NRC Generic Letter 78-28, Forwarding pages omitted from 07/11/78 letter
text
WASHINGTON, D.C. 20555
July 28, 1978
ALL BWR POWER REACTOR LICENSEES
Gentlemen:
We have discovered that pages 3/4 3-51 and B 3/4 11/5 were inadvertently omitted from the Draft Radiological Effluent Technical Specifications for BWRs (BWR-STS-I) which were forwarded to you by our letter dated July 11, 1978. Attached are copies of the omitted pages for your use.
If you have any questions on this matter, please contact us.
Sincerely,
Brian K Grimes, Assistant Director for Engineering and Projects Division of Operating Reactors
Enclosures:
- 1. Page 3/4 3-51
- 2. Page B 3/4 11-5TABLE 4.3-11 (Continued)
TABLE NOTATION
- - During releases via this pathway.
- - During liquid additions to the tank.
(1) - The CHANNEL FUNCTIONAL TEST shall also demostrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:
1. Instrument indicates measured levels above the alarm/trip setpoint
2. Circuit failure.
3. Instrument indicates a downscale failure.
4. Instrument controls not set in operate mode.
(2) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
1. Instrument indicates measured levels above the alarm/trip setpoint.
2. Circuit failure.
3. Instrument indicates a downscale failure.
4. Instrument controls not set in operate mode.
(3) - The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Bureau of Standards radiation measurement system) liquid radioactive source positioned in a reproductible geometry with respect to the sensor and emitting beta and gamma radiation with the fluences and energies in the ranges measured by the channel during normal operation.
BWR-STS-I 3/4 3-51RADIOACTIVE EFFLUENTS BASES
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3/4.11.2.5 EXPLOSIVE GAS MIXTURE
This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. (Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration below the flammability limits.) Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
3/4.11.2.6 MAIN CONDENSER
Restricting the gross radioactivity rate of nobel gases from the main condenser provides reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10 CFR part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment. This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.
3/4.11.2.7 MARK I CONTAINMENT (OPTIONAL)
This specification provides reasonable assurance that releases from drywell purging operations will not exceed the annual dose limits of 10 CFR Part 20 for unrestricted areas.
3/4.11.3 SOLID RADIOACTIVE WASTE
The OPERABILITY of the solid radwaste system ensures that the system will be available for use whenever solid radwastes require processing and packaging prior to being shipped offsite. This specification implements the requirements of 10 CFR Part 50.36a and General Design Criteria 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/liquid/solidification agent/catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.