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3F0599-02, Rev 0 to LAR 249 to License DPR-72,proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of Otsgs.B&Wog Proprietary Topical Rept BAW-2346P,Rev 0 Encl.Rept Withheld,Per 10CFR2.790 | 5 May 1999 | Crystal River | Rev 0 to LAR 249 to License DPR-72,proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of Otsgs.B&Wog Proprietary Topical Rept BAW-2346P,Rev 0 Encl.Rept Withheld,Per 10CFR2.790 |
3F0611-02, Attachments 1, 2 & 3, 4 & 6 Crystal River Unit 3, License Amendment Request 309, Revision 0 Attachment 1, Description of Proposed Change, Background, Justification for the Request, Determination of No Significant Hazards Considerations | 15 June 2011 | Crystal River | Attachments 1, 2 & 3, 4 & 6 Crystal River Unit 3, License Amendment Request #309, Revision 0 Attachment 1, Description of Proposed Change, Background, Justification for the Request, Determination of No Significant Hazards Considerations |
3F0695-03, Forwards Response to GL-95-03, Circumferential Cracking of SG Tubes, Per 10CFR50.54(f) | 22 June 1995 | Crystal River | Forwards Response to GL-95-03, Circumferential Cracking of SG Tubes, Per 10CFR50.54(f) |
3F0698-25, Advises That FPC May Be Requesting Enforcement Discretion or Other Regulatory Action in Near Future,Based on Review of Industry Operating Experience.Evaluation of Crystal River, Unit 3,operation W/Tube End Anomalies,Encl | 16 June 1998 | Crystal River | Advises That FPC May Be Requesting Enforcement Discretion or Other Regulatory Action in Near Future,Based on Review of Industry Operating Experience.Evaluation of Crystal River, Unit 3,operation W/Tube End Anomalies,Encl |
3F0698-28, Application for Amend to License DPR-72,exigent LAR 228,rev 0,proposing one-time Exigent License Amend to Allow Operation W/Number of Indications Previously Identified as Tube End Anomalies & Multiple Tube End Anomalies in OTSG | 18 June 1998 | Crystal River | Application for Amend to License DPR-72,exigent LAR 228,rev 0,proposing one-time Exigent License Amend to Allow Operation W/Number of Indications Previously Identified as Tube End Anomalies & Multiple Tube End Anomalies in OTSG |
3F0704-11, 60-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 | 26 July 2004 | Crystal River | 60-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 |
3F0787-04, Submits List of All Pressure Isolation Valves & Description of Periodic Tests or Other Measures Performed to Detect Leakage,Acceptance Criteria for Leakage,Operational Limits & Test Frequency,Per Generic Ltr 87-06 | 10 July 1987 | Crystal River | Submits List of All Pressure Isolation Valves & Description of Periodic Tests or Other Measures Performed to Detect Leakage,Acceptance Criteria for Leakage,Operational Limits & Test Frequency,Per Generic Ltr 87-06 |
3F0808-01, License Amendment Request 301, Revision 0, Application to Modify Improved Technical Specifications for Replacement Steam Generators | 28 August 2008 | Crystal River | License Amendment Request #301, Revision 0, Application to Modify Improved Technical Specifications for Replacement Steam Generators |
3F0897-10, Forwards Description of Changes,Reason for Request & Evaluation of Request Re TS Change Request Notice 211,Rev 1, in Response to NRC | 20 August 1997 | Crystal River | Forwards Description of Changes,Reason for Request & Evaluation of Request Re TS Change Request Notice 211,Rev 1, in Response to NRC |
3F0905-06, License Amendment Request 290, Revision 2 Re Probabilistic Methodology to Determine the Contribution to Main Steam Line Break Leakage Rates for the Once-Through Steam Generator from the Tube End Crack Alternate Repair Criteria | 9 September 2005 | Crystal River | License Amendment Request #290, Revision 2 Re Probabilistic Methodology to Determine the Contribution to Main Steam Line Break Leakage Rates for the Once-Through Steam Generator from the Tube End Crack Alternate Repair Criteria |
3F0913-02, License Amendment Request 313, Revision 1, Revision to Improved Technical Specifications Administrative Controls for Permanently Defueled Conditions and Response to Requests for Additional Information | 4 September 2013 | Crystal River | License Amendment Request #313, Revision 1, Revision to Improved Technical Specifications Administrative Controls for Permanently Defueled Conditions and Response to Requests for Additional Information |
3F0989-01, Discusses Rev to FSAR Radiological Consequences.Changes Establish Revised Licensing Basis for LOCA & Letdown Line Failure Accident Radiological Consequences,Recognizing That Margins Established by 10CFR100 Have Not Been Reduced | 13 September 1989 | Crystal River | Discusses Rev to FSAR Radiological Consequences.Changes Establish Revised Licensing Basis for LOCA & Letdown Line Failure Accident Radiological Consequences,Recognizing That Margins Established by 10CFR100 Have Not Been Reduced |
