Semantic search
Jump to navigation
Jump to search
| Issue date | Title | From | To | |
|---|---|---|---|---|
| NRC Generic Letter 1988-05 | 17 March 1988 | NRC Generic Letter 1988-005: Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants | Miraglia F Office of Nuclear Reactor Regulation | |
| NRC Generic Letter 1988-07 | 7 April 1988 | NRC Generic Letter 1988-007: Modified Enforcement Policy Relating to 10 CFR 50.49 Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants. | Miraglia F Office of Nuclear Reactor Regulation | |
| ML20154M112 | 25 May 1988 | Responds to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants. Program Document Describing Plant Policy to Identify & Correct RCS Leakage Being Prepared | Northern States Power Company Musolf D | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) Office of Nuclear Reactor Regulation |
| NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification | 2 August 1988 | NRC Generic Letter 1988-012: Removal of Fire Protection Requirements from Technical Specifications | Miraglia F Office of Nuclear Reactor Regulation | |
| ML20151X874 | 23 August 1988 | Advises That Util 880525 Response to Generic Ltr 88-05 Re Boric Acid Corrosion of Carbon Steel Reactor Boundary Components in PWR Plants Acceptable.Util Should Maintain Records of Program & Results Obtained from Program | Office of Nuclear Reactor Regulation Diianni D | Northern States Power Company Musolf D |
| ML20247M133 | 24 May 1989 | Forwards Input to SALP 8 Rept for Units 1 & 2.Evaluation Conducted Per 880606 Rev to NRC Manual Chapter 0516, Systematic Assessment of Licensee Performance & Provides Input Per Guidelines in Rl Hague 890412 Memo | Office of Nuclear Reactor Regulation Diianni D | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) Greenman E |
| NRC Generic Letter 1991-17 | 17 October 1991 | NRC Generic Letter 1991-017: Generic Safety Issue 29, Bolting Degradation or Failure in Nuclear Power Plants. | Partlow J Office of Nuclear Reactor Regulation | |
| Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion. | 5 January 1995 | Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion. | Grimes B Office of Nuclear Reactor Regulation | |
| Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. | 5 January 1995 | Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. | Grimes B K Office of Nuclear Reactor Regulation | |
| ML20151J577 | 29 July 1997 | Forwards 120-day Response to GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations | Northern States Power Company Richard Anderson | Office of Information Resources Management |
| ML023220476 | 18 November 2002 | RAI, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity | Kim T NRC/NRR/DLPM/LPD3 | Nuclear Management Co Nazar M |
| L-PI-03-007, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-day Response for Prairie Island Nuclear Generating Plant, Request for Additional Information | 20 January 2003 | Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-day Response for Prairie Island Nuclear Generating Plant, Request for Additional Information | Nuclear Management Co Nazar M | Office of Nuclear Reactor Regulation Document Control Desk |
| L-PI-05-013, Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates 09-10-04 Fuel Cycle 22: 12-7-2002 to 11-23-04 | 22 February 2005 | Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates 09-10-04 Fuel Cycle 22: 12-7-2002 to 11-23-04 | Nuclear Management Co Solymossy J | Office of Nuclear Reactor Regulation Document Control Desk |
| IR 05000282/2005004 | 21 July 2005 | IR 05000282-05-004, 05000306-05-004 on 04/01/2005 - 06/30/2005 for Prairie Island Nuclear Generating Plant, Units 1 and 2; Adverse Weather Protection; Fire Protection; Inservice Inspection Activities. and Other Activities | NRC/RGN-III/DRP/RPB3 George Wilson | Nuclear Management Co Thomas J. Palmisano |
| L-PI-04-135, Inservice Inspection Summary Report, Interval 3, Period 3, Interval 4, Period 1 Refueling Outage Dates: April 16, 2005 - June 10, 2005, Fuel Cycle 22: October 11, 2003 - June 10, 2005 | 8 September 2005 | Inservice Inspection Summary Report, Interval 3, Period 3, Interval 4, Period 1 Refueling Outage Dates: April 16, 2005 - June 10, 2005, Fuel Cycle 22: October 11, 2003 - June 10, 2005 | Nuclear Management Co Thomas J. Palmisano | Office of Nuclear Reactor Regulation Document Control Desk |
| IR 05000282/2006003 | 14 August 2006 | IR 05000282/2006003, 05000306/2006003; 4/01/06 - 6/30/06; Prairie Island Nuclear Generating Plant, Units 1 and 2; Inservice Inspection Activities, Reactor Vessel Head Replacement, Radiation Protection, and Other Activities | Richard Skokowski NRC/RGN-III/DRP/RPB3 | Nuclear Management Co Thomas J. Palmisano |
| L-PI-09-015, Submittal of Inservice Inspection Examination Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage, Dates: 09-19-2008 to 11-01-2008 Unit 2, Fuel Cycle 24:12-15-2006 to 11-01-2008 | 28 January 2009 | Submittal of Inservice Inspection Examination Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage, Dates: 09-19-2008 to 11-01-2008 Unit 2, Fuel Cycle 24:12-15-2006 to 11-01-2008 | Xcel Energy Wadley M | Office of Nuclear Reactor Regulation Document Control Desk |
| IR 05000282/2013008 | 22 July 2013 | IR 05000282-13-008, 05/20/13 - 06/13/13, Prairie Island Nuclear Generating Plant, Unit 1, Post-Approval Site Inspection for License Renewal | NRC/RGN-III/DRS/EB2 Benny Jose | Xcel Energy Jeffery Lynch |
| L-PI-16-049, Revision 34 to Updated Safety Analysis Report, Appendix L, Requirement of Renewed Operating Licenses | 3 June 2016 | Revision 34 to Updated Safety Analysis Report, Appendix L, Requirement of Renewed Operating Licenses | Xcel Energy | Office of Nuclear Reactor Regulation |
| ML18155A450 | 18 May 2018 | Updated Safety Analysis Report (USAR) Revision 35, Section 6, Engineered Safety Features | Minnesota Xcel Energy | Office of Nuclear Reactor Regulation |