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IR 05000269/202100414 February 2022Integrated Inspection Report 05000269/2021004 and 05000270/2021004 and 05000287/2021004 and Apparent Violation
ML20189A07729 June 20208 to Updated Final Safety Analysis Report, Chapter 4, Reactor
ML20189A10829 June 20208 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses
ML20189A10929 June 20208 to Updated Final Safety Analysis Report, Chapter 15, Appendix 15A. Tables
ML19260E08431 October 2019Issuance of Amendments 415, 417, and 416, Regarding the Updated Final Safety Analysis Report Description of Tornado Mitigation
ML19242C72828 August 2019Attachments 5 - 12: Thermal-Hydraulic Models for High Energy Line Break Transient Analysis, Duke Energy/Framatome Affidavits, Regulatory Requirements, Definitions, Time Critical Operator Actions and Feasibility Assessment for New Proposed T
RA-18-0026, Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Sections Associated with the Oconee Tornado Licensing Basis14 September 2018Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Sections Associated with the Oconee Tornado Licensing Basis
ML18192A98031 December 2017Revision 27 to Updated Final Safety Analysis Report, Chapter 15, Appendix 15A, Tables
ML18192A91031 December 2017Revision 27 to Updated Final Safety Analysis Report, Chapter 4, Reactor
ML18192A97831 December 2017Revision 27 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses
ML17202U79130 August 2017Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
ML17166A26011 July 2017Flood Hazard Mitigation Strategies Assessment (CAC Nos. MF7950, MF7951 and MF7952) Public
ML15177A37226 June 2015NRC Request to Receive Oconee LOCA Summary Report
ML14206A79013 August 2014Issuance of Amendments Regarding Implementation of the Protected Service Water System
ONS-2014-080, License Amendment Request (LAR) to Reduce Allowed Maximum Rated Thermal Power When High Pressure Injection (HPI) Equipment Is Inoperable License Amendment Request No. 2013-0330 June 2014License Amendment Request (LAR) to Reduce Allowed Maximum Rated Thermal Power When High Pressure Injection (HPI) Equipment Is Inoperable License Amendment Request No. 2013-03
ML14084A03621 March 2014Initial Exam 2013-302 Draft SRO Written Exam
ML14084A03521 March 2014Iinitial Exam 2013-302 Draft RO Written Exam
IR 05000269/20130056 February 2014IR 05000269-13-005, 05000270-13-005, 05000287-13-005; 05000269-13-502, 05000270-13-502, 05000287-13-502; on 10/01/2013 - 12/31/2013; Oconee Nuclear Station Units 1, 2 and 3; Problem Identification and Resolution
ML13364A33730 December 2013302 Initial Exam Final SRO Written Exam
ML13364A33530 December 2013302 Initial Exam Final RO Written Exam
IR 05000269/201200331 July 2012IR 05000269-12-003, 05000270-12-003, 05000287-12-003; 04/01/2012 - 6/30/2012; Oconee Nuclear Station Units 1, 2 and 3; Adverse Weather Protection
IR 05000269/20120027 May 2012IR 05000269-12-002, 05000270-12-002, 05000287-12-002, on 01/01/2012 - 3/31/2012; Oconee Nuclear Station; Maintenance Effectiveness, Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications, Problem Identification and
ML10022001628 January 2010Issuance of Amendment Nos. 366, 368, and 367, Reactor Protective System and Engineered Safeguard Protection System Digital Upgrade
ML0921706842 September 2009Request for Withholding Information from Public Disclosure for Oconee Nuclear Station, Units 1, 2, and 3 Regarding Reactor Protective Systems/ Engineered Safeguards Protective System Digital Upgrade (Tac Nos. MD7999, MD8000, and MD8001) - S
ML0910503313 April 2009Supplemental Request for Additional Information for License Amendment Request for Reactor Protective System/Engineered Safeguards Protective System Digital Upgrade, Technical Specification Change Number 2007-09, Supplement 15
ML08308008928 October 2008License Amendment Request for Reactor Protective System/Engineered Safeguards Protective System Digital Upgrade, Technical Specification Change Number 2007-09, Supplement 9
IR 05000269/200700531 January 2008IR-05000269-07-005, 05000270-07-005, 05000287-07-005 on 10/10/2007 - 12/31/07 for Ocenee, Units 1,2 & 3; Refueling & Outage Activities
IR 05000269/200700330 July 2007IR 05000269-07-003, 05000270-07-003 & 05000287-07-003, on 04/01/2007 - 06/30/2007, Oconee, Units 1, 2, and 3, Licensed Operator Requalification, Maintenance Effectiveness, Radioactive Material
IR 05000269/200600530 January 2007IR 05000269-06-005, 05000270-06-005, 05000287-06-005, on 10/01/2006 - 12/31/2006, Oconee, Units 1, 2, and 3
IR 05000269/200600426 October 2006IR 05000269-06-004, IR 05000270-06-004, and IR 05000287-06-004, on 07/01/2006 - 09/30/2006, Duke Power Company
IR 05000269/200600328 July 2006IR 05000269-06-003, IR 05000270-06-003, IR 050000287-06-003, 04/01/06 - 06/30/06; Oconee, Units 1, 2, & 3; Inservice Inspection Activities, Radioactive Gaseous and Liquid Effluent Monitoring System, Event Followup, and Other Activities
ML05174015631 May 2005DPC-NE-3005-A, Revision 2, Oconee Nuclear Station, UFSAR Chapter 15 Transient Analysis Methodology.
ML05032003130 September 2004DPC-NE-3003-A, Revision 1, Mass and Energy Release and Containment Response Methodology.
ML04190039430 June 2004Site - 2003 Annual Report
IR 05000269/200400226 April 2004IR 05000269-04-002, 05000270-04-002 & 05000287-04-002, on 12/28/2003 - 03/27/2004, Oconee Nuclear Station Units1, 2 & 3, Seneca, Sc; Personnel Performance During Nonroutine Plant Evolutions, & Surveillance Testing
IR 05000269/200300424 October 2003IR 05000269-03-004, IR 05000270-03-004, IR 05000287-03-004, on 06/29/2003-09/27/2003, Oconee Nuclear Station, Units 1, 2, and 3, Licensed Operator Requalification
ML03149046921 March 2003Revisions to Topical Reports DPC-NE-3000 and 3005 in Support of Steam Generator Replacement Response to NRC Staff Request for Additional Information
ML03083044320 March 2003Meeting, Handouts for Discussion of June 7, 2002, Submittal on Tornado Mitigation
ML20236T51720 July 1998Proposed Tech Specs Re one-time Extension to Functional Test Frequencies for Hydraulic & Mechanical Snubbers
Information Notice 1996-45, Potential Common-Mode Post-Accident Failure of Containment Coolers12 August 1996Potential Common-Mode Post-Accident Failure of Containment Coolers
ML20148D97614 January 1988Forwards Response to IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. Summary of Schedule for Responding to Bulletin for McGuire & Catawba Stated
NRC Generic Letter 1987-1612 November 1987NRC Generic Letter 1987-016: Transmittal of NUREG-1262, Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses
ML20211G94330 December 1985Preliminary Development of an Integrated Approach to the Evaluation of Pressurized Thermal Shock as Applied to the Oconee Unit 1 Nuclear Power Plant
ML20209E51730 April 1985Dominant Accident Sequences in OCONEE-1 Pressurized Water Reactor
ML20062P04410 January 1980Discusses B&W Overfeed Transient Analysis Using IRT Deck Simulating Facilities.Figures 1-9 Re Computed Transient Results Encl
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