NRC Generic Letter 1978-28
| ML031280378 | |
| Person / Time | |
|---|---|
| Issue date: | 07/28/1978 |
| From: | Grimes B Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| GL-78-028 | |
| Download: ML031280378 (4) | |
UNITED STATES
NUCLEAR REGULATORY COMMIS.SiON
so no2 2 WASHINGTON, D. C. 20555
- July 28, 1978 G Z7 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 BWR's (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,
6 + - 4 - - - - - - --
Brian Grimes, Assistant Director for Engineering and Projects Division of Operating Reactors Enclosures:
1. Page 3/4 3-51
2. Page B 3/4 11-5
TABLE 4.3-11 (Continued)
TABLE NOTATION
- - During releases via this pathway.
- ^During liquid additions to the tank.
(1) - The CHANNEL FUNCTIONAL TEST shall also room demonstrate that automatic isolation of this pathway and control 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.
that control room
(2) - The CHANNEL FUNCTIONAL TEST shall also demonstrate conditions exist:
alarm annunciation occurs if any of the following the alarm/trip
1. Instrument indicates measured levels above setpoint.
2. Circuit failure.
3. Instrument indicates a downscale failure.
4. Instrument controls not set in operate mode.
use of a known (traceable
(3) - The CHANNEL CALIBRATION shall include the system)
to the National Bureau of Standards radiation measurement geometry liquid radioactive source positioned in a reproducible gamma radiation with respect to the sensor and emitting beta and by the with the fluences and energies in the ranges measured channel during normal operation.
BWR-STS-I 3/4 3-51
I
RADIOACTIVE EFFLUENTS
BASES
3/4.11.2.5 EXPLOSIVE GAS MIXTURE
concentration of This specification is provided to ensure that the gas holdup in the waste potentially explosive gas mixtures contained of hydrogen and oxygen.
system is maintained below the flammability limits in the system to prevent the (Automatic control features are included these flammability limits.
hydrogen and oxygen concentrations from reaching isolation of the source of These automatic control features include or injection hydrogen and/or oxygen, automatic diversion to recombiners, the flammability limits.)
of dilutants to reduce the concentration below and oxygen below their flam- Maintaining the concentration of hydrogen of radioactive mability limits provides assurance that the releases the requirements of materials will be controlled in conformance with CFR Part 50.
General Design Criterion 60 of Appendix A to 10
3/4.11.2.6 MAIN CONDENSER
gases from the Restricting the gross radioactivity rate of noble that the total body exposure main condenser provides reasonable assurance will not exceed a small to an individual at the exclusion area boundary
100 in the event this effluent fraction of the limits of 10 CFR Part environment without treat- is inadvertently discharged directly to the of General ment. This specification implements the requirements Part 50.
A to 10 CFR
Design Criteria 60 and 64 of Appendix
3/4.11.2.7 MARK I CONTAINMENT (OPTIONAL)
that releases This specification provides reasonable assuranceannual dose the from drywell purging operations will not exceed limits of 10 CFR Part 20 for unrestricted areas.
3/4.11.3 SOLID RADIOACTIVE WASTE
ensures that the system The OPERABILITY of the solid radwaste system require processing and will be available for use whenever solid radwastes specification implements packaging prior to being shipped offsite. This Design Criteria 60 of the requirements of 10 CFR Part 50.36a and General included in establish- Appendix A to 10 CFR Part 50. The process parameters but are not limited to waste ing the PROCESS CONTROL PROGRAM may include, ratios, waste type, waste pH, waste/liquid/solidification agent/catalyst mixing and curing oil content, waste principal chemical constituents, times.
BWR-STS-1I B 3/4 11-5
r Niagara Mohawk Power Corporation cc: Eugene B. Thomas, Jr., Esquire LeBoeuf, Lamb, Leiby & MacRae
1757 N Street, N. W.
Washington, D. C. 20036 Anthony Z. Roisman Natural Resources Defense Council
917 15th Street, N. W.
Washington, D. C. 20005 Oswego County Office Building
46 E. Bridge Street Oswego, New York 13126