ML20077M503
| ML20077M503 | |
| Person / Time | |
|---|---|
| Site: | Indian Point |
| Issue date: | 08/30/1983 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML093451373 | List: |
| References | |
| NUDOCS 8309120354 | |
| Download: ML20077M503 (31) | |
Text
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Effluent and Waste Disposal Semi-Annual Report January 1 - June 30, 1983 Facility Indian Point 3 Licensee New York Power Authority This information is provided in accordance with the requirements of Regulatory Guide 1.21.
The numbered sections of this report reference corresponding sections Of the subject Regulatory Guide, pages 1.21-10 to 12.
A.
Supplemental Information 1.
Regulatory Limits Indian Point Unit 3 is presently subject to limits on radioactive waste releases that are set forth in sections 2.4 and 3.4 of Appendix B to Docket
- 50-286 entitled " Environmental Technical Specification Requirements for Once-Through Cooling"- (T.S.). The percentages of technical specification limits reported in Table 1A are the percent of one half of the quarterly limits specified in the ETSR.
2.
Maximum Permissible Concentrations a.
Fission and Activation Gases The quarterly limits for those specifications stated in the ETSR have been used to calculate the percent of technical specification limit.
The K, L, M, N value3 for vent release points are based on the isotopic concentrations reported in Table 1C and on the individual isotopic K, L, M, N values in Table 2.4-5 of the ETSR.
The percent of permissible discharges reported for IP-3 are based on assuming that IP-3 can use only 50% of the T.S. limits measured in Curies / second and detailed in Memorandum of Understanding between NYPA and Con Edison.
b&c. Iodines & Particulates The quarterly limits for iodine-131 and particulates with half-lives greater than 8 daya in section 2.4.2.b.3 of the'ETSR have been used as the maximum permissible concentration for the purpose of calculating the percent of technical specification limit. Again only one half of the permissible lbmit is used for IP-3 as stated in 2(a) above.
8309120354 830830 PDR ADOCK 05000286 R
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i b&c Iodines and Particulates Iodine-131 and particulate releases are quantified by collecting a continuous sample of ventilation air on a potassium-iodide impregnated activated charcoal cartridge and a glass-fiber filter paper.
These samples are chang-ed weekly as required in Table 2.4-2 of the ETSR and the concentration of isotopes found by analysis of these samples is combined with the volume of air discharged during the-sampling period to calculate the amount of activity discharged.
For other iodine isotopes the ratio of each isotope to iodine-131 is determined for a monthly 24-hour sample.
These ratios are then used, along with the total monthly discharge of iodine-131, to calculate the amount of these other isotopes discharged in this monthly period.
d.
Liquid Effl'uents A proportional composite sample of each batch discharge is taken and an isotopic analysis is performed in com-pliance with requirements specified in Table 2.4-1 of the ETSR. This isotopic concentration data is combined with information on volume discharged to determine the amount of each isotope discharged in this period.
Samples of continuous discharges have been taken and analyzed in compliance with Table 2.4-1 of the ETSR.
This concentration data is combined with the volume discharged to calculate the total activity discharged.
i
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Liquid Effluents All liquid discharges from Indian Point are made through a common discharge canal with a minimum of 100,000 gpm dilution water. The isotopic content, excluding tritium and dissolved noble gas, of continuous and batch mode discharges from the site for the third and fourth calendar quarters have been added and a weighted average fraction of MPC has been calculated for this isotopic mixture as described in 10 CFR 20.
The percent of applicable limit reported is the percent of MPC concentration of the time averaged diluted concentration for the calendar quarter.
The tritium limit has been established in the same manner as the other isotopes in liquid effluents.
Since there is no limit stated for dissolved noble gases in 10 CFR 20, we have established a lLnit of 2.55 x 10-3 uCi/cc based on a dose calculation that has been provided to USNRC inspectors.
3.
Average Energy The average energy (E) of the radionuclide mixture in releases of fission and activation gases was as follows:
1st Quarter:
E
= 2.23 E-3 MeV/ dis
}E
= 2.28 E-1 MeV/ dis y
B 2nd Quarter:
E
= 4.62 E-2 MeV/ dis E
= 1.50 E-1 MeV/ dis Y
B 4.
Measurements and Approximations of Total Radioactivity a.
Fission and Activation Gases Analysis of effluent gases has been performed in compliance with the requirements of Table 2.4-2 of the ETSR.
