ML19317D234
| ML19317D234 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/09/1978 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19317D233 | List: |
| References | |
| NUDOCS 7911190616 | |
| Download: ML19317D234 (3) | |
Text
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O 3.9.3 The rate of release of radioactive materials in liquid waste from the station shall be controlled such that the instantaneous concentrations of radioactivity in liquid waste upon release from the Restricted Area, does not exceed the values listed in 10CFR20, Appendix B, Table II, Column 2.
3.9.4 The equipment installed in the liquid radioactive waste system shall be maintained and operated to process liquids as necessary prior _to their l discharge in order to limit the activity, excluding tritium and dissolved noble gases, released during any calendar quarter to 1.25 curies or less per unit.
3.9.5 As far as practicable, the releases of liquid waste shall be co-ordinated with the operation of the Keowee hydro unit.
3.9.6 Liquid waste discharged from the liquid waste disposal system shall be continuously monitored during release. The liquid effluent control monitor reading shall be compared with the expected reading of each discharge batch. The monitor shall be tested daily or prior to releases and calibrated at refueling intervals.
The calibration procedure shall consist of exposing the detector to a referenced calibration 9.-urce in a controlled, reproducible geometry. The sources and geometry shall be referenced to the original monitor calibration which provides the applicable cali-bration curves.
3.9.7 The effluent control monitor shall be set to alarm and automatically close the waste discharge valve such that the limits specified in 10CFR20 are net.
In the event that the effluent control monitor is inoperable or cannot be calibrated to perform this function, redundant valve line-up check of the ef fluent pathway and redundant sample analyses will be performed prior to each liquid effluent release to assure that prescribed release limits are not exceeded. _
t 3.9.8 In addition to the continuous monitoring requirements, liquid radio-l active waste sampling and activity analysis shall be performed in accordance with Table 4.1.3. Records shall be maintained and reports of the sampling and analysis shall be submitted in accordance with Section 6.6 of these Technical Specifications.
Bases It is expected that the releases of radioactive materials and liquid wastes will be kept within the design objective levels and will not exceed the concentration linics specified in 10CFR20. These levels provide the reasonable assurance that the resulting annual exposure to the whole body or any in-l l dividual body organ will not exceed 5 millires 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 i
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temporarily result in releases higher than design objective levels but still within the concentration limits specified in 10CFR20. It is expected that when using this operational flexibility under unusual operating conditions, the licensee shall exert every effort to keep the levels of radioactive materials and liquid wastes as low as reasonably achievable and that annual l releases will not exceed a small fraction of the annual average concentration limits specified in 10CFR20.
The anticipated annual releases from the three Oconee units 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 is as follows:
- a. Maximum expected reactor coolant corrosion product concentrations.
- b. Reactor coolant fission product concentration corresponding to 0.25 percent fuel cladding defects.
- c. Steam generator primary-to-secondary leakage rate of 20 gpd.
- d. 255,160 gallons per year processed by the waste disposal system in a 30-day hold-up.
- e. 1,060,800 gallons per year processed by the reactor coolant bleed treat-ment system.
- f. A decontamination factor of 410 for all radionuclides except tritium for the coolant bleed and waste evaporators and a decontamination factor of 10 for the demineralizers except for tritium which had an assumed decontanination factor of 1 for evaporation-demineralization.
A decontamination factor
- g. NoryvalbydemineralizationforCs,Mo,andY.
of 10 was used for the evaporation of iodine.
- h. The decay time of the reactor coolant bleed system was 30 days.
The application of the above estimates results in the radionuclide discharge concentrations and rates shown in Table 111-12 of the " Final Environmental3."
Statement Related to Operation of Oconee Nuclear Station Units 1, 2, and These concentrations are based on an annual average flow in the Keovee River of 1,100 cfs.
Operating procedures will identify all equipment installed in the liquid waste handling and treatment systems and will specify detailed procedures for operating and maintaining this equipment.
l The as low as reasonably achievable liquid release objectives expressed in this specification are based on the guidelines contained in the proposed Appendix I of 10CFR50. 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.
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3 . 9, RELEASE OF LIQUID RADI0 ACTIVE WASTE Applicability Applies to the controlled release of ail liquid waste discharged from the station which may contain radioactive materials.
Obiective To establish conditions for the release of liquid waste containing radio-active materials and to assure that all such releases are within the concen-tration ibnits specified in 10 C7R 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 waste, excluding tritium and dissolved gases, shall be less than 5 curies per unit;
- b. The annual average concentration of radioactive materials in liquid waste, upon release from the Restricted Area, excluding tritium and dissolved noble gases, shall not exceed 2 x 10-8 pC1/ml;
- c. The annual average concentration of tritium in liquid wasta, upon release from the Restricted Area, shall not exceed 5 x 10-6 pCi/ml; fh d. The annual average concentration of dissolved gases in liquid waste, upon release from the Restricted Area, shall not exceed 2 x 10-6 uCi/ml; Specifications 3.9.1 If the experienced release of radioactive =aterials 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;
- c. Describe these actions in a report to NRC/ DOR within 30 days af ter !
incurring the reporting obligation.
3.9.2 The release rate of radioactive liquid ef fluents, excluding tritium and dissolved noble gases, shall not exceed 10 curies during any calendar quarter without specific appreval of the Ce=mtssion. Similarly, the quarterly average concentration of tritium released from the
,% Restricted Area shall not exceed 1 x 10-5 uC1/ml.
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