i t
I n
D o
M_
4 _ 0000000000000000__
0 _
c D
0_
2 _
O3 s
N 1
A R _
9_
I _
1 _
E D
D_
L B
E4 8 _ 324001 1 0091 1 021 2 _ 7 _
A E2 N _
)
1 1
_ 3 _
T P0 O_H S3 I _
3 _
T_P M
1 _
6 D0 C _
(
N7 E _ D 2_ 6962059937428479 _ 0 _
I8 R _ E 1
1 1 1 1 1 1 2 1 22231 3 _ 1 _
U ZI _E
_ 3 _
DD_S
_ P 8_
_ 0 1
H8/
C1 T A0DM_D 7_496?036793748251 _ 1 _
E4 0
N
- _ 228?751 926205536_ 6 _
0
_ I 4 _
1 1 1 1 1
_ 2 _
0 1
T7LD_ U
_ 1 A8LP
)
AS _
_ S
=
S 3 _ 338681 41 839381 47 _ 7 _ R D_
R
- _ 1 2222337543421 1 1
_ 0 _ U U
E_
1 _
_ 5 _ OND O=
E_
_HO P_
H'
( IG D:S_
_ MTN RS
_ LCI OS
_ AES CA
_CRS E
EL I
L RC
_ FD T
_ O F Y N __
G N _
E OTO O _
_ SLO OU II _
DI _
_ DB DLT_
NT_
_ L _ OAS OIR_
_ A _ IIR IBU_
UE _
E E
E E
U U
U E
U_O
_ T _ RR T
RAE R _
NEN SES SUS NUN
_ EAO O
ETL I _
I P S E _-
NNNEEESSSSSUUUNN _ T _ PVH S
D _
- 2 J
l
_ =O 8
f o
l DN A
DE m E 0.
17 P
0 _
L _ 972?1 57549001 774 _ 5 _
8 S
6 _
A _ 21 1 1
1 1 1 44541 1 2 _ 6 _
09 T _
T _
_ 3 _
D 61 N
D_
O_
N E,
O T_
IW R0 I
E_
U3 T
S 4 _ 0000000000000008 _ 0 _
F TAE C
P _
2 _
0RN E
A _
~
EU S
R L _
E PJ M
I LB EH D
T. G M_
OAi AO 4 _ 0000000000000000 _ 0 _
U D
0 2 _
Y TR N
1 LH A
R _
9 _
C ET I _
1 _
N D
E D
D _
U 7
QS8 E4 8 _ 72000000071 52320 _ 9 _
V9 E2 N _
)
1 _
1
- _ 3 _
E R
P0 O _ H 1
m S3 I _
P 3 _
F 0,
T_U 6
1 _
I 1 1 D0 C
N NY N7 E _ D 2_ 5921 1
23432732753 _ 9 _
1 1 1 1 1 1 _
1 A
I U
ZI _ E
- 1 J
_ 0
.EA H8/
_ S 4 RJ C1 T I
A0DM_D 7 _ 64869229091 26681 _ 9 _
E D E1 0
N 1
1 2231 1
_ 8 _
L B
0 1
_I 4 _
_ 1 O
A T7 D _ U T
A8 P _
)
AS _
_ S S
3 _ 1 22O1 221 1 1 01 1 20 _ 8 _ R 1
R D_
~
_ 1 _ U U
E __
1 _
_ OND O=
E_
_ HO H
P_
_ ( IG
- dss,
_ MTN R$
_ LCI OS
_ AES CA
_ CRS EL II RC
_ FDM
_ O FYN _
N _
EF OTO _
O _
_ SLO II _
DI _
_ DB DLT _
NT _
_ L _ OAS OIA _
IC _
_ A _ IIR I B V __
UE _
E E
E E
U U
U U_O O
_ T _ RRU RAE R _
NEN SES SUS NUN
_ EAO ETL _
I _ NNNEEESSSSSUUUNN _ T _ PUH PSE _
D _
i Cd
8 fo 2
5 1
0 1
7 8
0 _
L _ 66832491 74942 _ 8 _
1 1 1
/
6 _
A _
1 1 1 1 321 2 1
_ 9 _
1 T -
T _
_ 1 _
N D_
O _
1
/
O T_
8 I
E-0 T
S -
4 _ 0000000000000000 _
0 _-
)
d C
P _
2 _
e E
A _
u R
L _
n I
i t
D M_
_- 0000000000000000 _ 0 _
4 i.
D 0
2 N
1 t
A R __
9 _
I 1 _
4 D
D __
E E4 8 _ 2000001 001 2291 03 _
1 L
B E2 N _
)
1 -
_ 2 _
A P0 O _ H T
S3 I _ P 3
6 TM 1
D0 C _-
(
N7 E
D 2
_-21 1 1 3241 37628336 _ 3 _
I8 R _ E 1
_ 5 -
U ZI _ E DD_P 8
1
_-0 H0/
S C1 T A0DM_D 7 _ 257282497909?51 3 _ 0 _
E1 0
N 1
1 1
_ 1 _
0 1
- I 4 _
_ 1 _
O T7 D _- U A8 P
)
BS _
_ S S
3 _ OOOO1 OO1 1 4340000 _ 4 _ R D_
R
_ 1 _ U E_
U 1 _
_ OND O=
E_
_ HO P_
H
(
IG D8_
_ NTN Rg
_ LCI OS
_ AES CA
_ CRS E
EL II L
RC
_ FDM T
_ O G
FYN _
N -
EF 0
OTO _
O _
_ SLO V
II _
DI
_ DB DLT_
NT
_ L _-OAS OIA IC _
_ A IIR E
IBV -
UE _
E E
E E
U U
U U_O
_ T - RRU T
RAE NEN SES SUS NUN R
_ EAO I
ETL NNNEEESSSSSUUUNN _ T _ PVH I
S PSE _
D -
2 E' tl l
O-8 fo 3
m m_
v.
5 1
0 1
h 7
a 8
0_
L_
4860782504165574 _
2_
/
6 _
A_
22 1
1 2221 1 1
__3 T_
T_1 1
D_
O_
_2_
1 N
/
O T_
8 I
E_
0 T
S_
4 _
2_0000000000000000_0_
C P_
)
d E
A __
e R
L u
I
~
n D
i M_
4 Ot
_0000000000000000__0_
n D
0 2_
o N
1 _
c A
R __
9_
(
1 I
4 D
D_
E4 8_31 00010001 3 5 1 0 1 0 _ 6 __
c E.
