ML19317E948
| ML19317E948 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/23/1972 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19317E930 | List: |
| References | |
| NUDOCS 8001070741 | |
| Download: ML19317E948 (8) | |
Text
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bM 3.16 REI2ASE OF LIQUID RADICACTIVE WASTE Applicability:
Applies to the controlled release of all liquid waste discharged from the plant which may contain radioactive materials.
Ob jective :
To establish conditions for the release of liquid waste containing radioactive materials and to assure that all such releases are within the concentration limits specified in 10 CFR Part 20.
In addition, to assure that the releases of radioactive material in liquid wastes (above background) to unrestricted areas meet the low as practicable concept, the following liquid release objectives shall apply:
a.
The annual total quantity of radioactive materials in liquid wasta, excluding tritium and dissolved gases, shall be less than 5 curies; b.
The annual average concentration of radioactive materials in liquid wasta, prior to dilution in Bailey Cove, excluding tritium and dissolved gases, shall not exceed 2 x 10-8 uC1/ml; c.
The annual average concentration of tritium in liquid waste, prior 'to dilutien~in' Bailey Cove,'shall not exceed 5 x 10-6 pCi/ml; d.
The annual average concentration of dissolved gases in liquid waste, prior to dilution in Bailey Cove, shall not exceed 2 x 10-6 pCL/ml.
Specific'ations:
A.
Release Quantities and Concentrations of Radioactive Materials in Liquid Waste 1.
If the experienced release of radioactive materials in liquid wastes, when averaged over a calendar quarter, is such that these quantities if continued at the same release rate for a year would exceed twice the annual objectives the licensee will:
a.
make an investigation to identify the causes for such release rates; b.
define and initiate a program of action to reduce such release rates to the design levels, and; l
c.
describe these actions in a report to the Cocunission l
within 30 days.
2.
If the experienced release of radioactive material in liquid waste, when averaged over a calendar quarter, is such that these quantities if continued at the same l
3.16-1 8001070 [
1 1
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release rate for a year would exceed eight times the annual objectives, the licensee shall define and initiate a program of action to assure that such release rates are reduced, and shall submit a report to the Commission within 7 days describing the causes for such release rates and the course of action taken to reduce them.
3.
The rate of release of radioactive materials in liquid waste from the plant shall be controlled such that the instantaneous concentration of radioactivity in liquid waste does not exceed the values listed in 10 CFR Part 20, Appendix 3, Table II, Column 2.
B.
Treatment and Monitoring 1.
The equipment installed in the liquid radioactive waste system shall be maintained and operated with the intent i
uof keeping releases within the objtectives of these Specifications.
2.
At least one service water pump shall be in operation when liquid radioactive wastes are being released.
3.
Liquid waste discharged from the test tanks shall be continuously monitored during release.
The liquid affluent monitor reading shall be compared with the expected reading of each discharge bat h.
The monitor shall be tested daily and calibrated at refueling intervals.
The calibration procedure shall consist of exposing the detector to a referenced calibration source in a controlled, reproducible geometry.
The sources and geometry shall be referenced to the original monitor calibration which provides the applicable calibration curves.
4.
The effluent control monitor shall be set to alarm and automatically close the waste discharge valve such that j
the requirements of the specification are met.
In the event of a malfunction in the monitor, the alarm shall i
sound and automatically close the waste discharge valve.
5.
Steam generator blowdown shall be continuously monitored, except that during periods when the monitor is not cperating, daily grab samples shall be taken.
C.
Sampling and Analvsis In addition to the above continuous monitoring requirements, liquid radioactive waste sampling and activity analysis shall be performed in accordance with Table 3.16-1.
Records shall be maintained and reports of the sampling and analysis results shall be si.-uitted in accordance with Sections 5.6 and 5.7 of these Specifications.
3.16-2
Basis:
It is expected that the releases of radioactive materials in liquid waste will be kept within the design objective levels and will not exceed the concentration limits specified in 10 CFR Part 20.
These levels provide reasonable assurance that the resulting annual exposure to the whole body or any organ of an individual will not exceed 5 millirems per year.