In the case of isolated tanks (batch release) the total activity discharged is based on an isotopic analysis of each batch and the volume of gas in the batch corrected to standard temperature and pressure.
Vapor containment purge and pressure relief discharges have been treated as batch releases. At least one complete isotopic concen-tration analysis of containment air is performed per month and this is applied to a gross analysis of the ventilation air performed prior to each pressure relief.
Isotopic analyses for each vapor containment purge are taken prior to and during the purge. This in-formation is combined with the volume of air in each discharge to calculate the radionuclide composition of these discharges.
The continuous discharges are based on weekly samples of ventilation air for isotopic content. This information is combined with total air volume discharged and the process radiation monitor readings to determine the continuous discharges.
a a
e 5.
Batch Releases a.
Liquid 1983 1st Quarter 2nd Quhrter Number of Batch Releases 40 80 Total Time Period Batch Releases (Min.)
8.40E+3 1.65E+4 Maximum 5.05E+2 9.05E+2 Average 2.10E+2 2.06E+2 Minimum 1.05E+2 2.00E+1 Average Stream Flow (cfs) 2.60E+4 4.43E+4 b.
Gaseous Number of Batch Releases O
20 Total Time Period Batch Releases (Min.)
N/A 5.13E+3 Maximum N/A 2.76E+3 Average N/A 2.57E+2 Minimum N/A 3.00E+0 6.
Abnormal Releases a.
Liquid None b.
Gaseous None l
l Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI - ANNUAL REPORT B. GASEGUS EFFLUENTS FIRST AND SECOND QUARTERS, 1983
f 4
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TABLE lA EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1983)
GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QUARTER QUARTER EST. TOTAL 1
2 ERROR %
A. Fission & Activation Gases
- 1. Total. release Ci 2.95 E+1
'5.30 E+2 2.50 E+1
- 2. Average release rate for period uCi/sec 3.79 EO 6.74 E+1
- 3. Percent of. technical specification 1.91 E-1 1.83 E+0 limit.
B. Iodines
- 1. Total iodine -131 Ci
<2.44 E-5 3.28 E-5' 2.50 E+1
- 2. Average release rate for period uCi/sec
<3.14 E-6 4.17 E-6
- 3. Percent of technical specification 5.73 E-4 4.36 E-3 limit.
J
.C. Particulates
- 1. Particulates with half-lives > 8 days Ci 5.91 E-6 4.55 E-5 2.50 E+1 2.' Average release rate for period uCi/sec 7.60 E-7 5.79 E-6
- 3. Percent of technical specification limit 5.73 E-4 4.36 E-3
- 4. Gross alpha radioactivity Ci
<2.44 E-7
<3.16 E-7 D. Tritium 1.' Total release Ci 1.42 E-1 3.51 E-1 2.50 EFl
- 2. Average release rate for period uCi/sec 1.83 E-2 4.47 E-2
- 3. Percent of technical specification limit NA NA J
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TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1983)
GASEOUS EFFLUENTS-GROUND RELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter
- 1. Fission Gases Krypton (Kr) 85 Ci 2.95 E+1 7.03 E-2 Krypton (Kr) 85m Ci 6.89 E-4 Krypton (Kr) 87 Ci Kryptnn (Fr) nn Ci Xenon (Xe) 133 Ci 4.71 E+2 5.74 E+1 Xenon (Xe) 133m Ci 1.20 E+O Xenon (Xe) 135 Ci 5.05 E-1 Xenon (Xe) 135m Ci Xenon (Xe) 138 Ci Xenon (Xe) 131m Ci Unidentified Ci TOTAL FOR PEPIOD Ci 2.95 E+1 4.71 E+2 5.93 E+1*
< 2.44 E-5 3,28 E-5 iodine (I) 133 Ci Iodine (I) 135 Ci TOTAL FOR PERIOD Ci
<2.44 E-5 3.28 E-5
e e
TABLE 1C -FAGE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL PEPORT (1983)
CASEOUS EFFLUENTS-GROUND RELEASES C0NTINUOUS MODE BATCH MODE Nuclides Released Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter
- 3. Particulates Antimony (Sb) 125 Ci Barium-Lanthanum 140 Ci 2.49 E-7 Cadmium (Cd) 109 Ci 7.20 E-7 2.79 E-6 Cerium (Ce) 139 Ci Cerium (Ce) 141 Ci Cerium (Ce) 144 Ci 1.01 E-6 Cesium (Cs) 134 Ci Cesium (Cs) 137 Ci 3.11 E-7 2.88 E-7 Cobalt (Co) 57 Ci Cobalt (Co) 58 Ci Cobalt (Co) 60 Ci 1.39 E-7 2.17 E-6 Iron (Fe) 55 Ci 3.48 E-6 6.02 E-6 Manganese (Mn) 54 C1 Mercury (Hg) 203 Ci Neptunium (Np) 239 Ci Nickel (Ni) 63 Ci Strontium (Sr) 85 Ci Strontium (Sr) 89 Ci Strontium (Sr) 90 Ci Tin (Sn) 113 C1 Chromium (Cr) 51 Ci 1.46 E-6 i
others
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a Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI - ANNUAL REPORT C. LIQUID EFFLUENTS FIRST AND SECOND QUARTERS, 1983 1
r TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1983)
LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QUARTER QUARTER EST. TOTAL 1
2 ERROR %
A. Plssion and activation products
- 1. Total release (not including tritium, gases, alpha)
Ci 6.04 E-2 1.99 E-1 2.50 E+1
- 2. Average diluted concentration during period uCi/ml 4.07 E-lO 6.14 E-10
- 3. Percent of applicable ILuit 4.75 E-4 2.30 E-3 B. Tritium
- 1. Total release Ci 6.08 E-1 2.16 E+1 2.50 E+1
- 2. Average diluted concentration during.