E2 N_H
_ )
1 _
_ 1 L
B P0 O_P A
S3 I
T 6
T_M 3 __
1 a
D0 C_(
N7 E_
D 2__3331 3131 32367325_4
_ 9 _
I8 R_E 1
U ZI _ E' m
H0/1DD_S
_ P 8_
_ 0 8
m C1T 1
A0DM_D 7_5395259267456247_4
_ 1 _
1 E1 0_IN 1 1 1 1 1 1
0 1
4 _
_ 1 _
0 T7 D _ U A8 P __
_ )
CS_
6_S A
S 3_31 4421 O21 41 R
T 01002_2__U R
D_
A U
E_
1 _
OND O=
E_
_ HO H
.P_
_ ( IG D : S __
_ MTN RS
_ LCI OS
_ AES CA
_ CRS E
EL II L
RC
_ FDM T
_ O F Y N __
G N_
EF OTO_
O O_
_ SLO U
II DI _
_ DB DLT_
NT_
_ L_OAS OIA_
IC_
_ A_IIR E
IBV_
UE E
E E
E U
U U
U_O
_ T _ RRU O
T R A E __
R _
NEN SES SUS NUN
_ EAO ETL D_NNNEEESSSSSUUUNN T_PVH I
I _
S PSE _
21 -
l' ll l
l lll{1l
{
o 8
fo 4
5 1
0 1
7 8
0 -
L - 3800447636076230 /
6 -
A - 9425956478771 551 1 T -
T -
1 21 1
1 1 N
D -
O -
1 T -
/
O 8
I E-0 T
S -
4 - 0000000000000000 )
d C
P -
2 -
e E
A -
u R
L -
n I
i t
D n
M-4 - 0001 00000000001 0.o (o
D 0 -
2 -
c N
1 A
R -
9 -
4 I -
1 -
D D -
E 8 - 61 6921 0000294221 E4 L
B E2 N -
)
1 -
231 2 A P0 O - H
- - T S3 I - P 3 -
6 TN 1 -
D0 C -
(
N7 E - D 2-3649621 7051 49029 I8 R - E 1 - 3705222 1 22241 1 4 U ZI - E 1 1 DD-P 8 -
- 0 H0/
- S C1 T A0DM D
7 - 5643381 43693001 1 E1 0 - N
- - 4476524355333335 0 1 - I 4 - O T7 D - U A8 P -
)
DS -
S S
3 95683358981 50089 R R
D-1 1
1 1 U U
E-1 -
1
- OND O -
E-
- HO H
P-( IG D:S-
- MTN RS
- LCI OS
- AES CA
- CRS E
EL II L
RC
- FDM T
- O G
FYN -
N -
E O
OTO -
O -
- SLO U
II -
DI -
- DB DLT -
NT-
- L - OAS OIA -
IC -
- A - IIR E
IBV-UE -
E E
E E
U U
U UT - RRU T
RAE -
R -
NEN SES SUS NUN - O - EAO O
I ETL -
I - NNNEEESSSSSUUUNN - T - PUH S
PSE -
D -
- 3 l
8 f
o 5
6 1
0 1
7 8
0 _
L _ 571 25029e76671 1
_ 2 _
1
/
6 _
A _ 3597861 9a991 534 _ 4 _
1 l
1 T _
T _
1 1 1
_ 2 _
N D _
O _
1 1
/
O T_
8 I
E _
~
0 T
S _
4 _ 0000000000000000 _ 0 _
)
d
~
C P_
2 _
e E
A _
un R
L _
i I
t D
n M_
4 _ 0000000000000000 _ 0 _
oc D
0 2 __
N 1 _
(
A R _
9 _
4 I _
1 _
E D
D _
L E4 8 _ 022501 001 000363 1
_ 1 _
B E2
)
1 _
1 N __
_ 2 _
AT P0 O
H S3 I _ P 3 _
T __ M 6
1 _
D0 C
(
~
N7 E _ D 2 _ 3458498376033345 _ 5 _
I8 R _ E 1
_ 1 22 1 351
_ 2 _
U ZI _ E
_ 2 _
1 DD _ P 8_
_ 0 H0/
_ S C1 T A0DM_N
_ D 7 _ 8381 761 656790998 _ 3 _
E1 0
- _ 1 24453855564521 2 _ 1 _
0 1 _ I 4 _
_ 7 _
O T7 D _ U A8 P _
)
ES _
_ S S
3 _ 48671 91 366040987 _ 3 _ R R
D_
1 1 21 253e21 1
_ 8 _ U U
E_
1 _
_ 2 _ OND O=
E __
_ HO H
P_
_ ( IG D:S_
_ MTN RS OS
_ - _ LC
_ AES CA
_ CRS E
EL II L
RC
_ FDM T
_ O G
FYN _
N _
EF 0
OTO _
O _
_ SLO V
II _
DI _
_ - _ OA
_ DB D L T __
NT _
_ L OIA IC _
_ A _ IIR E
IBV_
WE _
E E
E E
u U
U U_T_
_ RRU T
RAE R _
NEN SES SUS NUN
_ O EAO I
ETL _
I _ NNNEEESSSSSUUUNN _ T _ PUH S
PSE _
D _
- 5
- ]
8 fo 6
6 1
0 1
7 8
0 _
L _839251 85361 44032 _ 4 _
/
6 _
A _
1 21 1 21 353553122 _ 3 _
1 T _
T _
_ 4 _
1 N
D _
O _
/
O T _
8 I
E _
0 T
S _
4 _ 0000000000000000_ 0 _
C P _
2 _
)
d E
A _
eu R
L _
n I
D i
4 _ 0000000000000000 _ 0 _
t.
M_
o D
0 2_
c N
1 A
R _
9 _
(
I _
1 _
4 D
D _
E E4 8 _ 0000000000000000 _ 0 _
L E2 N _
)
1 _
B P0 O _ H AT S3 I _ P 3 _
T_(
6
_ N 1 _
D0 C
N7 E_
D 2 _ 0460080030030000 _ 6 _
I8 R
E 1 _
_ 1 _
U ZI DD__E P
8_
_ 0 1
H0/
S C1 T A0DM_N
_ D 7 _ 4445698874979868 _ 6 _
E1 0
1 1 32321 1 1 _ 5 _
0 1
_I 4 _
_ 2 _
O T7 D _U A8 P _
)
FS _
_ S S
3 _ 4597920732245274 _ 2 _ R R
D_
1 1 1 1 1 1 21
_ 6 _ U U
E_
1 _
_ 1 _ OND O=
E_
_ HO H
.P_
_ ( IG D
S__
_ MTN RS
_ LCI OS
_ AES CA
_ CRS E
EL II L
RC
_ FDM T
_ O G
FYN _
N _
EF O
OTO _
O _
_ SLO U
II _
DI _
_ DB DLT_
NT_
_ A _ IIR I B V __
UE _
E E
E E
U U
U E
U_O
_ T _ RRU T
RAE R _
NEN SES SUS NUN
_ EAO I
ETL _
I _ NNNEEESSSSSUUUNN _ T _ PVH S
PSE _
D _
- 3) 1C
8 fo 7
i 6
1
+-
0 4
1 7
8 0_
L_91 92666872502021 _
/
6 __
A 1
1 1 1 23221 1 1 2_
T_
T _
1 1
N D_
O _
/
O T_
8 I
E_
0 T
S 4 _ 0000000000000000
)
d C
P_
2 _
e E
A u
R L _
n I
i t
D M_
4 _
n 0000000000000000_
o D
0_
2 _
c N
1
(
A R __
9 __
I 4
1 D
D_
E E4 8_ 0000000000000000 e
L B
E2 N _
)
1 A
P0
.O __ H T
S3 6 T_M 3 __
I P
1 D0 C_ (
N7 E_ D 2_10000000001 10000_
I8 R __ E 1
U ZI DD__E
+
P 8 _
_ 0 1
H0/
S 8
C1 T 1
A 0 D M __ D 7_51 3831 6902908887_
1 E1 0_
N 221 1 1
1 4 _
O 0
D_I T7 P __ U A8
_)
GS_
_ S A
S 3_30643509?0594244
_ R T
R D_
1 1
1
- U A
U
.E_
1 _
_ OND O=
E_
_ HO H
.P_
_ ( IG D tS _
_ MTN RS'
_ LCI OS
_ AES CA
_ CRS E
EL II L
RC
_ FDM T
_ O F Y N __
G N _
EF OTO O _
DI _
_ DB DLT_
NT_
_ OAS OIA_
_ IIR E
IBV_
UE _
E E
E E
U U
U U_
_ RRU T
RAE _
R _
NEN SES SUS UN
_ EAO lt I
ETL _
I _ NNNEEESSSSSUULNN_
_ PUH S
PSE_
D _
~
~ d
. O 8
fo 8
6 1
0 1
7 8
0 _
L _ 4055739270508074 _ 6 _
/
6 _
A _ 9698264484245744 _ 2 _
T _
T _
1 1
23221 22233331 2 _ 2 _
1 1
N D _
O -
_ 4 _
/
O T -
8 I
E __
0 T
S 4 - 0000000000000000 _
0_
C P _
2 -
)
d E
A _
e R
L _
u I
n D
i M_
t 4 _ 0001 00000000001 0 _
O (c
2_
n D
0 2 _
o N
1 _
A R _
9 _
I _
1 _
4 D-D _
E E4 8 _ 8684231 01 981 9255 _
2 __
L E2 N _
)
1 _
1 232 241
_ 2 B
P0 O _ H
_ 2 _
A S3 I _ P 3 _
T T __ M 6
1 _
D0 C_
(
N7 E
D 2__ 771 0769692829668 _ 3 _
I8 R _ E 1
61 473331 25582327 _ 1 _
U ZI _ E 1 1 1
_ 0 _
1 DD _ P 8 -
_ 1 _ 0 H8/
_ S C1 T A0DM_D 7 _ 5630831 49061 9865 _ 4 _
E1 0
N
- _ 8875386382083983 _ 6 _
0 1
_ I 4 _
1 1 1 1 1 1 221 1 1
_ 2 _
O T7LD_ U
_ 2 _ :
A8LP _
)
A S __
_ S S
3 _ 41 3001 8289361 496 _ 5 _ R R
D_
- _ 2344544965554222 _ 2 _ U U
E_
1 _
_ 7 _ OND O =
E_
_ HO H
P __
_ ( IG D:S_
_ MTN RS
_ LCI OS
_ AES CA
_ CRS E
EL II L
RC
_ FDM T
_ O G
FYN _
N _
E O
OTO _
O _
_ SLO U
II _
DI _
_ DB D L T __
NT _
E IBU _
UE _
E E
E E
U U
U U_TA_RR
_ II O
T RAE _
R _
NEN SES SUS NUN _ O _ EAO I
ETL _
I - NNNEEESSSSSUUUNN _ T _ PUH S
PSE _
D _
[j (;
l
v
-I i
- 7-
.s
'm
' p:
/\\
~)$=
<:o
'l 4.
C w-3-
q 3
i i
c i
1 5
l' l
l
\\
z o
I i
i w[
1 I
I r i LU i
i I-t.t'
< $7 CI.
Jl *- N m CD CD N Q C Q Q m (D v v v (D I vi l
c5
(.o i C1 -, -
1 (D I C W Hl H1 1
1 z
I o1 O 1 1
I y
.l Em O
- I HI I
i l
- a H
WI I
I l
- u. *
>=
(n I v i CD C (D C CD CD (D CD CD CD (D (D CD CD (D (D I CD I ogN-U CL I NI I
l W
CI A 1 I
I m
w E
J l i
I J
H-1 I
i mfE Q-1 I
I
$ at e#
El vl GCQQQCQQQCQeNeemici o
cp i N4 8,- I f
t
>H r
(D I I I I
I i
- s u d =D C.
