ML20137S691

Errata to Semiannual Radioactive Effluent Rept,Jan-June 1985

ML20137S691
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/30/1985
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20137S678	List: ML20137S675 ML20137S691
References
NUDOCS 8509300479
Download: ML20137S691 (2)

Text

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l SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT January - June 1985 Public Service Company of Colorado Fort St. Vrain Nuclear Generating Station August 1985 8509300479 850916 PDR R ADOCK 05000267 PDR

-2 1.0 Summary This report summarizes the radiological effluent released from the Fort St. Vrain Nuclear Generating Station for the -period January through. June, 1985. In addition, Table 3.1 provides a general summary of the plant systems under radiological surveillance, and Table 4.1 summarizes the solid radioactive waste removed from the site during the aforementioned time period. This information is provided pursuant to th'e requirements of Section 7.5.le of the Fort St. Vrain Techr.ical Specifications.

The large number of radionuclides discharged via the liquid 4 pathway during this reporting period can be attributed to the extensive decontamination efforts involved with the control rod drive refurbishment program. Of the gamma emitting radionuclides measured, the- most significant were 60Co with a total discharge of 450 microcuries and 137Cs with a total of 125.9 microcuries. As compared to the previous reporting period the tritium released via the liquid pathway. was down significantly from approximately 100 curies to approximately 4 curies. This reduction was due to the reactor being in a shutdown and depressurized condition.

There were no radionuclides discharged via the gaseous pathway except for gaseous tritium.

No solid radioactive- low level waste was- removed from the station during this reporting period. Work is continuing on the station program for 10CFR61 compliance. This program should be completed during the next reporting period.

There were no unplanned gaseous or' liquid radioactive releases from the site to the unrestricted area during this reporting period.

During the first half of 1985, one change was made to the Offsite Dose Calculation Manual (SUSMAP-2) which more clearly delineated the sample site descriptions for our Radiological Environmental Surveillance Program.

No changes were made to the Process Control Program (SUSMAP-3) during the reporting period.

No license-initiated major changes to the radioactive waste systems were made during this reporting period.