ML19341C623

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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

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" @_ public Service Company cf Odmede 12015 East 46th Avenue, Suite 440; Denver, CO 80239

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i l :n I p: February 23, 1981

S Fort St. Vrain i 74 - Unit No. 1 O P-81064 1  !

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! 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 1

In the referenced meeting, members of the NRC staff 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-i mitted to allow release of the Fort St. Vrain Unit No. 1

) 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 1

82 0s+30 M3 i

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