CE I Ch i I
I i
Z C
H I e l I
i 1
ga m
H.
Q
.Q4.
1 I
i 0,0 1 CD (D N CD (D CD (D CD C (D e N CD N== (D I mI c:r m
Wv
- I I'
w m
W (u ri^
1 I NI
@ 85
~
. CL -
OI T I1 I
I (n m H i s mi i
i H@
m
>= l 2,.,
v=
l l
t Z
QQ U 'l v'
I 1
g 5o rN W I C Nl 0") 00 *- CD (D N Q CD (D (D N m N v-v- CD I CD I y *-
H@
gl W e l I NI 3 INH I W I i l
I ecol a M
I' I
I Q U
- w
- x Z CD N I to i
I CC i
Ue>-
1 i
1 00 t
wC C (D C E I O N l e-N Q Q Q CD CD Q (D Q Q Q LD Q 5-Q l CD 1 W,-
CD I r I i i
i m
CD W i H-T I I
I (D
HN OI 3 I
I **
1 C oo (1. I I
l a C (A I I
I (A C
1 (A
- I (Y) I e *- CD CD (D CD G CD Q (D (D (D CD (D CD CD 1 NI Ck:
H i
E OI I I I
D C
t 3
tp i e I i
acro O 18 W4 I
I rC Z
G,,
e i
i w H (S C ** (t) i I
I EHr E Ut i
I I
JUH l
O CA I
i i CWW UC i
i i U CE (n WJ l
I i
HH CE U l
I LQE
- I I
I O IA > Z l r1 I
I WL QHO4 O I I
I (n J O l
HH I CH I t
l - Q co l
C J >- I EHI i J4 O C f.O i
CH I
hut I C l HHg j
l
- -4 Co i
3W I W
W W
W 3
3 3
3iHI m Ce o 2CWI CE I rWr (n W (n v13 v1 r3I I OI W ct O ll'.gp\\
WHI I M i r r r W W W (A (.D (A U1 (n 3 3 3 I r i H I CL D I l_. ()
(1. W W I O I I
I i
N
{
Ibb l
- -. - _ _ _. =.. _ - ~ - _
,l m
O.
1 8
fo 2
9 2
2 1
7 8
0 -
L - 241 1 31 O031 0?9033 8
/
6-A _
1
- 4 T-T-
1 1
N D-O-
/
O T-8 I
E-0 T
S-4 - 000000O000010000 1
C P -
2_
)
d E
A -
e R
L -
u I
n D
i t
M-4 - 000000O000004100 S
n D
0-2-
O (t
u.
N 6 -
A R -
9-I -
1 -
5 D
D-L E4 8
21 9000O0000S441 1 - 8 E
L E2 N -
)
1 -
- 1 B
P1 OH A
S3 I -
3-TP T
3 1 -
D0 C&
N7 ED 2
021 021 O01 1 01 I8 R - E 1 -
321 - 6 1
1 U
ZI - E DD P
8-0 1
H0/
- S 8
C1T 8
t A0GP - D
?
01 O1 iO08Od00201 - 6 f
1 E1 0 - N 0
6 I
4 _
O T7 DU A8 P -
)
BS-S A
S 3 _ 0 O O O 0 O O 3 2 O 0 0 0 0 0 O' 2
R T
R D-U A
U E-1 -
O=
E-OND 4.MTN HO H
P-( IG D:S-RS LCI OS AES CA CRS E
EL x'
FDM II L
RC T
D G
FYN.
G OTO-N_
kEF O_
SLO U
II -
DI DB DLT-NT-c
- L OAS OIA-IC-
- A IIR E
IBV-UE -
E E
E E
?'
U J
RAE-R _
MEH SES SUS. (
t NUN O
EA9 O^
I ETL-I -
1 S
PSE -
D1 NNEEESSSSSUUUNN T
PUH s
y
.51 -
1 x
R
. f
~
A
{
lll1ltt!
- i. p -
.~
O 8
fo 3
1 9
2 2
1 7
8 0 _
L _ 61 441 1 O434331 480 _ 7 _
/
6 _
A _
1 1
_ 6 _
T __
T __
1 1
N D
O T_
/
O 8
I E_
0 T
S 4 _ 000000O000001 800 _ 1 _
C P _
2 _
)
d E
A _
e R
L _
u I
n D
L i
M_
t 4 _ 1 00001 OO00031 008
_G O
(o 0_
n D
2 _
N 6
c A
R _
9 _
I _
1 _
5 D
D _
.._ 0_
E E4 8 _
1 1 000OO001 2651 38 L
E2 N _
)
1 _
_ 2 _
B P1 O _ H A
S3 I _
T __ F 3 __
T 3
P 1
D0 C
(
1 N7 E _ D 2_ 3O1 1 1 OO021 043340_3 _
I8 R _ E 1
~
- 2 _
U ZI _ E DD__P 8_
1 e_ 0 H8/
S C1 T A0DM_D 7 _
1 O1 30OO1 21 01 01 0 _ 2 _
1 E1 - 0 N
_ 1 _
0 6 _ I 4 _
O T7 D _ U A8 P _
)
CS _
_ S S
3 _ 0O2O0OO300000000 _ 5 _ R R
D_
_ U U
E_
1 _
_ OND O=
E
_ HO H
P_
_ ( IG D : S __
_ MTN RS
_ LCI OS
_ AES CA
_ CRS E
EL II L
RC - _
_ FDM T
_ C G
FYN _
N _
E O
OTO _
O _
_ SLO U
II _
DI _
, DB DLT_
NT _
OIA IC _
. L _ OAS
_ IIR U __ A IBV_
UE _
E E
E E
U U
U E
T _ RRU O
T RAE R _
NEN SES SUS NUN O _ EAO I
ETL _
I _ NNNEEESSSSSUUUNN__
T _PU S
PSE _
D _
{g l
8 fo 4
9 2
2 1
7 8
0 -
L - 41 231 60298750957 9 _
/
6 _
A _ 60857221 22241434 6 _
T_
T 1 1 1
_ 9 _
1 N
D O
1 T -
/
O 8
I E _
0 T
S _
4 - 000000000001 3020 _ 6 _
C P _
2 _-
)
d E
A _
e R
L _
u I
n D
i M_
t 4 _ 05061 00001 061 51 2 _ 8 _
n D
0 2 _-
2
_ 4 _
o N
6 _
c A
R _
9 _
(
I _
1 -
5 D
D _
E4 8 _ 80602953351 98877 _ 1 _
E L
E2 N _
)
1 _
3641 1 1 21
_ 7 _
B P1 O _ H
_ 2 _
A S3 I _ P 3
T 3
T M
1 _
D0 C
(
N7 E _ D 2 - 59547851 61 704208 _ 2 _
I8 R _ E 1 _ 33773 1
1 1 1 1 1
_ 6 _
U ZI E
_ 3 1 DD P
8 _
0 H8/
_ S C1 T A0DM_D 7 _ 91 48755659671 426 _ 5 -
E1 0
N
- _ 1 2321 1
1 1 1 1 - 2 _
0 6 _ I 4 _
_ 2 _
O T7 D _ U A8 P _
)
DS _
_ S S
3 _- 2675445252323034 _ 7 R
R D_
_ 5_U U -
E_
1 _
_ OND O=
,E_
_ HO P _
_ ( IG H Dt S_
_ MT R$
_ LCI OS
_ AES CA
_ CRS E
EL I
L RC
- FDM T
_ O G
FYN _
N -
E 0
OTO _
O -
_ SLO V
II _
DI _
_ DB DLT _
NT _
_ L _ OAS OIA _
IC _
_ A _ IIR I B V _-
UE _
E E
E E
U U
U E
RAE R _
NEN SES SUS NUNU_O
_ T _ RRU T
_ EAO I
ETL _
I - NNNEEESSSSSUUUNN - T _ PVH S
PSE _
D _
)dg r
,i
O 8
fo 5
9 2
2 1
7 8
0 _
L _ 50350721 71 532346 4
/
6 -
A _
1 366433322248521 - 0 T -
T _ 1 1
N D _
O -
/
O T -
8 I
E -
0 T
S -
4 _ 000000000000021 0 - 3 _
C P _
2 _
)
d E
A _
e R
L _
un I
D i
t M_
4 _ 020001 0001 01 3520 n O
(o D
0 2 _
1 -
c N
6 _
A R -
9 _
I -
1 5
D D _
E E4 8_ 401 6563857789473
_3 L
E2 N_
)
1 1 21 253
_ 2 -
B P1 O
H
_ 2 -
A S3 I _ P 3 _
T T_(
3
_ M 1 _
D0 C
N7 E _ D 2 _ 51 53592829538077 I8 R _ E 1
1 3321 21 1
1 1 1 1
- 5 U
ZI _ E
- 2 DD__ P 8 _
- 0 1
H0/
S C1 T A0DM__D 7 _ 577500737321 1 275 - 2 _
E1 0
N 1 1 1
_ 9 -
0 6 _ I 4 _
O T7 D __ U A8 P
)
ES _
S S
3 -
1 OO1 O1 O231 01 001 R 1
R D_
1
- U U
E 1
_ OND O=
E-
_ HO H
P_
_ ( IG D:S
_ MTN RS
- LCI OS
- AES CA
_ CR E
EL II L
RC
- FDM T
- O G
FYN_
N -
EF O
OTO -
O -
_ SLO U
II DI -
_ DB DLT NT _
_ L _ OAS OIA _
IC _
_ A _ IIR IBV_
UE _
E E
E E
U U
U U_T - RRU E
