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Boron +, Nickel +, Carbon +, Hydrogen +, Chloride +, Lead +  and Zinc +

10 CFR 54 +, 10 CFR 50.55a +  and 10 CFR 54.21#a3 +

ASME Code Case N-729-1 +  and ASME Code Case N-722 +

NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2001-060 +, NRC 2002-0002 +, NRC 2002-001 +, NRC 2002-0027 +, NRC 2002-043 +, NRC 2004-0077, 60-Day Report Pursuant to NRC Bulletin 2003-02 and NRC First Revised Order EA-03-009 for Unit 1 Refueling Outage 28 Reactor Vessel Inspections +, NRC 2004-0075, 60-Day Response to Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors +, NRC 2004-0023, Response to First Revised Order EA-03-009 +, NRC 2004-0006, Day Report Pursuant to NRC Bulletin 2003-02 and NRC Order EA-03-009 for Point Beach Nuclear Plant Unit 2 Reactor Vessel Inspections +, NRC 2003-0089, NRC Bulletin 2003-02, 30-Day Response +, NRC 2003-0006, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response for Point Beach Nuclear Plant, Request for Additional Information (TAC No.MB4566 & MB4567) +, NRC 2002-0102, Letter from A. J. Cayia Dated 11/15/2002, Point Beach, Unit 1, Thirty-day Response to NRC Bulletins 2001-01, 2002-01 & 2002-02 for Reactor Vessel Head & Vessel Head Penetration Nozzle Inspection Findings +, NRC 2002-0082, Day Response to NRC Bulletin 2002-02: Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs +, NRC 2002-0037, Supplement to Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. +, NRC 2002-0038, Supplement to Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles. +, NRC 2002-0029, Revised Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. +  and NRC 2002-0050, To License Amendment Request 229 TS LCO 3.5.2, ECCS-Operating, & LCO 3.5.3, ECCS-Shutdown +

05000266  +, 05000301  +, 00266  +  and 00301  +

ML053420129 +  and NRC 2005-0002, Response to Request for Additional Information Regarding the Point Beach Nuclear Plant, Units 1 and 2, License Renewal Application +

MRP-139 +, MRP-227 +  and MRP-126 +

Meyer L +  and Florida Power & Light Energy Point Beach +

NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +  and NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +

ML060530413 +, ML023220542 +, ML022170391 +  and ML043010155 +

NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal +, NRC 2001-060 +, NRC 2002-0002 +, NRC 2002-001 +, NRC 2002-0027 +, NRC 2002-043 +, NRC 2004-0077, 60-Day Report Pursuant to NRC Bulletin 2003-02 and NRC First Revised Order EA-03-009 for Unit 1 Refueling Outage 28 Reactor Vessel Inspections +, NRC 2004-0075, 60-Day Response to Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors +, NRC 2004-0023, Response to First Revised Order EA-03-009 +, NRC 2004-0006, Day Report Pursuant to NRC Bulletin 2003-02 and NRC Order EA-03-009 for Point Beach Nuclear Plant Unit 2 Reactor Vessel Inspections +, NRC 2003-0089, NRC Bulletin 2003-02, 30-Day Response +, NRC 2003-0006, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response for Point Beach Nuclear Plant, Request for Additional Information (TAC No.MB4566 & MB4567) +, NRC 2002-0102, Letter from A. J. Cayia Dated 11/15/2002, Point Beach, Unit 1, Thirty-day Response to NRC Bulletins 2001-01, 2002-01 & 2002-02 for Reactor Vessel Head & Vessel Head Penetration Nozzle Inspection Findings +, NRC 2002-0082, Day Response to NRC Bulletin 2002-02: Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs +, NRC 2002-0037, Supplement to Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. +, NRC 2002-0038, Supplement to Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles. +, NRC 2002-0029, Revised Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. +  and NRC 2002-0050, To License Amendment Request 229 TS LCO 3.5.2, ECCS-Operating, & LCO 3.5.3, ECCS-Shutdown +

NRC Bulletin 04-01 +, NRC Bulletin 02-01 +, NRC Bulletin 01-01 +, NRC Bulletin 02-02 +  and NRC Bulletin 03-02 +

Information Notice 90-10 +, Information Notice 2005-02, Pressure Boundary Leakage Identified on Steam Generator Bowl Drain Welds +, Information Notice 2001-05, Through-Wall Circumferential Cracking of Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzles at Oconee Nuclear Station Unit 3 +  and Information Notice 2000-17, Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V.C. Summer +

DPR-24 +  and DPR-27 +

Washington +  and Texas +

Steam Generator +, Reactor Coolant System +, Reactor Pressure Vessel +  and Control Rod +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Boric Acid +, Non-Destructive Examination +, Weld Overlay +, Stress corrosion cracking +, License Renewal +, Liquid penetrant +, Through-Wall Leakage +, DM weld +  and Leak Before Break +

WCAP-16266-P +  and WCAP-16345-P +

WCAP-16345-P +  and WCAP-16266-P +