ML092390118

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Crystal River, Unit 3, Response to Individual Plant Actions Regarding Pressurized-Water Reactor Owners Group Topical Report, BAW-2374, Revision 2, Risk-informed Assessment of Once-Through Steam Generator Tube Thermal Loads Due to Breaks in
ML092390118
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 08/25/2009
From: Franke J A
Progress Energy Florida
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
3f0809-02, TAC ME1799
Download: ML092390118 (7)


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