ML19325C548
| ML19325C548 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/10/1989 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML19325C544 | List: |
| References | |
| NUDOCS 8910170038 | |
| Download: ML19325C548 (2) | |
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N TABL'E 2.3-1 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS (4. 5)-
.A.
Monitor Tank Releases Type of Detectable Samplina Frecuency Activity Analysis Concentration (3)
Each Batch Individual Gamma 5 x 10-7 uCi/ml (2)
H-3 10-5 uC1/mi Monthly Composite (1)
Gross Alpha 10-7 uC1/ml Sr-90 5 x 10-8 uCi/mi NOTES (1) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant.
(2) For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near this sensitivity limit when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using measured ratios with those radionuclides which are routinely identified and measured.
(3) The detectability limits for radioactivity analysis are baseo on the technical feasibility and on the potential significance in the environment of the quantities released.
For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported.
(4) The results of these analyses should be used as the basis for recording and reporting the quantities of radioactive material released in liquid effluents during the sampling period.
In estimating releases for a period when analyses were not performed, the average of the two aojacent data points spanning this period should be used. Such estimates should be included in the effluent records and reports; however, they should be clearly identified as estimates, and the method used to obtain these data should be described.
(5) Deviations from the sampling / analysis regime will be noted in the report specified in Section 5.6.1.
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l THREE MILE ISLAND - UNIT 2 2-4 AMENDMFNT t
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891017003s 891010 ADOCK 050 g 0 DR
g
-f b s
1-V.
L RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS (5) 4 i
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' SAMPLE TYPE SAMPLING FRE0VENCY TYPE OF ACTIVITY ANALYSIS DETECTABLE CONCENTRATION (1)
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, Maste Gas Decay Tank Release Gas Each Tank H-3 10-6 uCi/cc' Release Individual Gamma Emitters 10-4 uC1/cc (2) 1 Reactor _Buildino Purae Releases Gas Each Purge-H-3 10-6 uC1/cc Individual Gamma Emitters
'10-4 uC1/cc (2)
Con'enser Vacuum Pump Releases d
Gas Monthly H-3 10-6 uC1/cc Monthly (3)
-Individual Gamma Emitters 10-4 uC1/cc (2).
Unit Exhaust Vent Releast Points Gas Monthly (4)
H-3 10-6 uCI/cc Individual Gr.mma Emitters 10-4 uC)/cc (2) o Charcoal Weekly (6) 1-131, I-133, I-135 10-12 uC)/cc s.
Particulates-Weekly Individual Gamma Emitters 10-10 UC1/cc (2)
Monthly Composite Sr-90 10-II uC1/cc Monthly Composite Gross Alpha Emitters 10-11 uC1/cc d
(1)
The above detectability limits are based on technical feasibility and on the
-potential significance in the environment of the quantitles released.
For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the state limits, they should also be reported.
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THREE MILE ISLAND - UNIT 2 2-11 AMENDMENT H
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