-period uCi/ml 4.08 E-9 6.67 E-8
- 3. Percent of applicable limit
.l.36 E-4 2.-22 E-3
~C. Dissolved and entrained gases
- 1. Total release Ci O.00 EO 7.16 E-2 2.50 E+1
- 2. Average diluted concentration during period uci/ml 0.00 EO 2.21 E-10
- 3. percent of applicable limit 0.00 EO 8.67 E-6 D. Gross alpha radioactivity
- 1. Total release Ci
< l.18 E-4 < 5.73 E-4 2.50 E+1 E. Volume of waste release (prior to dilution) liters 1.56 E+6 2.84 E+6 1.00 E+1 l
F. Volume of ' dilution water used during period liters 1.49 E+11 3.24 E+11 1.00 E+1 1
I i'
e-e TABLE 2B e
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LIQUID EFFLUENT AND WASTE DISPOSAL SEMI-AimUAL REPORT Continuous Mode Batch Mode NUCLIDES UNIT lst QUARTER 2nd QUARTER lst QUARTER 2nd QUARTER
. Antimony (Sb) 122 Ci 2.21 E-4 Antimony (Sb) 124
-Ci Antimony (Sb) 125 Ci 1.35 E-3 6.81 E-4 2.59 E-3 Barium / Lanthanum 140 Ci.
1.69 E-3 Barium (Ba) 133 C1 1.51 E-5 Cadmium (Cd) 109 Ci 6.31 E-5
~2.56 E-5 7.12 E-5 Cerium (Ce) 139 C1 4.35 E-6 4.40 E-6 Cerium (Ce) 141 Ci 3.85 E-6 3.11 E-6 3.04 E-4 Cerium (Ce) 144 Ci 2.92 E-5 2.25 E-5 7.48 E-6 Cesium (Cs) 134 Ci 9.40 E-5 3.52 E-4 4.98 E-3 Cesium (Cs) 136 Ci 5.05 E-4 Cesium' (Cs) 137 Ci 2.77 E-4 9.33 E-4 1.01 E-2 Cesium (Cs) 138 Ci 6.18 E-5
~ Chromium (Cr) 51 Ci 2.22 E-3 Cobalt (Co). 57 Ci 4.75 E-5 3.54 E-5 1.96 E-4 Cobalt
.(Co) 58 Ci 2.97 E-3 3.56 E-3 3.00 E-3 Cobalt (Co) 60 Ci 2.73 E-2 1.26 E-2 4.77 E-2 Iodine (I) 131 Ci 8.12 E-4 Iodine (I) 132 Ci r
Iodine (I) 133 Ci i
Iodine (I) 134 Ci Iodine (I) 135 Ci Iron (Fe) 55 Ci 3.84 E-2 6.76 E-2 Iron (Fe) 59 Ci 6.26 E-4 Mercury (Hg) 203 Ci 9.01 E-6 1.24 E-5 Neptunium (Np) 239-Ci 1.55 E-5 Manganese (Kn) 154 Ci 3.91 E-3 7.97 E-4 2.75 E-3
. Manganese (Mn)- 56 C1
~. - - - _
TABLE'2B - Page 2 e
Continuous Mode Batch Mode NUCLIDES UNIT 1st QUARTER 2nd QUARTER lst-QUARTER 2nd QUARTER Molybdenum (Mo) 99 Ci 4.58 E-3 Nickel (Ni) 63 Ci 2.59 E-3 2.93 E-3 Nickel (Ni) 65 Ci
' Niobium (Nb) 94 Ci Niobium (Nb) 97 C1 1.34 E-3 Phosphorus (P) 32 Ci Radium (Ra) 226 Ci Rubidium (Rb) 88 Ci Rhodium (Rh) 106 C1 1.25 E-3
~
Ruthenium (Ru) 103 Ci 3.41 E-6 Silver (Ag) 110m C1 2.17 E-4 5.31 E-3 Sodium (Na) 24 Ci Strontium (Sr) 85 C1 1.30 E-5 3.12 E-5 Strontium (Sr) 89 Ci-7:16 E-6 Strontium (Sr) 90 C1 1.86 E-6
-Strontium (Sr) 91 Ci Strontium (Sr) 92 Ci 9.74 E-6 Technetium (Tc) 99m Ci 4.05 E-4 Tin
-(Sn) 113 Ci 9.15 E-6 4.54 E-5 Tungsten (W) 187 Ci Yttrium (Y) 88 Ci j
Yttrium (Y) 91m Ci 5.11 E-6 Yttrium (Y) 92 Ci Zine (Zn) 65-Ci 5.68 E-4 Zirconium / Niobium 95 Ci 3.86 E-5 1.40 E-3 Zirconium (Zr) 97 Ci TOTAL FOR PERIOD Ci 3.61 E-2 6.04 E-2 1.63 E-1
