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Iodine +, Nitrogen +, Hydrogen +  and Lead +

10 CFR 55 +, 10 CFR 50.67 +, 10 CFR 26 +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.9 +, 10 CFR 50.82 +, 10 CFR 50.120 +, 10 CFR 55.43 +  and 10 CFR 50.82#a +

05000302  +  and 00302  +

ML13056A005 +, ML13144A777 +, ML11292A041 +, ML081060231 +, ML041940505 +  and ML020700585 +

Technical Support Center +  and Emergency Operations Facility +

Duke Energy Florida +  and Wunderly B +

NRC Generic Letter 04-02 +, NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 86-04, Policy Statement On Engineering Expertise on Shift +, NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 2003-01, Control Room Habitability +  and NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +

3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F0514-08, NRC Commitment Change Report - May 2014 +  and 3F0514-08, NRC Commitment Change Report - May 2014 +

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

ML13144A777 +  and 3F0213-09, Request for Schedule Relaxation Associated with the Fukushima Orders (EA-12-049 and EA-12-051) +

NRC Bulletin 03-01 +, NRC Bulletin 82-02 +, NRC Bulletin 84-03 +  and NRC Bulletin 85-03 +

NUREG-1122, Rev. 3 Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

FPP +, ES +, Emergency Operating Procedure +, CP-1 +, CP-252 +, CP-253 +, SP-175A +  and CP-118 +

3F0580-02 +, 3F0485-07 +, 3F0514-08, NRC Commitment Change Report - May 2014 +, 3F1280-08 +, 3F0289-04 +, 3F1207-05 +, 3F0578-08 +, 3F0685-01 +, 3F1285-09 +, 3F0803-03, 60-Day Response to NRC Bulleting 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors +, 3F0987-20, Forwards Responses to Request for Addl Info Re IE Bulletin 85-003.Valve Position Visual Indication,Both Open & Closed, Provided in Control Room for Each Valve.Indications Not Dependent on Power Being Available to Valve Actuators +, 3F0987-14, Forwards Response to Generic Ltr 87-12, Loss of RHR While RCS Partially Filled. Plant Shutdown & Cooldown to Partially Drained Condition Takes Approx 72 H to Complete Depending on Cause of Shutdown.Lists Event That Would Occur +, 3F0586-19, Responds to 860213 Generic Ltr 86-04.Util Program Re Engineering Expertise on Shift Unchanged from Util .Specified Training Will Be Provided Per NUREG-0737 & Tech Specs as Stated.Present Program Will Not Be Modified +, 3F1297-24, Provides Supplemental Info to Support Util Response to NRC Request for Addl Info,Dtd 970128.Clarification to Util RAI Responses,Discussed During NRC Audit USI A-46 & Calculations Encl also.W/10 Oversize Drawings +, 3F0785-27, Submits Rev to Commitment Re Training of Replacement Reactor Operator & Senior Reactor Operator Candidates in Heat Transfer,Fluid Flow & Thermodynamics,Per NUREG-0737, Item I.A.2.1(4) +, 3F0684-06, Forwards Response to IE Bulletin 82-02,Action Items 1,2 & 4 Re Threaded Fastener Practices.Flange at Location P-6 Showed Definite Signs of Leakage During Refuel III Insp +, 3F0208-01, License Amendment Request 295, Revision 0: Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times - Response to Request for Additional Information +, 3F0797-25, Provides Addl Clarification & Info on NRCs SER That Accompanied Amend 152,requesting 18 to 24-month Fuel Cycle Extensions.Withdrawal of TS Changes Made in Util ,Requested.Commitments Made,Encl +, 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 +, 3F1207-02, Request for Extension of Completion Date for Corrective Actions and Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized. +, 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, 3F0204-05, License Amendment Request No. 279, Revision 0, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Sampling System for Babcock & Wilcox Reactors Using the Consolidated Line Item +, 3F1203-02, Response to Generic Letter 2003-01, Control Room Habitability +  and 3F0702-07, License Amendment Request 257, Revision 0, Emergency Diesel Generator Allowed Outage Time Extension +

Washington +  and Florida +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Residual Heat Removal +, Remote shutdown +, Emergency Feedwater Initiation and Control +, Decay Heat Removal +, Control Rod +  and Containment Spray +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Shift Technical Advisor +, Earthquake +, Fire Watch +, Control Room Habitability +, Spent fuel rack +  and Gas accumulation +