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| Issue date | Title | |
|---|---|---|
| IR 05000400/2022002 | 5 August 2022 | Integrated Inspection Report 05000400/2022002 |
| ML21004A236 | 4 January 2021 | 301 Exam Report Items - SRO as Given Written Exam |
| IR 05000400/2018002 | 7 September 2018 | Errata - Shearon Harris Nuclear Power Plant - Nuclear Regulatory Commission Integrated Inspection Report 005000400/2018002 |
| ML18222A165 | 10 August 2018 | Nuclear Regulatory Commission Integrated Inspection Report 05000400/2018002 |
| 05000400/LER-2016-006 | 14 December 2016 | Reactor Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking and a Weld Fabrication Void LER 16-006-00 For Shearon Harris Nuclear Plant, Unit 1 Regarding Reactor Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking and a Weld Fabrication Void |
| ML13017A349 | 28 January 2013 | Relief Request I3R-10 for Spent Fuel Pool Cooling Piping Inservice Inspection Program - Third 10-Year Interval |
| ML12318A396 | 13 November 2012 | NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit No. 1 - Acceptance Review or Relief Request I3R-10 Spent Fuel Pool Cooling Piping Inservice Inspection Program - Third Interval (Tac. ME9892) |
| HNP-12-099, Relief Request I3R-10 Spent Fuel Pool Cooling Piping Inservice Inspection Program - Third Interval | 8 November 2012 | Relief Request I3R-10 Spent Fuel Pool Cooling Piping Inservice Inspection Program - Third Interval |
| ML090060737 | 30 November 2008 | NUREG-1916, Volume 1, (2:2) Chpt 3 - End, Safety Evaluation Report Related to the License Renewal of Shearon Harris Nuclear Power Plant, Unit 1 |
| ML081830260 | 1 July 2008 | Meeting Minutes of the ACRS Plant License Renewal Subcommittee Regarding Shearon Harris, May 7, 2008 |
| ML071260037 | 4 June 2007 | Bl 2004-01 Closeout Letter for Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations |
| ML052060215 | 1 August 2005 | Ltr., Bulletin 2003-02 Response Leakage from RPV Lh Penetrations and RCPB Integrity (Tac No. MC0541) |
| HNP-04-166, Day Report, 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, Request (2) | 14 January 2005 | Day Report, 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, Request (2) |
| HNP-04-154, Day Summary Report NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity, Request (2) | 13 January 2005 | Day Summary Report NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity, Request (2) |
| HNP-04-097, Day Response to NRC Bulletin 2004-01 for the Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-water Reactors | 27 July 2004 | Day Response to NRC Bulletin 2004-01 for the Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-water Reactors |
| HNP-03-118, 90-Day Response to NRC Bulletin 2003-02 for Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity | 13 November 2003 | 90-Day Response to NRC Bulletin 2003-02 for Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity |
| HNP-02-164, Letter from James Scarola, Harris Nuclear Plant - - Request for Additional Information, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. | 24 January 2003 | Letter from James Scarola, Harris Nuclear Plant - - Request for Additional Information, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. |
| HNP-02-118, 30-Day Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs | 12 September 2002 | 30-Day Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs |
| HNP-02-063, 60-Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity | 15 May 2002 | 60-Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity |
| HNP-02-052, Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity | 2 April 2002 | Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity |
| ML18016A963 | 25 May 1999 | Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend |
| ML18016A288 | 27 January 1998 | Forwards Rev 0 to Procedure HNP-ISI-002, Shearon Harris Nuclear Power Plant,Isi Program Plan,2nd Interval. Plan Describes Exams & Schedules for Performing ASME Code Insps of Class 1,2 & 3 Components & Supports |
| ML18012A475 | 24 January 1997 | Forwards Revised Request for Relief from ISI Requirements for ASME Code Case N-522 |
| ML18018B899 | 13 February 1985 | Requests NRC Approval for Use of Alternate Approach to Existing Guidelines in SRP 3.6.2 Re Postulation of Arbitrary Intermediate Pipe Breaks in Class 1,2 & 3 Pipes.Technical Basis for Elimination of Breaks Encl |
| ML18018A469 | 16 March 1983 | Forwards Minutes of 830201-03 Meetings W/Mechanical Engineering Branch to Respond to Questions Transmitted in 821222 Ltr.Responses Committing to FSAR Change Will Be Incorporated Into Future Amend |
| ML18230A100 | 26 September 1975 | Transmits 8/5/1975 Nrc/Cp&L/Ebasco Meeting Minutes & Isometric Drawing of Main Steam & Feedwater Piping in Tunnel Area. Advises CP&L Will Use Meeting Minute as General Pipe Rupture Design Criteria |