ML20246D635
ML20246D635 | |
Person / Time | |
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Site: | Fort Saint Vrain |
Issue date: | 03/15/1989 |
From: | Zech L NRC COMMISSION (OCM) |
To: | Sharp P HOUSE OF REP., ENERGY & COMMERCE |
Shared Package | |
ML20246D630 | List: |
References | |
CCS, MARKEY-890315, NUDOCS 8907110380 | |
Download: ML20246D635 (2) | |
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QUESTION 2. Isn't it true that the Fort St. Yrain Gas-cooled reactor in )
1 Colorado has had a-variety of malfunctions since its ' '
initial start up, and that its' utility cwner recently announced it would abandon the plant for commercial 3 I
operation in 1990. What it NRC's assessment of the safety and reliability of the Fort St. Vrain Gas-cooled reactor, compared to the current generation of light water reactors?
What does this say about the advisability of relying on this technology to meet our national security needs?
ANSWER It is true that Fort St. Vrain has had a variety of operational weblems over its service life wnich have affected plant availability and that Public Service Company of Colorado (owner and operator of Fort St. Vrain) notified us in December 1988 of early tennination of Fort St. Vrain operations. Plant availability has generally been lower than LWR's of the same vintage which, to a large degree, has been cue to leakage problems with the helium circulators. The correction of the problem is of primary concern to the designers of the new MHTGR's.
In our view, the safety of Fort St. Vrain is comparable to that of existing light water reactors. However, there are two areas where we believe Fort !
St. Vrain has enhanced safety characteristics beyond existing light water reactors:
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{ . n,1 00ESTION2.,(Continued) -E-1' 1
1 (a) lower' radiological exposure' rates for operating personnel, 1
l -- and (b) longer response times under core heatup' accidents.
The NRC has not been involved in any assessments regarding the use of this technology to meet national security needs (i.e. as a production reactor).
1 and, therefore, cannot comment on this issue.
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