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UNITC'3 CT TE] DEPARTMENT OF COMMERC3 | UNITC'3 CT TE] DEPARTMENT OF COMMERC3 Ne'lonel Inst.itute of Ctander de and Technology | ||
\\ | |||
/ | |||
Gathemtvo, Ma vem 20099 1 | |||
1 | August 1,1990 l-l U. S. Nuclear Regulatory Commission Document Control Desk Washington D.C. 20555 t | ||
l-l | |||
U. S. Nuclear Regulatory Commission | |||
==Subject:== | ==Subject:== | ||
Additional information on Request for Changs to | Additional information on Request for Changs to Section 6.2 of the Technical Specifications, i | ||
Section 6.2 of the Technical Specifications, | Docket No. 50-184. | ||
In response to the telecon request from Mr. Ted Michaels, we respec'..t"j xibmit the following | In response to the telecon request from Mr. Ted Michaels, we respec'..t"j xibmit the following analysis of this change, as prescribed in 10 CFR 50.92(c). | ||
analysis of this change, as prescribed in 10 CFR 50.92(c). | (1) | ||
(1) | This requested change does not involve a significant change in the probability or consequences of an accident previously evaluated. In the 1984 license renewal for NIST i | ||
Test Reactor, (NBSR-9, Addendum 1) aloss-of flow accident (LOFA) was analyzed. The j | |||
consequences of such an accident would be increased. | principal conclusion was that the fuel temperature rise is well below 'he melting point of L | ||
the cladding, and that no fuel damage would result. The number and type of heat l | |||
exchangers did not enter this analysis, and therefore neither the probability nor consequences of such an accident would be increased. | |||
[ | [ | ||
(2) | (2) | ||
(3) | This requested change does not incur the possibility of a new or different kind of accident from any accident previously evaluated. In no accident evaluated do the number or type i | ||
of heat exchangers enter; the proposed change will not affect this c'onclusion. | |||
appropriately for a MW operation.1 | (3) | ||
4 | The proposed change does not invalve a significant reduction in a margin of safety. The performance specWj.ons for the heat exchangers are unchanged, and they will be sized appropriately for a MW operation.1 | ||
cor.siderations are unchanged with respect to performance, material, design pressure and | ^ | ||
temperature, and fabrication code requirements.4 | 4 l s In view of the above analysis, we conclude that the proposed change involves no significant hazards. The only purpose and effect of the proposed change is to allow full consideration of; the best possible heat exchangers, incorporating the best available technology. The basic design - | ||
Sinc cly,' | cor.siderations are unchanged with respect to performance, material, design pressure and temperature, and fabrication code requirements.4 l | ||
Sinc cly,' | |||
hdchael Rowe | |||
^ | |||
Chief, Reactor Radiation Division | Chief, Reactor Radiation Division | ||
}Y | |||
+ooeoso m aoosoi i | |||
p PDR ADOCK 0D000184 | |||
PDR | + | ||
A F DC k | |||
A | U s. | ||
-}} | |||
Latest revision as of 14:07, 17 December 2024
| ML20056A265 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 08/01/1990 |
| From: | Rowe J NATIONAL INSTITUTE OF STANDARDS & TECHNOLOGY (FORMERL |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9008060252 | |
| Download: ML20056A265 (1) | |
Text
_._
UNITC'3 CT TE] DEPARTMENT OF COMMERC3 Ne'lonel Inst.itute of Ctander de and Technology
\\
/
Gathemtvo, Ma vem 20099 1
August 1,1990 l-l U. S. Nuclear Regulatory Commission Document Control Desk Washington D.C. 20555 t
Subject:
Additional information on Request for Changs to Section 6.2 of the Technical Specifications, i
Docket No. 50-184.
In response to the telecon request from Mr. Ted Michaels, we respec'..t"j xibmit the following analysis of this change, as prescribed in 10 CFR 50.92(c).
(1)
This requested change does not involve a significant change in the probability or consequences of an accident previously evaluated. In the 1984 license renewal for NIST i
Test Reactor, (NBSR-9, Addendum 1) aloss-of flow accident (LOFA) was analyzed. The j
principal conclusion was that the fuel temperature rise is well below 'he melting point of L
the cladding, and that no fuel damage would result. The number and type of heat l
exchangers did not enter this analysis, and therefore neither the probability nor consequences of such an accident would be increased.
[
(2)
This requested change does not incur the possibility of a new or different kind of accident from any accident previously evaluated. In no accident evaluated do the number or type i
of heat exchangers enter; the proposed change will not affect this c'onclusion.
(3)
The proposed change does not invalve a significant reduction in a margin of safety. The performance specWj.ons for the heat exchangers are unchanged, and they will be sized appropriately for a MW operation.1
^
4 l s In view of the above analysis, we conclude that the proposed change involves no significant hazards. The only purpose and effect of the proposed change is to allow full consideration of; the best possible heat exchangers, incorporating the best available technology. The basic design -
cor.siderations are unchanged with respect to performance, material, design pressure and temperature, and fabrication code requirements.4 l
Sinc cly,'
hdchael Rowe
^
Chief, Reactor Radiation Division
}Y
+ooeoso m aoosoi i
p PDR ADOCK 0D000184
+
A F DC k
U s.
-