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| Issue date | From | Title | Project stage | |
|---|---|---|---|---|
| ML092120053 | 5 August 2009 | Peter Bamford Plant Licensing Branch I | 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 in Reactor Coolant System. | Other |
| TMI-09-105, Response to June 25, 2009, Public Meeting Between the U.S. Nuclear Regulatory Commission and the Pressurized Water Reactor Owners Group (PWROG) Related to PWROG Topical Report BAW-2374, Revision 2 | 4 September 2009 | Exelon Cowan P | Response to June 25, 2009, Public Meeting Between the U.S. Nuclear Regulatory Commission and the Pressurized Water Reactor Owners Group (PWROG) Related to PWROG Topical Report BAW-2374, Revision 2 | Meeting |
| ML093010455 | 3 November 2009 | Peter Bamford Plant Licensing Branch I | Once-Through Steam Generator Tube Loads Under Conditions Resulting from Postulated Breaks in Reactor Coolant System Upper Hot-Leg Large-Bore Piping | Other |
| TMI-10-004, Summary of Analysis Results to PWROG Topical Report BAW-2374, Revision 2 | 29 January 2010 | Exelon David Helker | Summary of Analysis Results to PWROG Topical Report BAW-2374, Revision 2 | Other |