T RAE R _
NEN SES SUS NUN - O _ EAO O
I ETL _
I _ NNNEEESSSSSUUUNN - T - PVH S
PSE _
D _
3
O 8
fo 6
0 3
2 1
7 8
0 -
L _ 47904S4341 27008 - 9 1
/
6 -
A 2221 1 1
- 7 1
1 1 1
T -
T -
1 N
D -
O -
1
/
O T -
8 I
E -
0 T
S -
4 - 0000000000000000 _ 0 _
)
d C
P _
2 -
e E
A -
u R
L -
n I
i t
D n
M-4 - 00000000001 00000 -
1 O
(c o
D 0 -
2 -
N 6 -
A R -
9 -
5 I _
1 _
D D _
E E4 8 _ 004331 1 21 8531 422 - 0 _
L B
E2 N -
)
1 1 1
- 6 _
A P1 O - H T
S3 I - P 3 _
3 T - M 1 _
D0 C -
(
N7 E _ D 2 - 33451 42963065446 - 5 _
I8 R - E 1
1 1
- 8 _
U ZI
_ E 1 DD P
8 _
_ 0 H0/
- S 8
C1 T 8
A0DM D
7 - 031 2OO1 070531 230 E1 0 - N
_ 2 0
6 - I 4 _
O T7 D - U A8 P -
)
FS -
_ S A
S 3 _
1 1 OOOOO20000001 0 - 5 _ R T
R D _
_ U A
U E _
1 _
_ OND O -
E-
- HO H
sP -
( IG D
S-
_ MTN RS-LCI OS
_ AES CA
- CRS E
EL II L
RC
- FDM T
_ O G
FYN -
N _
EF O
OTO -
O _
_ SLO U
II -
DI _
_ DB D L T.-
NT -
_ A _ IIR E
IBV_
UE -
E E
E E
U U
U U_T - RRU T
RAE -
R -
NEN SES SUS NWN - O _ EAO O
I ETL -
I _ NNNEEESSSSSUUUNN - T _ PVH S
PSE -
D _
JE#
_ O 8
f o
7 0
3 2
1 7
8 L _ 691 0932584409380 _
1 0 __
/
6 A _
1 1 1
21 1
_ 4 _
T_
T _
1
_ 1 _
N D
O _
1
/
O T_
8 I
E_
)
0 T
S 4 _ 0000000000000000 _ 0 _
d e
C P _
2 _
u E
A _
n R
L _
i I
t n
D M __
4 _ 0000000000000000 _ 0 _
o c
D 0
2 _
. OS s
N 6 _
A R __
9 _
I 1
E D
D _
L E4 8 _ 21 01 20000434601 4 _ 8 _
BA E2 N _
)
1 1
- 3 _
T P1 O _ H S3 I _ P 3 _
T __ M 3
1 _
D0 C_D
(
N7 E
2_3542301 335622343 _ 9 _
I8 R _ E 1
_ 4 _
U ZI
_E DD__P 8 _
1
_ 0 H0/
S C1 T A0DM_N
_ D 7 _
1 375431 1 44441 0 3 2 __
7 _
E1 0
4 _
0 6 _ I 4 _
O T7 D _ U A8 P _
)
GS _
_ S S
3 _ OOO2OOO1 00001 _ 7 _ R 1 1 1 R
D _
_ U U
E _
1
_ OND O=
E __
_ HO H
P
_ ( IG D:S_
_ MTN RS
_ LCI OS
_ AES CA
_ CRS E
EL II L
RC
_ FDM T
_ O G
FYN _
N _
E 0
OTO _
O _
_ SLO V
II _
DI _
_ DB DLT_
N T __
- A _ IIR IBV_
E UE _
E E
E E
U U
U
_ T _ RRU RAE R _
NEN SES SUS NUNU_O T
O
_ EAO I
ETL _
I _ NNNEEESSSSSUUUNN _ T _ PV S
PSE _
D _
~ (c-
_ C 8
f o
8 0
3
~
2 1
7 8
0 _
L-8933858549362324 /
6 _
A _0674275688042398
- 1 T _
T 1 1 221 1 1 21 1 N
D _
O - : _
T _
/
O 8
I E -
~
0 T
S _
4 - 0000000000024230-1 -
)
C P _
2 - de E
A _
u R
L _
n I
i D
t M_
4 - 1 7061 200821 1 6242 n O5 o
D 0
2 -
1 31 g N
6 _
A R
9 -
I 1 _
D D _
E E4 8
6930269395973327 L E2 N -
)
1
- 249621 1
2371 621 BA P1 O _ H 1 T S3 I - P 3
T_M 3
1 _
D0 C
(
N7 E _ D 2 - 981 59401 00095625 I8 R _ E 1
_ 4621 633334434333 -
1 -
U ZI - E 1 1 1 DD _ P 8 _
- 0 H8/
_ S C1 T A0DM D
7 - 77042841 48850074 E1 0 - N
- - 235531 1 1 31 1 1 2222 -
1 -
0 6 - I 4 - O T7LD _ U A8LP -
)
AS -
- S S
3 _ 589845501 4524046 R R
D -
1 1 U U
E -
1
- OND O=
E -
- HO P_
H
- ( IG D:S
- MTN R S'
- LCI OS
- AES CA
- CRS E
EL II L
RC
- FDM T
- O G
FYN -
N -
E 0
OTO -
O -
- SLO V
II _
DI -
- DB DLT -
NT-
- L - OAS OIA -
IC -
- A - IIR E
IBV-UE -
E E
E E
y U
U UT - RRU T
RAE -
R -
NEN SES SUS NUN - O - EAO O
I ETL -
I - NNNEEESSSsSUUUNN - T - PUH S
PSE -
D -
- 9)
- lC i
8 f
o 1
D N
A D.
m E
E 0 1
P 0 _
L _ 393021 031 621 5861 _
1 _
S 6 _
A _ 1 1 1 1 1 1 1 1 D 6 T _
T _
3331 1 _ 4 _
0
_ 2 _
N.
N D _
O _
E O
T _
IW R E_
I U
F T T
S 4 _ 00O0000000801 O A7 C
P _
2 _
000_1 R8 E
A_
S E9 R
L E P1 M
I L
ER D
B M_
A TE 4 - 00OO00000221 441 2 -
0__ 4 _
T T
D 0
1 _
AR Y TA N
6 _
LU A
R _
9 _
C N EQ I _
1 D
E D
D _
' OB001 1 594241 3 _ 5 _
8 _ 401
~
U D
SN E4 Q
VO E2 N_
)
1 _
1
_ 4 _
E R
C P0 O_
H F mE S3 I _
P 3 _
0S T_U T 6 6
1 _
N D0 C
9 5 0 7' G4745649041 8 _ 9 _
N N7 E_
D 2 __
IO O I8 R _ E
~ 1 1 1 1
_ 0 _
I J
U ZI _ E
_ 1 _
T DD _ P 8 _
_ 0 C
1 E
.R H8/
_ S 6
C1 T
. _ O323673853668530 _ 8 _
I A0DM_N
_ D 7
E D E4 0
_ 6 _
L B
0 6 _ I 4 _
0 A
T7 D _ U T
A8 P _
)
- - AS _
_ S S
3 _ 01 OOOOOO001 01 00 _ 4 _ R 1
R D _
_ U U =
E_
1 _
_ OND O=
.E_
_ HO H
.P
_ ( IG D gS _
_ MTN RS
_ LCI OS
_ AES CA
_ CRS EL II RC
_FD O
FYN _
N _
E OTO _
O
_ SLO II _
DI
_ DB DLT _
NT_
_ L _ OAS OIA _
_ A
__II IBV_
UE -
E E
E E
U U
U U_O
_ T RRU RAE R _
NEN SES SUS NUN
_EA ETL _
I _ NNNEEESSSSSUUUNN _ T PVH PSE _
D _
_y-
m, O
8 fo 2
m 4
u 2
m 3
1
,s 7
8 0_
L_?O6?45?0391 80423_6_
/
6_
A_
1 1 1 21 1 3
T_
T 1
1 N
D_
O_
_1 T
/
O 8
I E_
0 T
4 -
S_
P_
2_0O00000000000000_0_
)
d C
e E
A u
R L __
+
n I
i
. t D
M 4 _
0 _-
_0O00000000102000_3 n
0 (6
o D
2_
c N
6_
m A
R 9 _-
I _
1 D
D_
E E4 8_5O00002001221 101 -
5_
L B
E2 N_)
1 1
A
.P0 O_H T
S3 IT_P 3_
6 C_M 1 -
D0
(
N7 ED 2_0O239242753631 1 1 _ 9 -
I8 R_E 5_
1 _
1 U
ZI E
1 DD_P 8_
__0 H8/
S 5
C1T 8
A0DM_D 7_2O44531 8635041 1 1 _ 8 _
2 E4 0
N 1
5_
0 6I 4 _
O T7 P_U D
A8
)
BS_
_S A
S 3 __ O O O O O O O O 000001 00_1 _R T
R D_
_U A
U E_
1 _
_OND O-E_
HO H
P_
_(
IG D : S __
_MTN RS LCI OS
_ AES CA
_ CRS E
EL II L
RC
_ FDM T
_ O FYH_
G N_
EF OT0 O _
_ SLO O
U II _
DI _
- DB D L T _-
NT_
L_OAS OIA_
IC_
A_IIR IBV_
UE -
E E
E E
U U
U E
U_O_EAO T_RRU T
RAE_
R_
NEN SES SUS NUN O
ETL_
D_NNNEEESSSSSUUUNN T_PVH I
I S
PSE g
llllll!
