ML19260B249: Difference between revisions

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Omaha Public Power District 1823 HARNEY a OMAHA. NEBRASMA 68102 e TELEPHONE 536-4000 ARE A CODE 402 December 4, 1979 Director of Nuclear Reactor Regulation ATTN: Mr. Robert W. Reid, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D. C. 20555
* Omaha Public Power District 1823 HARNEY a OMAHA. NEBRASMA 68102 e TELEPHONE 536-4000 ARE A CODE 402 December 4, 1979 Director of Nuclear Reactor Regulation ATTN: Mr. Robert W. Reid, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D. C. 20555


==Reference:==
==Reference:==

Latest revision as of 07:34, 22 February 2020

Forwards Loss of Load to One Steam Generator Incident Analysis, as Supplemental Info Re Application for Amend to License DPR-40,permitting Cycle 6 Operation Following Core Reload
ML19260B249
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 12/04/1979
From: William Jones
OMAHA PUBLIC POWER DISTRICT
To: Reed R
Office of Nuclear Reactor Regulation
Shared Package
ML19260B250 List:
References
NUDOCS 7912070463
Download: ML19260B249 (1)


Text

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Omaha Public Power District 1823 HARNEY a OMAHA. NEBRASMA 68102 e TELEPHONE 536-4000 ARE A CODE 402 December 4, 1979 Director of Nuclear Reactor Regulation ATTN: Mr. Robert W. Reid, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Reference:

Omaha Public Power District Fort Calhoun Station Unit No. 1 Docket No. 50-285 Stretch and Reload App'1 cations Gentlemen:

Omaha Publ.'c Power District hereby submits forty (h0) copies of supplemental material concerning (1) the Application for Amend-ment of Operating License (" Stretch Application"), filed July 17, 1979, which seeks to amend Facility Operating License No. DPR 40 to permit Lyele 6 operation following core reload at an increased power level of 1500 I&t, and (2) the Application for Amendment of Operating License (" Reload Application"), filed July 17, 1979, which seeks to permit Cycle 6 operation following core reload. The fol-loving materials are enclosed:

(1) Loss of Load to One Steam Generator Incident Analysis (2) Responses to NRC staff questions received October 30, 19'is, regarding Fort Calhoun Cycle 6 setpoints Should you desire additional information on these materials, please advise us.

Since ely,

~

YW W . CJones Divisi, . _/

on Manager Production Operations WCJ/KJM/BJH:jmm Enclosures cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N. W. 05,_o Washington, D. C. 20036 1515 7912070