ML20079L396

From kanterella
Jump to navigation Jump to search
Informs of re-evaluation of power-to-flow Events Occurring During Cycles 1 & 2 Under Revised Safety Limit SL 3.1,to Answer Staff Inquiries Re Technical Basis for Action.More Detailed Reanalysis of Calculations Will Be Performed
ML20079L396
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 02/09/1983
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Jay Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
P-83056, NUDOCS 8302230318
Download: ML20079L396 (1)


Text

1 Public service company of odle1mde 16805 Road 19 1/2, Platteville, Colorado 80651-9298 l

February 9, 1983 Fort St. Vrain Unit No. 1 P-83056

~. _ _

Mr. John T. Collins, Regional Administrator Region IV l 41983

. ! 'l Nuclear Regulatory Commission J

l J ll 611 Ryan Plaza Drive J

Suite 1000 Arlington, Texas 76011 J

ATTN: Mr. Philip Wagner

Subject:

Fort St.

Vrain Power-to-Flow Integral Fraction

Dear Mr. Collins:

Amendment Number 23 to the Fort St. Vrain Technical Specifications revised Safety Limit SL 3.1 from a fuel cycle basis to a fuel segment basis.

In implementing the revised criteria, the power-to-flow integral fraction for cycles 1 and 2 was reset to zero with the concurrence of the Nuclear Regulatory Commission.

Recent inquiries by your staff have questioned the technical basis for this action.

Rather than complicate the situation further, we have agreed to re-evaluate the power-to-flow events which occurred during cycles 1 and 2 under the revised SL 3.1 and include their contribution into the present cycle 3.

It has been determined that a conservative value for the power-to-flow integral fraction for cycles 1 and 2 is 0.02314.

This value will be added to the integral fraction for cycle 3 for the appropriate fuel segments; i.e., those segments that were in the core during cycles 1 and 2.

In the future, if the adjusted integral fraction approaches the limit of 1.0, we will perform a more detailed re-analysi s of our calculations to take credit for the very conservative assumptions we have made in this evaluation.

If you have any further questions concerning this subject, please contact me or Mr. Chuck Fuller at (303) 785-2224.

Ver truly ours, J

8 r

Don Warembourg Manager, Nuclear Production DW/cis 8302230318 830209 PDR ADOCK 05000267 A

__