]
li!
~
D
~
~
m m
')
(
8 fo 3
u a
s-4 w
m 2
3 1
g 7
8 0_
.A_5?561?2486282?48 _2_
L_
/
6
. T __
_5_
1 1 1 1
1 1 1 1
T_
u O
_1 m
1 N
D_
~
T_
/
O 8
I 0
T E_
S 4 _ 0000000000000000_0_
)
d C
P _
2_
9 e
E A __
u R
L_
n I
i t
D M __
n 4 _ 0100000001001 000_3_
o D
Q (6
0 2_
c N
6_
A R
9_
I _
1 _
D D_
E A
8_ 1 1 0001 L
E4 0 0 1 0 2 0 0 2 __ 0 _
1 1 B
E2 N_)
1 _
1 A
P0 O _H T
S3 T_P 3_
I 6
1 _
D0 C_G N7
_ D E_E 2_22529341 23893425_6
_ 4 _
I8 R
1 _
U ZI
_E H8/DD_S
_P 8_
_0 1
5 C1 T 8
~
A0DM_D 7_2282237262296301
_ 7_
2 E4 0
N 1
6_
0 6 _ I 4 _
O T7 D _ U A8 P _
)
CS_
_S A
S 3_O1 22OOOO001 00820_ 8_U R
T R
D_
A U
E_
1 _
_OND O=
E_
_HO H
P_
_ ( IG D sS _
_ MTN RS
_LCI OS AES CA
_CRS A
E EL II L
RC
_ FDM T
_ O F Y N __
N __
G EF OTO_
O_
O
_ SLO U
II DI
_ DB x.
DLT_
N T __
_ L _ OAS OIA_
IC_
_ A _
T_IIR
.x E
IBV_
UE_
E E
E E
U U
u U_O_
RRU T
Q ETLRAE_
R NEN SES SUS UN t
EAO I _
I D_NNNEEESSSSSUUt NN_T_PVH S
PSE _
o Qt
~
l'
_ O 8
f o
4 4
2 3
1 7
8 0 _
L _ 786471 4200485281 _ 7 _
/
6 _
A _- 21 233344354331 2 _ 9 _
T _
T
_ 4 _
1 1
N D _
O _
/
O T -
8 I
E _
0 T
S _
4 _ 0000000000000000_ 0 _
)
C P _
2 _
e E
A _
d u
R L _
n I
i D
t M_
4 _ 001 0000000003020 _ 6 _
O (o
n D
0 2 _
c N
6 _
A R _
9 _
6 I _
1 D
D _
E E4 8 _
1 4531 3030363361 6 _ 8 _
L E2 N
1 _ 1 1
1
_ 7 _
BA P0 O
T S3 I
3 _
6 T
1 D0 C
N7 2
Q_148584497423471 26 - 8 _
I8 1 1 1 1 1 1 321
_ 0 _
s U
Zl
_ 2 _
DD _
8 _
_ 0 1
H8/
C1 T A0DM 7 _- 2432244054301 51 7 _ 7 _
E4 0
1 1 21 1 21 1 1 21
_ 8 _
0 6
4 _
1 _
O T7 D
A8 P _
)
DS _
_ S S
3 _ O221 OO1 21 21 1 022 _ 8 _ R 1
R D _
_ 1 _ U U
E _
1 _
_ OND O=
E_
_ HO H
P _
_ ( IG D : S __
_ MT RS
_ LCI OS
_ AES CA
_ CRS E
EL I
L RC
_ FD T
_ O G
FYN _
N _
E O
OTO _
O _
_ SLO U
II _
DI _
_ DB DLT _
NT
_ L _ OAS OIA _
IC _.
_ A _ IIR E
I B V __
UE _
E E
E E
U U
U U_T
_ RRU T
RAE R _-
NEN SES SUS NUN O
O _ EAO I
ETL _
I NNNEEESSSSSUUUNN - T _ PUH S
PSE _
D _
_ W1
O 8
fo 5
4 2
3 1
7 8
0 _
L _ ?253543487902361 _ 9 _
1
_7
/
6 _
A _
1 2232598543321 1
T _
T _
_ 5 _
1 N
D _
O _
/
O T _
8 I
E _
0 T
S _
4 _ 0000000000000000 _ 0 _
)
d C
3 _
2 _
e E
f _
u R
L _
n I
i t
D M __
n 4 _ 00000000000031 01 _ 5 _
o D
O (6
0 2 _
c N
6 _
A R _
9 _
I _
1 _
D D_
E E4 8 _ 225523692521 0935 _ 1 _
L B
E2 N __
)
1 1 1 1
_ 9 _
A P0 H
O T
S3 I _
3 _
T_P M
6 1
D0 C _
(
N7 E _ D 2 _
1 522572596865091 _ 3 _
I8 R _ E 1 _
1 1 1 1 364321 1 1
_ 2 _
U ZI _ E
_ 3 _
1 DD _ P 8 _
_ 0 H8/
_ S C1 T A0DM_N
_ D 7 _ 3376544954932233 _ 2 _
E4 0
1 1 1 31
_ 4 _
0 6 _ I 4 _
_ 1 _
O T7 D _ U A8 P _
)
ES _
_ S S
3 _
1 21 O3O1 1 220021 1 1 _ 8 _ R R
D _
_ 1 _ U U
.E_
1
_ OND O=
.E __
_ HO H
P
_ ( IG D ; S __
_ MTN RS
_ LCI OS
_ AES CA
_ CRS E
EL II L
RC
_ FD T
_ O G
FYN _
N _
E O
OTO _
O _
_ SLO U
II _
DI _
_ DB DLT_
NT_
_ A._ I OIA E
IBV _
UE _
E E
E E
U U
U U_T _ RRU T
RAE _
R _
NEN SES SUS NUN _ O _ EAO O
I ETL _
I _ NNNEEESSSSSUUUNN _ T _ PUH S
PSE _
D _
3(g
O 8
f o
6 4
2 3
1 7
8 0 -
L - 570691 8354321 8?5 /
6 -
A -
1 1
2321 22 1
1 T -
T _
' 1 N
D -
O_
T
/
O 8
I E-L 0
T S -
4 _- 00000000O0000000 0 -
)
d C
P -
2 e
E A -
u R
L -
n I
i t
D n
M-4 - 0000000008000000 o D
0 -
2 -
O (6
c N
6 -
A R -
9 -
I -
1 -
D-D -
E E4 8 _ 003202025?4391 1 2 L B
E2 N-
)
1 _
1 A P0 O - H T
S3 I - P 3 _
6 T-M 1 -
D0 C -
(
N7 E - D 2 _- 35233761 32680652 2 -
I8 R - E 1
1 1 1 1 U ZI - E
- DD - P 8 -
- 0 1
H8/
- S C1 T A0DM D
7 - 0241 1 2295421 21 1 0 _
- E4 0 - N 1
0 6 - I 4
- - O T7 D - W A8 P-
)
FS -
- S S
3_ 2O1 O2OO1 21 1 00001 -
1 - R R
D-
. U U
,E.
1 -
- OND O=
E
- HO H
.P.
