ML19260C620
| ML19260C620 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/31/1979 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML19260C619 | List: |
| References | |
| NUDOCS 8001080136 | |
| Download: ML19260C620 (1) | |
Text
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public service company oe cdlasde 16805 Weld County Road 19 1/2, Platteville, Colorado 80651 October 31, 1979 Fort S t.
Vrain U it No. 1 n
P-79250 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Commission
,,0V c1979 Region IV B
office of Inspection and Enforcement 611 Ryan Plaza Drive
~ ~~~
Suite 1000 Arlington, Texas 76012 REF:
Facility Operating License No. DPR-34 Docket No. 50-267
Dear Mr. Seyfrit:
The Fo rt S t. Vrain Nuclear Generating Station Non-Radiological Technical Specifications outline reporting requirements with regard to chemical con-centrations of non-radioactive liquid effluent and turbine building sump effluent fellowing commercial operation. Although Fort S t.
Vrain has been accepted by Public Service Company of Colorado for commercial operation, the plant has not yet reached 100% power, nor has the Technical Specifica-tion definition of commercial operation been met.
Specification SR NR 1.1 and SR NR 1.3 require that reports based on evalua-tion of data obtained during the first 90 days of commercial operation be submitted within 120 days following commercial operation.
Since the plant has not yet been operated at power levels in excess of 70%, information based on 100% power commercial operation is not available. Evaluation by Water Chemistry personnel indicates that data taken under the present 70%
power restriction is not representative of 100% power conditions.
Due to the number of variables, the actual impact of 100% power generation cannot be es timated.
We request relief from the reporting requirements referenced above until the plant attains 100% full power operation, or until 70% is determined to be the maximum attainable power level, if that should eventually be the case.
If relief is granted, we will evaluate data for the 90 day period following determination of the final attainable power level and submit the required report.
If you have any questions, please contact this office, (303) 571-7436.
Ve ry t ruly yours,
'l02 095 LL yy;- g Don Warembourg f
Manager, Nuclear Production l
DW/alk