United States Nuclear Regulatory Commission - Protecting People and the Environment

Forwarding pages omitted from 07/11/78 letter (Generic Letter 78-28)


                                                              GL 78-28
                                UNITED STATES 
                        NUCLEAR REGULATORY COMMISSION 
                           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 11-5







8101100430

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                           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 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 3-51

8101100437


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RADIOACTIVE EFFLUENTS BASES
_____________________________________________________________________________


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.

Page Last Reviewed/Updated Monday, May 13, 2013