ML19326C919

Forwards Revised Pages to Util Semiannual Operating Rept Submitted 750301 & 0321.Source of Numbers Contained in Util Rept, Rept of Radioactive Effluents, Discussed.W/O Encl

ML19326C919
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/23/1975
From:	Woodward J ARKANSAS POWER & LIGHT CO.
To:	Anthony Giambusso Office of Nuclear Reactor Regulation
References
NUDOCS 8004290552
Download: ML19326C919 (3)

Text

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NRC DISTRIBUTION FOR PART 50 DOCKET MATER (TEMPORARY FORM)

CONTROL NO:- 682E Enviro FILE.

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.DATE OF DOC DATE REC'D LTR TWX A

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!!r. A. Gianbusso INPUT CLASS UNCLASS PROPINF9 50-313 xxxxxxx ENCLOSURES:

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Subj ect:

Arkansas Power G Ligl rJpan Docket No. 50-313 License No. DPR-51 Semi-Annual Operating Report

Dear Mr. Giambusso:

Upon review of our Semi-Annual Operating Report at submitted to you on March 1, 1975 and March 21, 1975, we have found several errors in the environmental portion as submitted on the latter date.

R ose pages and items we are revising are as follows:

Page 174 Reporting of Radicactivity in the Environs (1) External Radiation, 4th Quarter 1974 Page 202 Report of Radioactive Effluents,1974 Section I, for October and Total items la), Ib), Ic)

Rese revision pages are attached.

Also, during conversations with Mr. Blaine Murray, Office of Inspection and Enforcemeat, Region IV, the source of our numbers as contained in the " Report c f Radioactive Effluents"Section I, line la) was discussed.

W e following 3s our discussion of this e urce.

Tabic 2-2, Item 1, of Appendix B to Operating License No. DPR-51 (Environmental Technical Specifications) specifies that a " gross beta and gamma" analysis be done prior to release of each batch of liquid waste. The definition of " gross beta and gamma" was the sub-ject of much discussion in our original efforts to set up our radio-chemistry nrogram. %e final decision was to do a gross beta count by the liquid scintillation method to satisfy this requirement.

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sion was based on the fact that this method would more accurately reveal the true activity contained in each release.

n e liquid scintillation counting equipment was set up to count all beta events with energies above that of the tritium beta; therefore, the activity measured was attributable to all nuclides contained in the sample, including dis-solved noble gases (excluding tritium). These au the numbers as reported in Section I, line (a) of " Reporting of Ra !ioactive Effluents" because of the wording " Gross Radioactivity (8,Y)" that so closely resembles the wording of the above mentioned table in Appendix B of This gross beta analysis was done simply to satisfy that our license.

requirement of Table 2-2 and was written on each liquid release permitNo issued to the operators to record that this analysis had been done.

interrogation of the Appendix B limits or other use was made of the values obtained from gross beta analysis because the results of the gamma isotopic analysis are known to be a more accurate detemination The sum of individual of the true activity contained in the samples.

gamma isotopic results were used to interrogate the Appendix B limits.

For this reason in future reports we will report in Section I, line la),

" Report of Radioactive Effluents", the sum of those activities of indi-vidual isotopes as determined by gamma spectroscopy methods and listed individually in Section I, line -7 of the same report.

If you have any questions or comments concerning this approach, do not hesitate to call.

Very truly yours, 5W f

J.11. Woodward Director, Power Production JIIW:tw Attachment cc:

Mr. E. Morris lloward, Director U. S. Nuclear Regulatory Commission Region IV, Suite 1000 611 Ryan Plaza Drive Arlington, Texas 76012 l

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