ML20062L576
| ML20062L576 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/05/1981 |
| From: | Loges J PUBLIC INTEREST RESEARCH GROUP, COLORADO |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8102090200 | |
| Download: ML20062L576 (2) | |
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r Questions, Submitted by John Loges, Colorado Public Interest Research Group 1.If the reactor is pushed toward its rated capacity, will the efficiency change comparably?
- 2. Since increased efficiency would apparently require increased temperature, do you perceive a problem with continuing shrinkage?
- 3. Has tha_ proposed. Emergency Safety. Tower been_ cited, and, if so, has the Incation been chosen?
on what consideratio[/har-Win thaMowen ~badona+-a *=bc b~ ~op c 5;
o fer Stn * "" I N '/)
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is pushed beyond 70%?
5.
Have PSco and other public officials and. suthorities complied fully with the psevisions of the latest-NRC reguls tions?
6_.
When will there be evacuation drills to determine whether new safety plans are in fact practical?
- 7. _Have you resolved the issue of having an expert emergency techniciah on 30 minute call?
- 8. What are the results of the recent computer analysis of the l
performance of the core of the reactor?
9.
Is there stin a problem with the carbon cadding en the fuel rods? are there sti n changes in configuration?
- 10. If the roda do change configuration,does the change anffect safety considerations?
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- 11. Will the capacity increases be accompanted k[n'the kind of amounts of radiation generated by the reactor?
- 12. Of the radio-isotopes generated by the plant, how is it decided which ones to monitor? Which ones are monitored?
- 13. Given the exceptionally long time the plant has required to 1
become commercially operational, win the designed life span of the plant han to be re-appraised to consider the deter-ioration of materials caused by aging?
- 14. When will the transcript of the NRCACRS meeting on Monday, January 26 become available?
I
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