ML19341C623

From kanterella
Jump to navigation Jump to search
Forwards Addl Info Re Reactor Core Primary Coolant Bypass Fractions & Comparison of Predicted Vs Measured Core Region Outlet Temps Before & After Experience of Core Region Outlet Temp Redistribution,Per NRC 810210 Request.W/O Encl
ML19341C623
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 02/23/1981
From: Swart F
PUBLIC SERVICE CO. OF COLORADO
To: John Miller
Office of Nuclear Reactor Regulation
References
P-81064, NUDOCS 8103030843
Download: ML19341C623 (1)


Text

. - - -.

i E3 o

l public Service Company cf Odmede

'?

12015 East 46th Avenue, Suite 440; Denver, CO 80239 i

l I

n p:

February 23, 1981 S

Fort St. Vrain i

74 Unit No. 1 O

P-81064 1

4 Mr. James E.

Miller, Chief Special Projects Branch j

Division of Project Management j

U.S. Nuclear Regulatory Commission Uashington, D.C.

20555 Docket No. 50-267

Subject:

Additional Temperature Redistribution Information i

References:

(1) PSC/NRC Meeting February 10, 1981 s

(2) PSC Letter P-81057 February 19, 1981

Dear Mr. Miller:

i In the referenced meeting, members of the NRC staff 1

requested certain additional information related to reactor 4

core primary coolant by-pass fractions and a comparison of predicted -vs-measured core region outl et temperatures i

before and af ter a core region outlet temperature redis-I tribution is experienced.

This letter transmits the requested information.

I Uith the submittal of the attached information and the revised Testing Procedure RT-500K transmitted per letter P-81057, all information requested by the Staff has been sub-mitted to allow release of the Fort St. Vrain Unit No. 1 i

)

from the present 70% power restriction for testing purposes.

j PSC requests the NRC concur with the contents of Testing Procedure RT-500K to allow the planned testing to begin in very early March, 1981.

1 e

j very truly yours,

~7-s Atbwa f.Mf e 1 Frederic E.

Swart Nuclear Project Manager PES /pa 82 0s+30 M3

-