At the same time, the licensee is permitted the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentration ILmits specified in 10 CFR Part 20.
It is expected that using this operational flexibility under unusual operating conditions, the licensee shall exert every effort te keep levels of radioactive material in liquid wastes s; low as practicable and that annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR Part 20.
The design objectives have been developed taking into account a combination of variables including fuel failures, primary system leakage, primary-to-secondary leakage and the performance of the various waste treatment systems.
The actual magnitude of these parameters are as follows:
a.
Maximum expected reactor coolant corrosion product concen-trations; b.
Reactor coolant fission product concentration corresponding to 0.1% fuel cladding defects; Steam generator primary-to-secondary leak rate of 0.01 gpm; c.
d.
Hydrogenated liquid waste generation rate of L.75 spm; Aerated liquid waste generation rate of 0.475 sym; e.
f.
Steam generator blowdown rate of 5 gym, of which 3 gym is diverted to the waste disposal system for processing before discharge; g.
Decontamination factor of 104 for all radionuclides except tritium for the boron recovery and waste disposal evaporators; h.
Decontamination factor of 10 for Cs, Sr, Mo and Y for cesium domineralizer.
3.16-3
The application of the above estimates results in the radionuclide discharge concentrations and rates shown in Table 3.16-2.
Also given in this table are the radionuclide concentrations in the reactor coolant and the secondary coolant, which are the " source terms" for releases from the primary and secondary systems, respectively.
Liquid radioactive waste is mixed with service water in the plant discharge system prior to release. With four circulating water pumps in operation, the rated capacity of the system is 400,000 gpm.
This is equivalent to a dilution multiple of 2.5 x 10-6 min / gal x the discharge rate in gal / min. Liquid radioactive waste from the waste treatment system is collected and stored in tanks until a quantity sufficient for processing has accumulated.
The processed liquid waste is discharged through a recorder controller which provides a measure and control of volume of liquid released.
The volume discharged and the analysis of the proportional composite sample provide the basis for reporting the quantity and concentration of activity released.
The operating manual will identify all equipment installed in the liquid waste handling and treatment systems and will specify detailed procedures for operating and maintaining this equipment.
The low as practicable liquid release objectives expressed in this Specification are based on the guidelines contained in the proposed Appendix I of 10 CFR 50.
Since these guidelines have not been adopted as yet, the release objectives of this Specification will be reviewed at the time Appendix I becomes a regulation to assure that this Specification is based upon the guidelines contained therein.
References:
FSAR, Section 9.14, Waste Disposal System FSAR, Section 11.2.2, Process Radiation Monitoring System Tech Spec Sections 5.6 and 5.7, Records and Reporting of Radioactive Releases to Environment l
l 3.16-4 1
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Table 3.16-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS A.
Test Tank Releases Type of Sensitivity (5)of Samplins ?recuency Activity Analysis Analysis Each Batch Gross d.[
10-7 ACi/mi One Batch / Month Dissolved Noble Gases 10-4 'A41/ml Weekly Proportional Ba-140, La-140, I-131 10-6'gi/ml Composite (1)
Monthly Proportional Gamma Emitters 10-6 Aci/ml(2)
Composite (1)
H-3 10-5 'Mi/ml Gross o<
10- 7 'l4C1/mi Quarterly Pro ortional Sr-89, Sr-90 10-6pi/milo)
Composite ( )
3.
Secondary Plant Blowdown and Leakage Releases (3)
Type of Sensitivity (5)of Samplina Frecuency Activity Analysis Analysis Weekly Gross & I 10-7 s.Ci/mi Ba-140, La-140 I-131 10-6' uci/mi One Sample / Month Dissolved Noble Gases 10-4 'uC1/mi Monthly Proportional Gamma Emitters 10-O'g i/m1(2)
Composite (4)
H' 10-3'E i/mi Grt s G 10- 7 'A C1/mi QuarterlyProgortional Sr-89, Sr-90
'.0-8/ C1/ml(o)
Composite ( )
NOTES:
5 }A proportional sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant.
