ML19341B824
| ML19341B824 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/18/1981 |
| From: | Swart F PUBLIC SERVICE CO. OF COLORADO |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| P-81054, NUDOCS 8102270693 | |
| Download: ML19341B824 (2) | |
Text
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public service company of cenenam 12015 East 46th Avenue, Suite 440; Denver, CO 80239
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February 18, 1981 Fort St. Vrain Unit No. 1 P-81054 Mr. James E. Miller, Chief Special Projects Branch Division of Project Management U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Docket No. 50-267
Subject:
RECA 3 Code Analysis of FSV Scram Transient
Reference:
PSC/GAC/NRC Meeting of 2/10/81
Dear Mr. Miller:
At the referenced meeting attended by representatives of the
.Public Service Company of Colorado (PSC), General Atomic-Company.(GhC), and members of the NRC staff, a presentation was made-by GAC.that demonstrated the ability of the RECA 3 Code to predict reactor core region outlet temperatures un-der scram transient conditions.
The transient analyzed by GAC using the RECA 3 Code involved a reactor scram from 35 percent power.
A discussion ensued concerning the ability of the RECA 3 Co/ a to predict reactor core region outlet temperatures fol-lowing reactor scrams from other. core conditions.
Specifi-cally, discussions focused on a reactor core " temperature redistribution" configuration that has occurred at higher h/
reactor power levels where pressure drops across the core II" exceed approximately 4.0 psid.
The NRC staff expressed a 3
concern about the ability of the RECA 3 Code to adequately predict reactor core region outlet temperatures following a reactor scram from a power level above the " temperature
[O redistribution" threshold.
810227tigg
P-81054 Page 2 February 18, 1981 This letter is to confirm, in writing, PSC's verbal commit-ment made at the referenced meeting to evaluate a reactor scram transient from a " temperature redirtribution" confi-guration using the RECA 3 Code should an appropriate scram transient occur.
It should be understood that a scram will not be intentionally induced for the purpose of this analysis.
It should be further understood that PSC intends to operate the reactor with the region inlet orifice valves adjusted to establish a " normal" reactor core pressure drop.
No special efforts will be made to induce a " temperature redistribution" configuration.
With the above understandings, PSC will have the first suitable scram transient analyzed to determine if the RECA 3 Code can adequately predict reactor core region outlet tempe rature s.
The predicted region outlet temperatures will be compared to the region outlet temperatures that are meas-ured during the scram from the " temperature redistribution" configuration.
The results of this analysis will be submit-ted to the MRC for information and consideration.
Very truly yours, m
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Frederic E.
Swart Nuclear Project flanager FES/pa S