- ( IG D:S-
- MTN RS
- LCI DS
EL II L
RC FDM T
~
O G
FYN -
N -
E 0
OTO -
O -
- SLO V
II -
DI -
- DB DLT-NT -
- L OAS OIA -
IC -
- A - IIR E
IBV -
UE -
E E
E E
U U
U UT - RRU T
RAE -
R -
NEN SES SUS NUN - O - EAO O
I ETL -
I - NNNEEESSSSSUUUNN - T - PVH S
PSE -
D -
9lE l
_ g 8
f o
7 4
2 3
1 7
8 0 _
L _ 2S44431 91 S041 043 _ 0 _
/
6 _
A _
1 1 1
_ 8 _
1 T_
T_
N D __
O 1
T_
/
O 8
I E __
)
d 0
T S
4 _ 0000000000000000 _ 0 _
e C
P _
2 _
u E
A _
n R
L _
i I
tn D
M __
o 4 _ 00000000001 00000 _ 1 _
c D
0 2 _
g (6
N 6 _
A R _
9 _
I _
1 _
E D
D _
L E4 8 _ 1 01 1 01 001 2731 000_2
_ 8 _
BA E2 N _
)
1 1
T P0 O _ H S3 I _
3 _
T __ F 6
P 1 _
D0 C
(
N7 E _ D 2_
1 21 1 1 01 3631 00031 _ 4 _
I8 R _ E 1 _
_ 2 __
U ZI _ E 1 DD _ P 8 _
_ 0 H0/
_ S C1 T A0DM_D 7 _ O32232O6401 0002 _ 6 _
1 E4 0 _ N
_ 2 _
0 6 _ I 4 _
0 T7 D _ U A8 P _
)
GS _
_ S S
3 _ OOOOOOO 80000001 0 _ 1
_R R
D_
_ U U
E_
1 _
_ OND O-E_
_ HO H
P_
_ ( I D:S_
_ MTN RS
_ LCI OS
_ AES
~
CA
_ CRS E
EL I
L RC
_ FDM T
_ O F Y N __
G N _
E OTO O _
_ SLO 0V II _
DI _
_ DB DLT _
NT _
_L
_ OAS OIA _
IC _
A _ IIR IBV_
W E __
E E
E E
E U
U U
U_T
_ RRU T
RAE R
NEN SES SUS UN 1
O _ EAO g
R I
ETL _
I _ NNNEEESSSSSUUL NN _ T_PUH S
PSE _
D _
_ j 3
(
(
ll
O 8
f o
8 4
2 3
1 7
8 0 _
L_
68902255671 6272 _ 9 _
1
/
6 _
A _ 6580293997864?46 _ 9 _
T _
T _
1 1 1 1 1 1 1 1 1
_ 8 _
1 1
N D _
O _
_ 1 _
O T_
8 I
E _
0 T
S _
4 _ 0000000000001 000_ 1 _
C P _
2 _
E A _
)
d R
L_
e I
u D
n M_
4 _ 01 1 000000341 3531 _ 2 _
1 i
0t D
1
_ 3 _
0 2_
n N
6 _
o A
R _
9_
c I _
1
(
D D _
6 E4 8 _ 4751 3096931 681 69 _
8 __
E2 N _
)
1
_ 2 1 1 1 1 1 34342 1 _
1 E
L P0 O _ H
_ 3 _
B S3 I _ P 3 _
A 6
T _ M 1
T D0 C _
(
2 __.
N7 E _ D 0776773367328634 _ 9 _
I8 R _ E 3224547099974222_ 8 _
1 U
ZI _ E 1
_ 8 _
DD _ P 8 _
_ 0 1
H8/
_ S C1 T A 0 D M __ D 7 _ 9700751 260803794 _ 8 _
E4 0
N 1
445347843531 1
_ 9 _
0 6 _ I 4 _
_ 5 _
O T7LD _ U A8LP _
)
AS _
_S S
3 _ 36635O2454S23364
_ R
_1 R
D _
6 _U U
E_
1 _
_ OND
~
O=
E_
H
_P_
_ HO
_ ( IG D;S_
_ MTN RS
_ LCI OS
_ AES CA
_ CRS E
EL I
L RC
_ FDM T
_ O G
FYN _
N_
E 0
OTO _
O _
_ SLO V
II _
DI _
- DB DLT _
NT _
_ L _ OAS OIA _
IC _
_ A _ IIR IBV_
UE _
E E
E E
U U
u U_T E
_ RRU O
T RAE R _
NEN SES SUS UN O _ EAO ti I
ETL _
I _ NNNEEESSSSSUULNN _ T _ PVH S
PSE _
D _
h
!ll:
8 f
o 1
D N
A D
m E
0 E
1 /
P 0 -
L-466023031 65?9201 S 0
09 6 -
A - 22 1 1 1 1 1 1 1 33421 1 61 T-T -
- 3 _
D N
N D-O -
E,
T -
O IW R0 U3 I
E-F T T
S -
4 0O00000000081 000 - 1 _
AE C
P -
2 -
O Ri l
E A -
S EU E PJ R
L -
M I
L EH D
B A TG M-4 - 000000000222' 520 - 4 1
U T
AO D
0 -
2 -
1
- 2 TR N
6 -
YC LH A
R -
9 -
N ET I -
1 -
D E
D D-7 U
S8 E4 8 - 36300001 5062623 1 Q V9 E2 N -
)
1 -
1 1
1
- 6 E
1 R
P0
.O
- H m
F S3 I -
3 -
TP 0,
T 61 6
M 1 -
N D0 C-(
NY N7 E - D 2 - 931 7667456622528 - 9 IO OR I A I8 R - E 1 -
1 1 21 J TU U
ZI - E
- 0
.EA H0/
- S RJ C1 T 7
I E D A0DM D
7 -
1 523673853663540 - ? -
L E1 0 - N 1
- ? -
B 0
6 I
4 -
O A
T7 D - U T
A8 P -
)
AS -
- S S
3 -
1 2OOOOOO001 1 01 00 R R
D-
_ U U
E-1 -
_ ON O -
E-HO H
P -
(
IG D :S -
- MTN RS
- LCI OS
- AES CA
_ CRS EL II RC
- FDM
_ O FYN -
N -
E OTO -
O -
- SLO II -
DI -
- DB DLT -
NT -
- L
_ OAS OIA -
IC -
- A IIR IBV-UE -
E E
E E
U U
U UT
_ RR RAE -
R -
NEN SES SUS NUN - O EAO ETL -
I - NNNEEESSSSSUUUNN - T - PVH PSE -
D -
~ oD UJ l'
0 8
f o
2 5
1 1
1 7
8 0
L - 94?87670601 59456 /
6 A -
1 1 1 1 221 1 T T -
1 1
N D
O -
1
/
O T -
8 I
E 0
T S
4 - 000000000001 0000 - 1 C
P 2 -
)
d E
A eu R
L n
I D
i t
M 4 - 00000000001 061 00 n D
0 2-O (o
c N
6 A
R 9 -
I 1 -
7 D
D E
E4 8 - 71 00002001 27551 2 :
L E2 N
)
1 - B P0 O
H AT S3 I
P 3-6 T
1 -
I D0 C
(
N7 E
D 2
02331 34286374432 I8 R
E 1
1 1
7 -
U ZI E
1 DD P
8 -
- 0 H8/
S C1 T A0DM D
7 - 21 45631 86350431 2-4 -
E1 0
N 1 0 6
I 4 -
O T7 D
W A8 P
)
8S
- S S
3_ OO8OOOOO200001 00 R R
D
- U U
E 1 -
- OND
,E, O-
- HO H
P
( IG D:
R S~S.
- LCI
- MTN OS
- AES CA
- CRS E
EL II L
RC
- FDM T
- O G
FYN 0
OTO N _.
