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 Issue dateTitle
RA-23-0218, Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals21 September 2023Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals
IR 05000400/202000427 January 2021Integrated Inspection Report 05000400/2020004
ML21004A2364 January 2021301 Exam Report Items - SRO as Given Written Exam
ML20114E26212 May 2020Final ASP Analysis - Shearon Harris (LER 400-02-004-09)
RA-19-0123, License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications25 July 2019License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications
ML20311A5566 November 20172017 Q1-Q4 ROP Inspection Findings
IR 05000400/201400527 January 2015IR 05000400/2014005; on October 1, 2014, Through December 31, 2014; Duke Energy Progress, Inc., Shearon Harris Nuclear Power Plant, Unit 1, Operability Determinations and Functionality Assessments
ML15013A24513 January 2015Initial Exam 2014-302 Draft Sim_IN-Plant JPMs
ML15013A26713 January 2015Initial Exam 2014-302 Final Sim_IN-Plant JPMs
ML14338A0383 December 2014302 Final SRO Written Exam
ML13295A41617 October 2013301 Initial Exam Final SRO Written Exam
IR 05000400/201300230 April 2013IR 05000400-13-002: Carolina Power and Light Company; on January 1, 2013 - March 31, 2013; Shearon Harris Nuclear Power Plant, Unit 1; Operability Evaluations, Plant Modifications, and Event Follow-up
HNP-12-118, Response to Recommendation 2.3 Flooding Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident27 November 2012Response to Recommendation 2.3 Flooding Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
HNP-12-119, Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident27 November 2012Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML12053A34012 March 2012Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
ML12056A05012 March 2012Enclosure 4 - Recommendation 2.3: Flooding
ML12056A04912 March 2012Enclosure 3 - Recommendation 2.3: Seismic
IR 05000400/20110118 December 2011IR 05000400-11-011, on 08/29/2011 - 09/02/2011 & 09/19-23/2011; Shearon Harris Nuclear Plant, Unit 1; Triennial Fire Protection Inspection Report & Exercise of Enforcement Discretion
ML1121702332 August 2011Initial Exam 2011-301 Final RO Written Exam
IR 05000400/200800221 April 2008IR 05000400-08-002 on 01/01/2008 - 03/31/2008 for Shearon Harris, Unit 1; Routine Integrated Report
ML07150040313 June 20072.206 - Final Director'S Decision Under 10 C.F.R. 2.206, Denying Petitioners' Request to Not Accept the Licensee'S Application for License Renewal at Shearon Harris Plant, Unit 1
ML0707805372 April 2007G20060793 - Shearon Harris 2.206 Petition Proposed Director'S Decision
ML06298010721 September 2006G20060793 - 2.206 Supplement 1 Fire Protection Issues at the Shearon Harris Nuclear Power Plant
ML06264055020 September 2006G20060793 - John D. Runkle E-mail Re 2.206 - Recurring Fire Protection Issues at Shearon Harris Nuclear Plant
ML0533903529 January 2006FRN: All Nuclear Power Plants That Use Hemyc/Mt Fire Barriers Notice of Issuance of Director'S Decision Under 10 CFR 2.206
ML0533903119 January 2006G20050379 - Mr. Paul Gunter Ltr. Re. 2.206 - Inoperable Hemyc/Mt Fire Protection Systems
ML05263041120 October 2005G20050379 - Paul Gunter Ltr 2.206 Inoperable Hemyc/Mt Fire Protection Systems, Proposed Directors Decision
ML05174056227 June 2005G20050379 - Paul Gunter Ltr. 2.206 Inoperable Hemyc/Mt Fire Protection System
ML05152044527 May 2005Significant Adverse Condition Investigation Report
ML05144020912 May 2005G20050379 - Paul Gunter Ltr Re 2.206 - Inoperable Hemyc/Mt Fire Protection Systems
IR 05000400/200300729 April 2005Draft Letter to Carolina Power and Light from Ogle, Shearon Harris Nuclear Power Plant - NRC Fire Protection Inspection Report No. 05000400-2003-007
ML0503804433 February 2005Undated Draft, Revision 4, NRC Fire Protection Inspection Report No. 05000400/2003007
ML04085049419 March 2004Comment (1) of Tony Groblewski Regarding Notice of Clarification of Steam Generator Tube Integrity Event Reporting Guideline in NUREG-1022
ML04236055923 February 2004E-mail, C. Ogle to Eng Branch, Fwd: Peer Review of Inspection Reports
ML04238028416 January 2004E-mail, C. Ogle to Eng Branch, Peer Review of Inspection Reports
ML05038036816 January 2004E-mail from C. Ogle to Eng. Branch - Peer Review of Inspection Reports
ML03338052318 November 2003IR 05000400-03-007, Shearon Harris, on 02/01/03 - 10/21/03, Significance Determination of Fire Protection Findings
ML05152041023 October 2003Action Request 000997103
ML02267015722 March 2002August 2002 Exam 50-400/2002-301 Final Written SRO Exam
ML18016A79429 January 1999LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures9 July 1997Inadequate or Inappropriate Interim Fire Protection Compensatory Measures
ML18011A8052 March 1995LER 95-002-00:on 950207,unanalyzed Condition Existed Re Potential of Loss of Automatic ESF Actuations & Subsequent TS 3.0.3 Entry.Caused by Both Trains of Ssps Declared Inoperable.Plant Evolutions avoided.W/950303 Ltr
ML18010B1043 June 1993Responds to NRC 930506 Ltr Re Violation & Deviation Noted in Insp Rept 50-400/93-08.Corrective Actions:Fuel Pool Cooling Pump QA-SA Placed on Increased Testing Frequency & Maint Procedure MMM-012 Revised
NRC Generic Letter 1992-026 March 1992NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown.
ML0311405497 November 1991Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability
Information Notice 1991-38, Thermal Stratification in Feedwater System Piping13 June 1991Thermal Stratification in Feedwater System Piping
ML18009A4409 April 1990LER 90-006-00:on 900309,discovered That Evolution Violated Requirements of FSAR to Keep Individual Tanks Isolated from Another Tank.Caused by Failure to Address Evolution in Operating Procedure.Procedure revised.W/900409 Ltr
ML18022A7781 March 1990Rept of 10CFR50.59 Chnages to Procedures &/Or Plant Mods for 1989
ML18009A33922 January 1990LER 89-020-00:on 891031,jumper Wires in Limitorque Operator for Pressurizer PORV Block Valve 1RC-117 Found Contaminated W/Grease Leaking from Gear Box.Caused by Overfilling Gear Box.Wires repaired/replaced.W/900122 Ltr
ML18005B07326 September 1989LER 89-015-00:on 890827,discovered That Fuel Handling Bldg Operating Floor Equipment Hatch in Storage Location on Operating Deck Not Installed as Required.Caused by Inadequate Procedure.Procedure revised.W/890926 Ltr
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