TAC:ME1799
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MONTHYEARML0921200022009-07-31031 July 2009
[table view]Individual Plant Actions 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 ML0923901182009-08-25025 August 2009 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 Reactor ML0930104902009-11-0303 November 2009 Once-Through Steam Generator Tube Loads Under Conditions Resulting from Postulated Breaks in Reactor Coolant System Upper Hot-Leg Large-Bore Piping 2009-07-31 | |
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