EF O
- SLO V
II DI -
- DB DLT NT-
- A - IIR E
IBV UE _
E E
E E
U U
U UT - RRU T
RAE R -
NEN SES SUS NUN - O - EAO O
I ETL I _- NNNEEESSSSSUU(J NN T - PUH S
PSE D
3Q
(
0 1
8 fa 3
5 1
1 1
7 8
0-L -
1 89028281 051 31 28 9 -
/
6 -
A - 1 1 21 1
1 1 1 321 1
- 1 1
T -
T -
- 2 1
N D-O -
T-
/
O 8
I E-0 T
S -
4 - 0000000000001 000 - 1
)
d C
P -
2-eu E
A -
n R
L-i I
t D
no M-4 - 1 1 0001 0001 032000 O (7
c D
0 -
2-N 6 -
A R -
9 -
I -
1 -
E D
D-L E4 8 - 220001 0_
01 3671 32 -
1 1 B
E2 N -
)
1 3
AT P0 O - H S3 I - P 3 -
6 T - M 1 -
D0 C -
(
N7 E - D 2-52630341 44836765 7 _
I8 R - E 1 -
1 1
- W ZI - E 1 DD - P 8-
_ 0 H8/
- S C1 T A0DM D
7 - 329523737439731 1 E1 0 - N 1 0 6
I 4 -
O T7 D - U A8 P -
)
CS-
- S S
3 01 42OOO3001 00020 R R
D-
- - U U
.E-1 -
- OND O=
E-
- HO H
,P-
_ ( IG D JS -
- MTN R Q'
- LCI OS
- AES CA
_ CRS E
EL II L
RC
- FDM T
_ O G
FYN-N -
E 0
OTO -
O -
- SLO V
II -
DI -
_ DB DLT -
NT -
- L_OAS OIA -
IC -
- A - IIR E
IBV -
UE -
E E
E E
U U
U UT - RRU T
RAE -
R -
NEN SES SUS NUN -
O O _
T_EA I
ETL -
I - NNNEEESSSSSUUUNN -
PUH S
PSE -
D -
_:1-
^
1
pV 8
fo 4
6 1
1 1
7 8
0 _
L _
1 9878744981 351 38 _ 6 _
/
6 _
A _ 91 08056557781 646 _ 6 _
1 T_
T _
1 21 1 1
_ 4 _
1 N
D __
O _
1
/
O T_
8 I
E_
0 T
S 4 _ 000000000001 3020 _ 6 _
)
C P _
2 _
de E
A _
u R
L _
n I
i D
t M __
4 _ 051 61 00001 064532 _ 4 _
n 2 _
2
_ 5 _
D 0
u N
6 _
t A
R -
9 _
7 I _
1 _
D D _
E E4 8 _ 941 3325638721 483 _ 9 _
L E2 N_
)
1
_ 1 3741 1 1 1 242 1 _ 4 _
BA P0 O _ H
_ 3 _
T S3 I _
3 _
T_PM 6
1 _
D0 C __
(
N7 E
D 2 _ 97021 24803041 324 _ 0 _
I8 R _ E 1 _ 44895221 243221 1 2 _ 7 _
U ZI _ E
_ 5 _
DD _ P 8 _
_ 0 1
H0/
_ S C1 T A0DM_D 7 _
1 570999603972933 _ 2 _
E1 0
N
- _ 224431 2321 221 1 2 _ 1 _
1 0
6 _ I 4 _
_ 4 _
O T7 D _ U A8 P _
)
DS _
_ S S
3_ 2896446463S34056 _
R 5 __
R D _
_ 7 G
U E_
1 _
_ OND O -
E_
_ HO P __
H
_ ( IG D:S_
_ MTN RS
_ LCI OS
_ AES CA
_ CRS E
EL II L
RC
_ FDM T
_ O G
FYN _
N _
EF 0
OTO _
O _
_ SLO V
II _
DI _
_ DB DLT _
NT _
_ L _ OAS OIA _
IC _
_ A _ IIR E
IBV_
UE _
E E
E E
U U
U R _
NEN SES SUS NUNU __ T
_ RRU T
RAE O _ EAO I
ETL _
I _ NNNEEESSSSSUUUNN _ T _ PUH S
PSE _
D _
E
]
l
0 8
fo 5
6 1
1 1
7 8
0 -
L - 228851 5558434607 /
6 -
A - 248876821 7771 742 8 -
1 T -
T 1 1 1 1 N
D -
O /
O T-8 I
E -
)'
0 T
S -
4 - 000000000000021 0 C P -
2 -
de E
A -
u R
L -
n I
i D
tn M-4 _ 020001 0001 01 6621 O
{c o
D 0 -
2 _ N 6 -
A R -
9 -
7 I -
1 -
D D -
E E4 8 - 6261 799772999308 L E2 N-
)
1 _
1 22 1
1 1 3641 BA P0 O - H
- - T S3 I -
3 Tf 6
1 i
D0 C -
(
N7 E - D 2 - 667506431 5393068 I8 R
E 1 -
1 4443586442321 U ZI - E 1 DD - P 8_
- 0 H0/
- S C1 T A0DM D
7 - 8041 541 2271 43408 E1 0 - N 1 1 221 2241 1 1 0 6 - I 4 - O T7 D - U A8 P -
)
ES -
- S 3 _ 221 S
1 31 1 3531 031 1 2 R R
D-
- - U U
E-1 _
- OND O=
E -
- HO H
P-
- ( IG D:S-
- MTN RS
- LCI OS
- AES CA
- CRS Z
EL II L
RC
- FDM T
- O G
FYN -
i _
EF i
O OTO -
0 _
- SLO U
II -
DI _
- DB DLT -
NT _
- L - OAS OIA -
IC _
- A - IIR E
IBV-UE -
E E
E E
U U
U UT - RRU T
RAE -
R _
NEN SES SUS NUN - O-EAO O
I ETL -
I - NNNEEESSSSSUUUNN - T - PVH S
PSE -
D _
- 1P 2b lllllll
8 fo 6
6 1
1 1
7 8
0 _
L _ 9496362695448873 /
6 -
A 3443431 1 1
_ 9 -
1 1 1 1 1 1 1
T -
T
_ 3 -
1 N
D _
O -
/
O T _
8 I
E -
0 T
S -
4 _ 00O0000000000000 )
C P -
2 _
de E
A -
u R
L -
n I
i D
tn M-4 _ 00' 00000001 00000 u D
0 -
2 _
h N
6 -
A R -
9 -
7 I -
1 _
D D -
E E4 3_ 0075331 465960534 _ 1 -
L E2 N -
)
1 1
22
_ 1 BA P0 O - H
_ 1 T
S3 TP 3 -
I -
6 M
1 -
D0 C -
(
N7 E-D 2_ 686841 8095645098 _
I8 R - E 1
1 21 21 1 1 1
_ 8 -
U ZI - E
_ 1 -
DD - P 8 _
- 0 1
H0/
- S C1 T A0DM D
7 _ 0553423924743340 _ 8 -
E1 0 - N 2 0 6 - I 4 -
O T7 D - U A8 P -
)
FS -
- S S
3 _ 31 O2OO321 1 0001 1 _ 6 - R 1
R D -
_ 1 - U U
E-1 -
- OND O =
E -
- HO H
P -
- ( IG D ;S -
- MTN RS'
- LCI OS
- AES CA
- CRS E
EL II L
RC
- FDM T
- O G
FYN -
N -
E O
OTO -
O -
- SLO U
II -
DI -
- DB DLT -
NT -
_ L _ OAS OIA -
IC -
- A - IIR E
IBV-UE -
E E
E E
U U
U UT - RRU T
RAE -
R -
NEN SES SUS NWN - O - EAO I
ETL -
I -
NNNEEESSSSSUUUNN - T - PVH S
PSE -
D -
2 =d 2
l
I 8
fo 7
6 1
1 1
7 8
0 _
L _ 8454363499440323 _ 1 _
/
6 _
A _
1 1 1 1 1 1 231 1 1 1 _ 2 _
T_
T _
__2 1
1 N
D O _
/
O T _
E_
8 I
0 T
S 4 _0000000000000000 _ 0 _
C P _
2_
)
d E
A _
e R
L _
u I
n D
i.
M_
4 _ 00000000001 00000 _ 1 _
D 0
2 _
N 6 _
t A
R _
9 _
(
I _
1 7
D D _
8 _31 1 E4 221 001 607701 4 _ 6 _
E E2 N _
)
1 1 2
_ 6 _
L B
P0 O _ H A
S3 I _ P 3 _
T_(
T 6
_ M 1 _
D0 C
N7 E _ D 2 __ 4753402698722374 _ 3 _
I8 R _ E 1
_7 U
ZI _ E 1 DD _ P 8 _
_ 0 H8/
_ S C1 T - _
A0DM_D 7 _ 1 697751 784551 034 _ 3 _
E1 0
N
_ 7 _
0 6
_I 4 _
0 T7 D _U A8 P _
)
GS _
_ S S
3 _ 0OO2OOO1 1 1 1 0001 1
_ 8 _ R R
_ U U
1 _
_ OND O-a
_ HO H
_ ( IG Dg
_ MTN R S;
_ LCI OS
_ AES CA
_ CRS E
EL II L
RC
_ FDM T
_ O G
FYN_
N _
EF D
OTO _
O _
_ SLO U
II _
DI _
_ DB DLT _
NT_
_ L _ OAS OIA _
IC _
_ A _ IIR IBV_
UE _
E E
E E
U U
U U_T _ RRU ET RAE R _
NEN SES SUS NUN _ O _ EAO I
ETL _
I _ NNNEEESSSSSUUUNN
_T
_ PVH S
PSE _
D _
5ht L
O 8
fo 8
6 1
1 1
7 8
0 _
L _ 4723073006478596 _
1
/
6 _
A _ 7264569686806034 _ 7 T_
T _ 1 23321 1 22223321 1 _ 9 1
N D _
O _
_ 3 1
T _
/
O E_
8 I
0 T
0 0 0 0 0 0 0 0 0 0 0 2 5 2 3 0 __
S 4 _
2
)
d C
P _
2 _
1 e
E A _
u R
L _
n I
i t
D M_
4 _ 1 81 61 20005529773 _ 7 i
. O (i
w D
0_
2 _
1 41
_ 1 N
6 _
1 A
R _
9 _
7 I _
1 _
D D_
E 8 _ 0681 568988031 486 _
1 E4 L
B E2 N _
)
1
_ 550722221 581 6823 _ 7 A
P0 O _ H 1
1 1
_ 9 T
S3 I _ P 3 _
6 T _ M 1 _
D0 C _
(
N7 E _ D 2 _ 9581 61 346731 3259 _ 3 I8 R _ E 1
_ 794628032331 9655 _ 0 U
ZI _ E 1 1 1 1 1 1 1 1 1
_ 7 DD _ P 8 _
_ 1 0
1 H0/
_ S C1 T A0DM_D 7 _ 6404935308653768 _ 7 E1 0
N
- _ 3599855825565333 _
1 0
6 _ I 4 _
1
_ 0 0
T7LD _ U
_ 1 A8LP _
b AS_
3 _ 8451 957468047300 _ 1 b S
R D_
1 1 1 1 1 1
1 1 _ 5 b bND
.E_
1 _
1 U
- m. E _
HO O-P I
H D tS_
EL I
L RC FDM T
b G
FYN _
N _
E 0
OTO _
O _
bLO V
II _
DI _
bB DLT_
NT _
_ L BAS OIA IC _
_ A hIR IBV_
UE _
E E
E E
U U
U U __ T E
RRU T
RAE R _
NEN SES SUS NUN O bAO
_ O I
ETL _
I _ NNNEEFSSSSSUUUNN _ T PVH S
PSE _
D _
~
E(
i I
i l
l-A TABLE 8.