TABLE 2B - Page 3 Continuous Mode Batch Mode NUCLIDES UNIT lst QUARTER 2nd QUARTER lst Quarter
?rld QUARTER Xenon Xe 133 Ci 0.00 E0 1.82 E-5 0.00 EO 6.83 E-2 Xenon Xe 135 Ci 0.00 EO 9.67 E-6 0.00 EO 3.29 E-3 L
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r Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI - ANNUAL REPORT D. SOLID WASTE FIRST AND SECOND QUARTERS, 1983
TABLE 3 f
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS i
First and Second Quarter 1983 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
I
- 1. Type of waste
. Unit 6-month Est. Total Period Error, %
- a. Spent resins, filter sludges. evaporator nf 1.82 E 1 bottoms, etc.
Ci 7.04 E 2 1.00 E2
- b. Dry compressible waste, contaminated m'
2,13 E 2 equip, etc.
Ci 2.62 E O 1.00 E2
- c. Irradiated components, control m'
O.
E rods, etc.
Ci o.
E E
3
- d. Other (describe) m 0
E Ci 0
E E
- 2. Estimate of major nuclide composition (by type of waste)
E I
E E-E 3.
Solid Waste Disposition Number of Shipments Mode of Transportation Destination j
10 Truck Barnwell, South Carolina 4
Truck Richland, Washington B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination NONE
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l Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI - ANNUAL REPORT E. RADIOLOGIAL IMPACT ON MAN FIRST AND SECOND QUARTERS, 1983
Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI - ANNUAL REPORT F. METEOROLOGICAL DATA FIRST AND SECOND QUARTERS, 1983 f
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me*****tMC FORMAT FOR NUREG 1.210:* men 3
IP DATA JAN-MAR 1983 10 METER WIm SPEED & DIR. WITH 61-10 METER DELTA T PASQUILL CLASS D
..e me..h
.eun
-.-*e m
+-e WIM DIIECTION WIND SPEEC (MPHI 01-03
.04-07 08-12 13-18 19-24
>24 TOTAL H
24.
85.
48.
10.
D.
O.
167.
INE 32.
161.
65.
1.
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259.
NE
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4.
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o TOTAL 177.
537.
276.
33.
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D.
1023.
CALM 0.
.m T!TAL HOURS IN t10 NTH = 2160
. - _. ~... _
TATAL DATA HOURS TOTAL + CALM w*
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G memamenHRC FORMAT FOR HUREG 1.21manese IP DATA JAN-MAR 1983 10 METER WIND SPEED & DIR. WITH 61-10 METER DELTA T PASQUILL CLASS E WIte DIRECTION WIND SPEED (MPH) 01-03 04-07 08-12 13-18 19-24
>24 TOTAL H
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37.
5.
15.
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94.
tNE 57.
58.
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E 21.
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