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| Issue date | Title | |
|---|---|---|
| IR 05000289/2019003 | 6 November 2019 | Integrated Inspection Report 05000289/2019003 |
| RA-16-059, Proposed Alternative to Utilize Code Case N5134, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 | 14 June 2016 | Proposed Alternative to Utilize Code Case N5134, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 |
| RS-16-041, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1. | 28 January 2016 | Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1. |
| IR 05000289/2014004 | 13 November 2014 | NRC Integrated Inspection Report 05000289/2014004 (July 1, 2014 - September 30, 2014) |
| RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 | 24 September 2014 | Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 |
| ML092950450 | 31 October 2009 | NUREG-1928, (1:2) Cover-Chpt 3, Section 3.2, Safety Evaluation Report, Related to the License Renewal of Three Mile Island Nuclear Station, Unit 1, Exelon Generation Company, LLC |
| IR 05000289/2008003 | 5 August 2008 | IR 05000289-08-003, on 4/1/08-6/30/08; Amergen Energy Company, LLC; Three Mile Island, Unit 1; Flood Protection Measures |
| ML080220255 | 8 January 2008 | License Renewal Application, Appendix B Through Environmental Report Page 2-59 |
| IR 05000289/2007004 | 24 October 2007 | |
| ML061510411 | 27 June 2006 | Three Mile, Unit 1 - Bulletin 2004-01, Inspections of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors, |
| ML060170702 | 17 January 2006 | Sixty-Day Response to NRC 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, and Clarification to the Response to |
| ML050130028 | 3 February 2005 | Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity |
| RS-04-109, Units 1 & 2 and Three Mile Island, Unit 1 - Initial Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized. | 27 July 2004 | Units 1 & 2 and Three Mile Island, Unit 1 - Initial Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized. |
| RS-03-176, Thirty-Day Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Head Penetrations and Reactor Coolant Pressure Boundary Integrity. | 22 September 2003 | Thirty-Day Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Head Penetrations and Reactor Coolant Pressure Boundary Integrity. |
| ML022380323 | 25 September 2002 | Third 10-Year Interval Inservice Inspection Relief Requests |
| RS-02-154, Exelon/Amergen Thirty-Day Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs. | 11 September 2002 | Exelon/Amergen Thirty-Day Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs. |
| RS-02-061, Three Mile, Unit 1, Braidwood, Units 1 & 2, Byron, Units 1 & 2 - Exelon/Amergen Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. | 1 April 2002 | Three Mile, Unit 1, Braidwood, Units 1 & 2, Byron, Units 1 & 2 - Exelon/Amergen Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. |
| ML020420288 | 7 January 2002 | Amergen Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles, Item No. 5 |
| IR 05000289/1999003 | 29 June 1999 | Insp Rept 50-289/99-03 on 990425-0605.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support |
| Information Notice 1994-79, Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping | 23 November 1994 | Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping |
| Information Notice 1988-17, Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants. | 22 April 1988 | Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants. |
| ML042240487 | 28 February 1988 | NUREG/CP-0091, Vol 6, Fifteenth Water Reactor Safety Information Meeting: Decontamination and Decommissioning, Accident Management, and TMI-2, Held at Gaithersburg, MD, October 26-29, 1987 |
| NRC Generic Letter 1986-01 | 3 January 1986 | NRC Generic Letter 1986-001: Safety Concerns Associated with Pipe Breaks in the BWR Scram System |
| ML20132F214 | 31 October 1984 | Long-Term Corrosion Test Program of Nuclear Steam Generator Tubing Samples from TMI-1, Vols 1 & 2 |
| ML20094C273 | 3 August 1984 | Proposed Findings of Fact,Conclusions of Law & Brief in Form of Proposed Initial Decision Re Steam Generator Repair. Certificate of Svc Encl |
| ML19210A609 | 3 October 1975 | Tech Spec Change Request 5,Amend 3 Supporting Licensee Request to Change DPR-50,App a Re AEC to NRC Name Change, Util Organization Changes,Section 6 Consistency & Reg Guide 1.16 Revision.Certificate of Svc Encl |