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Letter  and Audit Report

ASME Section III +  and ASME Section XI +

10 CFR 50.48#c +  and 10 CFR 26.205#d3 +

05000302  +  and 00302  +

ML11242A151 +  and 3F1008-03, Relief Request 08-002-RR, Revision 0 +

Farideh Saba +  and Plant Licensing Branch II +

NRC Generic Letter 04-02 +  and NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +

ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +, ML11242A151 +...

3F0711-05, Comments on the Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Draft Report for Comment (NUREG-1437, Supplement 44) +, ML11201A006 +, RA-11-019, Request for Extension of Enforcement Discretion and Commitment to Submittal Dates for 10 CFR 50.48(c) License Amendment Requests +, ML101530397 +, 3F0510-01, NRC Commitment Change Report - May 2010 +, 3F0807-03, License Amendment Request 294, Revision 0, Elimination of Spent Fuel Pool Missile Shields, Supplement 1 +, 3F1189-17, Responds to Violations Noted in Insp Rept 50-302/89-23. Corrective Actions:Individual Posted at Sliding Door to Ensure Shut After Use Until More Permanent Corrective Action in Place +, 3F0808-03, Relief Request 07-001-SS, Revision 1, Alternate Examination Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on Three Areas 120 Degrees Apart on the Inside Surface +  and ML091910378 +

NEI 04-02, NFPA 805 Transition FAQ 10-0059, Rev 0 +  and NEI 99-04, Guideline for Managing NRC Commitment Changes +

OP-402 +, OP-409 +  and OP-404 +

SP-354A +, SP-306 +, SP-354B +, CP-252 +, CP-1130 +  and SP-249C +

3F0208-04 +, 3F1008-0S +, 3F1209-01 +, 3F1109-01 +, 3F0311-02, Response to Request for Additional Information Regarding Part 26 Exemption Request +, 3F0209-02, Response to Request for Additional Information, Regarding Response to Generic Letter 2004-02 +, 3F0508-07, Three Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +, 3F0211-01, License Amendment Request 311, Revision 0, Emergency Feedwater Pump Fuel Oil Volume +, 3F1210-05, License Amendment Request 310, Revision 0, Departure from a Method of Evaluation for Auxiliary Building Overhead Crane and Revisions to Associated Commitments +, 3F1209-02, Relief Request 08-002-RR, Revision 0, Completion of Regulatory Commitments +, 3F0508-12, Relief Request 08-001-RR, Revision 1, 60-Day Response, Summary of Analysis Calculations +, 3F0308-07, Relief Request 08-001-RR, Revision 1: Reports of Weld Overlay Examination Results +, 3F1008-03, Relief Request 08-002-RR, Revision 0 +, 3F0309-03, Response to Request for Additional Information Regarding Relief Request 08-002-RR, Revision 0, Dissimilar Metal Weld Overlay Repair During the Fourth 10-Year Inservice Inspection Interval +, 3F0809-01, License Amendment Request 304, Revision 1 Emergency Diesel Generator Voltage and Frequency Limits Revision +, 3F1008-05, Nine Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling Decay Heat Removal, and Containment Spray Systems +  and 3F0808-03, Relief Request 07-001-SS, Revision 1, Alternate Examination Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on Three Areas 120 Degrees Apart on the Inside Surface +

Washington +  and Florida +

Steam Generator +, Emergency Core Cooling System +, Decay Heat Removal +  and Containment Spray +

Progress Energy Carolinas +  and Franke J +

Weld Overlay +, Cyber Security +, Notice of Violation +, Exemption Request +, Fire Protection Program +  and Gas accumulation +