( }For certain mixtures of 3amma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations.
Under these circumstances, it will be more appropriate to calculate the concen-trations of such radionuclides using observed ratios with those radionuclides which are measureable.
3.16-5 i
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I ) Secondary plant blowdown and secondary plant leakage are each subject to the sampling and analysis requirements contained in Part B of Table 3.16-1.
I Since these potential sources of liquid radioactive waste are discharged on a continuous rather than batch basis, the volume of liquid to be used as a basis for obtaining proportional samples from secondary blowdown and leakage is that amount discharged over the period of one week.
( }These activity analyses sensitivities are based on the projected capabilities of laboratory instrumentation and techniques to be employed by Maine Yankee.
In order to assure that actual Maine Yankee operating experience is utilized, a reevaluation will be performed within 2 years of inicial full power operation of the plant to determine whether there sensitivities should be revised.
Ib)One quarterly proportional composito sample will be collected and analyzed for Sr-89 and Sr-90.
The proportional inputs to this sample will be from the test tank, secondary blowdown, and secondary leakags releases.
i i
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i Table 3 16-2 RADIO *!UCLIDE SOURCE TEIMS AND DISCHAf0ES Beactor Coolant Steam Generator.
Plant Discharge Fraction of Concentration Blowdown Concentration t' - atratica 10 CFR 20 Arumal Ehlease Isotops (pci/ml e 70*F)
(sci /=1 e 70*F)
(pCi/ml)
MFC,,
(Ci/ year) 1-131 2.99-la h.22-h 2.16-9 7.20-3 1.4 I-132 1.12-1 6.25-6 8.88-11 1.n-5 6.73-2 I-133 5.02-1 2.08-h 1.25-9 1.25-3 9.h9-1 1-13h 7.55-2 1.57-6 h 73-n 2.37-6 3.58-2 I-13 5 2.80-1 h.33-5 3.52-10 8.80-5 2.67-1 ar-89 3 11-h 5.82-7 p.81-12 9.37-8 2.13-3 sr-90 1.89-5 3.77-8 1.82-13 6.07-7 1 38-h Sr-91 1.97-h h.25-8 2.32-13 h.%-7 1.76-h Y-90 6.13-5 5.%-8 2.68-13 13h-8 2.03-h Y-91 2.h9-3 h.70-6 2.27-n 7.57-7 1.72-2 Mo-99 1.18-1 1.06-h 5.21-10 1.30-5 3.95-1 24-103 1.96-h 3.61-7 1.82-12 2.28-8 1.38-3 21-106 1.82-5 3.60-8 1.81-13 1.81-8 1.37-h Te-129 2.66-3 7.2h-8 1.7h-12 2.18-9 1 32-3 E
Te-132 2.51-2 2.h8-5 1 31-10 h.37-5 9.92-2 L
Ba-lho h.37-h 6.92-7 3 51-12 1.76-7 2.66-3 La-lho.
h.17-h 2.79-7 1.A-12 7.70-8 1.17-3 ca-13h 5.19-2 9.93-5 h.79-10 1.60-h 3.63-1 cs-136 1.75-3 2.78-6 1 58-12 2.63 -8 1.20-3 ca-137 1.h9-1 2.97-h 1.hh-9 7.20-5 1.09 cr-51 5.25-3 9 39-6 h.7h-u 1.58-5 3.52-2 un-%
3.80-5 7.50-8 3.76-13 3.76-9 2.85-h i
Fe-59 2.9h-5 5.h6-8 2 75-13 5.50-9 2.OB-h co-58 6.h3-3 1.26-5 6.32-n 7.02-7 h.79-2 co-60 7.25-h 1.hh-6 7.22-12 2.k1-7 5 h7-3 zr-95 1.29-6 2.h5-9 1.23-lh 2.05-10 9 33-6 T=6.62x10-9
(= 8.86 x 10-3
$= 5.02 H-3 2.3-2 h.59-5 1.22-7 h.07-5 92 3
- 2 99 2.99 x 10-1
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