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{{#ask: [[Generic letter::NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04)]] [[Site::Fort Calhoun]]
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    "query_string": "[[Generic letter::NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04)]] [[Site::Fort Calhoun]]",
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	Issue date	Title	From	To
NRC Generic Letter 1989-21	19 October 1989	NRC Generic Letter 1989-021: Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements	Partlow J Office of Nuclear Reactor Regulation
ML17223A757	15 March 1990	Provides Util Schedule for Resolution of USI A-2.Util Will Determine RCS Leak Detection Sys Capability & Response Time & Submit Revs to Tech Specs by 900731 If Necessary	Gates W OMAHA PUBLIC POWER DISTRICT	Office of Information Resources Management
LIC-90-0591, Provides Info Re RCS Leak Detection Sys to Detect Leaks from Primary Piping Sys to Containment,Per Generic Ltr 84-04 & USI A-2	13 August 1990	Provides Info Re RCS Leak Detection Sys to Detect Leaks from Primary Piping Sys to Containment,Per Generic Ltr 84-04 & USI A-2	Gates W OMAHA PUBLIC POWER DISTRICT	Office of Information Resources Management
ML20045H018	1 July 1993	Forwards 1993 Updated SAR & 10CFR50.59 Rept for Fort Calhoun Station.Info for Period 920123 Through 930122	Gates W OMAHA PUBLIC POWER DISTRICT	Office of Information Resources Management
ML20069H926	6 June 1994	Proposed Tech Specs Incorporating Changes to Credit Leak Before Break Methodology to Resolve USI A-2, Asymmetrical Blowdown Loads on Rcps	OMAHA PUBLIC POWER DISTRICT
ML072150293	30 July 2007	License Amendment Request (Lar), Modification of the Containment Spray System Actuation Logic.	Omaha Public Power District Bannister D J	Office of Nuclear Reactor Regulation Document Control Desk
LIC-13-0100, WCAP-17262-NP, Rev 1, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for Fort Calhoun, Unit 1	31 July 2013	WCAP-17262-NP, Rev 1, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for Fort Calhoun, Unit 1	Westinghouse Kupper C	Office of Nuclear Reactor Regulation
ML13220A073	5 August 2013	License Amendment Request 13-06; Plant-Specific Leak-Before-Break Analysis	Omaha Public Power District Cortopassi L P	Office of Nuclear Reactor Regulation Document Control Desk

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