PLANT V0GTLE DAILY AND MONTHLY PRECIPITATION
();
JANUARY 1,1987 THROUGH JUNE 30, 1987 January April F
January 2 through January 20 Missing April 3 0.18 January 26 0.36
' April 15 0.24 1
January 26 0.01 April 16 0.02 January 27 0.01 April 17 0.03 Total April 18 0.05 Total G inches l
February May February 2 0.24 May 4 0.33 February 5 0.16 May 12 1.16 February 6 1.66 May 14 0.32 February 7 0.64 May 15 0.03 February 16 1.83 Total T.N inches I
February 22 0.28 February 26 0.21
.C\\
February 27 2.05 V
February 28 2.42 Total 9.49 inches i
Marcn June March 1 0.37 June 2 0.37 Marcn 7 0.04 June 3 0.08 March 8 0.65 June 4 0.02 Maren 9 0.06 June 11 0.22 March 18 0.16 June 13 1.21 Maren 19 0.50 June 14 0.57 March 25 0.56 Jane 16 1.12 Maren 26 0.01 June 17 0.10 March 27.
0.10 June 18
- 0. 71 March 28 0.04 June 19 1.14 March 29 '
1.20 June 21 0.02 March 30 0.42 June 25 0.21 March 31 0.04 June 26 0.10 Total 4.1d inches Total W inches N1 4845A081287
I I
1 I
l n
LME M
~
33 v
H LLJ O
E
~
a "w
m g
a g
yg-O
~
.a E
.>h M
g n
er n
g-
=
=
u8 C
=
b
===.
' * ~,
N$ k mw m b
EEE5 gewE m$$
aaa WWWW w.mm 1
1 t.)
m =.
,e I
l 1l!!
l' O
a.
a.
D t
E 0 SR LF SNt sts e.
It I
WW
(
ESO 2
R I
DN I
W 7
m8 09 11 t
S N
ER L
LE A
TT i
I C
O 0A GR T
N VU t
Q E
T C
ND R
~
E AN P
LO PC E
^
.S 9
2 0
E R
U
^
G I
F H
f f
~
HHH5 fff.
f f f 2 1
$' t
- 5. t 552A t
371 H I
NH1T t
?
AAA HHHR TTTE T
SSSA SSSE e
EEER LLLG DDDD EEEE EEEE PPPP SSSS ssss t t t t IIII O
WWWW
., x,
~ E. D.
f l:l!
ll j
ll-i I:
se
\\
^
LmE &
=>
v MO e2
~
~
LaJ 35
~'
g
"!5 5
O
=8 5
3
=
=~
9 ss e
m-
.E I
g d
<t C,$
E
=k
===.
kkk e'
[
- 994_,
EEE5-8885
==
wmmw O
= =. i =.
_ O D
Et0 S R O F R SH t BE DD WW 1
E S
2 OR D
t N
I W
I 7
m 8 0 9 6 1 t
S t
t E R lA L E i
I C
T T O0 G
R T
A N
2 V U E
Q C
T R
N T i
E A S P
L R P
I F
9 4
l 0
i ERUG I
F Hf f
HHH5 ffF
/S,
f f t 2 1
552A5. N i,,
V.
X i
371 H NNNT v.
AAA HHHR TTTE T
'SSSA SSSE EEER LLLG DDDD EEEE EEEE PPPP SSSS SsBS DIED t
O WVWW
- + x,
~A-L
+
7 =',
' &, N
- f<.9g/-
w}
gg
- V
- 7. ;
i n-
- 0..
y]; y -
xtyg m,
}
,{j!.
1l [
( s; s; w.l yd.ya. v'
>. w I t ' _}!
- h..
- f<
~^
' I l ut <t f.j/n l-Q,, y. m 'I .P .'( .1% - t .j i l .( -( . (,, .,, n
- e p( l,., =
L. \\ () w,N.g g. '.r ( u +. z <.:. if' i
- f a
k fl I, .l} f _' j f J -, L s . U.i 'q, g g .'g.,; 6*. l , ' L,y [ *M,, h, zf a, /* Y ,,f':gf)g.'. gl,, ' )' (*.
- ?
a ./ q ' '). . 1 ,, j,., ' *
- w.
p / 1
- - a
,l9, wz +- } Q y, f 'i ,.t i,f f f,,,.M . _,' v] l E 2 o .l < $.,n-g E q v J < 1 i s., te ' 9 1 .\\.' - o< b;,, W a =, , g . e o 4*- 7,'/ O... Cz m O y f } .T ' tf 'h /'. p o. 4 m .?' l 1Me .,:,I 3" l ]. T ,,6Q i, n I i E ww sw n Q . g }h. r s r,m .g i
- s. rn EO B '?.
. C4 Z W _. g s t
- b gg W
wf (A t- / *. up N_ = s c i ] M >8' e L k \\ s i 1 l N
- w u
w mm .r f9 rw. g e ew g 'h hhh l 5555-MMMC 1 MM@ i ei WWW ad ad ad QQam WWWW W W W4'J EEEI s-3333 t, 4 +x+ e aw
I i l i O l o ^ E =. u (f)E M t k E-J" WN L/1 CO O Ch &M to O
- ZO gM M
w 2 8,5 e a e"C [ W M O n) am H r ( = y Z~ < CO H. J Cn W Ch. M b e eM we = m 1 CE: < D ::3 C.D Z
- = * <
W **) 4 i = t
===m m i A Q h s m c. g '~ EEE5 y/ wwwE mmm WWW .J.J.J OOOO WWWW WWWW O 4 +x* l I53 l
Geo' gia Power Corhoany r 333 Piedrnoot Avenue i Attanta, Georgia 30308 ) Telephone 404 526-6526 i l Mailing Address: ' Nst office Box 4545 ~ Atlanta. Georgia 30302 Georgia Power L T. Gucwa the scutnere sh;trc srtem l Manager Nuclear Safety l and Licensing SL-3061 0473m X7GJ17-V530 August' 28, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 i PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT-1 RELEASE REPORT Gentlemen: Pursuant. to the requirements of Plant Vogtle Unit 1 Technical Specification 6.8.1.4, please find enclosed the Semi-Annual Radioactive Effluent Release. Report for March 9,
- 1987, the date of initial criticality of the unit, through June 30, 1987.
Six copies are provided for your use.. Two copies of this report are being provided to the NRC - Region II office. Should you have any. questions in this regard, please contact this office at any time. Sincerely, pq%:= L. T. Gucwa l 1 JAE/im Enclosure c: (see next page) ] i T E-48 I% 1 J
deorgia PowerA ( U. S. Nuclear Regulatory Commission August 28,'1987 Page Two j i c: Georaia Power Comoany ~Mr. R. E. Conway (w/o enclosure) Mr. J. P. O'Reilly (w/o enclosure) Mr. G. Bockhold, Jr. Mr. J. F. D'Amico (w/o enclosure) Mr. C. H. Hayes-(w/o enclosure) GO-NORMS i Southern Comoany Services -1 Mr. R. A. Thomas (w/o enclosure) Mr. J. A. Bailey-(w/o enclosure) Shaw. Pittman. Potts & Trowbridaft Mr. B. H. Churchill, Attorney-at-Law (w/o enclosure) Troutman. Sanders. Lockerman & Ashmore Mr. A. M. Domby, Attorney-at-Law (w/o enclosure) U. S. Nuclear Regulatory Commissioll - Dr. J. N. Grace, Regional Administrator (2 copies) Ms. M. A. Miller, Licensing Project Manager, NRR (2 copies) { Mr. J._ F. Rogge,-Senior Resident Inspector-Operations, Vogtle I Georcians Aaainst Nuclear Enerav Mr. D. Feig Ms. C. Stangler (w/o enclosure) State of Georaia Mr. J. Setser, DNR American Nuclear Insurers Mr. L. Cross 1 l 0473m l 1 l rwis}}