3F1093-12, Proposed Tech Specs Reflecting Results of Numerous Meetings Re Improved TS | 15 October 1993 | Crystal River | Proposed Tech Specs Reflecting Results of Numerous Meetings Re Improved TS |
3F1202-03, Response to Request for Additional Information Regarding Fall 2001 Steam Generator Inspection | 2 December 2002 | Crystal River | Response to Request for Additional Information Regarding Fall 2001 Steam Generator Inspection |
3F1206-02, License Amendment Request 264, Revision 1: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information | 21 December 2006 | Crystal River | License Amendment Request #264, Revision 1: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information |
3F1294-01, Forwards Rev 21 to Final Safety Analysis Rept for Crystal River Unit 3 | 8 December 1994 | Crystal River | Forwards Rev 21 to Final Safety Analysis Rept for Crystal River Unit 3 |
BSEP 04-0109, Report of 10CFR50.59 Evaluation and Commitment Changes | 27 August 2004 | Brunswick | Report of 10CFR50.59 Evaluation and Commitment Changes |
BSEP 05-0059, Request for Notice of Enforcement Discretion Technical Specification 3.4.5, RCS Leakage Detection Instrumentation. | 13 May 2005 | Brunswick | Request for Notice of Enforcement Discretion Technical Specification 3.4.5, RCS Leakage Detection Instrumentation. |
BSEP 05-0060, Request for License Amendment Technical Specification 3.4.5, RCS Leakage Detection Instrumentation. | 17 May 2005 | Brunswick | Request for License Amendment Technical Specification 3.4.5, RCS Leakage Detection Instrumentation. |
BSEP 06-0044, Submittal of Technical Specification Bases Revisions | 13 April 2006 | Brunswick | Submittal of Technical Specification Bases Revisions |
BSEP 11-0068, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation | 12 July 2011 | Brunswick | License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation |
BSEP 16-0047, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program | 29 June 2016 | Brunswick | Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program |
BSEP 17-0060, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. | 29 June 2017 | Brunswick | Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. |
BSEP-97-0355, Responds to 970702 RAI Re Conversion to Improved TS for Plant | 8 August 1997 | Brunswick | Responds to 970702 RAI Re Conversion to Improved TS for Plant |
BSEP-97-0443, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433.Rev a to Improved TS & Revised Responses to 970808 & 970911 RAIs Also Encl | 13 October 1997 | Brunswick | Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433.Rev a to Improved TS & Revised Responses to 970808 & 970911 RAIs Also Encl |
CNS-15-062, Relief Request Serial Number 15-CN-001, Proposed Alternative Repair for Main Steam System Braided Flex-Hose - Submitted Pursuant to 10 CFR 50.55a(z)(2) | 16 July 2015 | Catawba | Relief Request Serial Number 15-CN-001, Proposed Alternative Repair for Main Steam System Braided Flex-Hose - Submitted Pursuant to 10 CFR 50.55a(z)(2) |
CNS-16-016, Emergency Plan Implementing Procedures, Including Revision 035 to RP/0/A/5000/001 and Revision 036 to RP/0/A/5000/001 | 8 March 2016 | Catawba | Emergency Plan Implementing Procedures, Including Revision 035 to RP/0/A/5000/001 and Revision 036 to RP/0/A/5000/001 |
CNS-17-013, Emergency Plan, Revision 17-1 | 19 April 2017 | Catawba | Emergency Plan, Revision 17-1 |
CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations | 25 May 2017 | Catawba | Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations |
CNS-18-017, Emergency Plan, Revision 18-1 and 18-2 | 24 March 2018 | Catawba | Emergency Plan, Revision 18-1 and 18-2 |
ENS 52573 | 24 February 2017 00:22:00 | McGuire | Technical Specification Shutdown Due to Rcs Pressure Boundary Leakage |
ENS 57195 | 27 June 2024 12:04:00 | Cook | Automatic Start of Turbine Driven Auxiliary Feedwater Pump |
HNP-02-052, Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity | 2 April 2002 | Harris | Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity |
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 | Harris | 60-Day Response to NRC 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 | Harris | 30-Day Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs |
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 | Harris | 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-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 | Harris | 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-06-060, License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity | 23 May 2006 | Harris | License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity |
HNP-06-116, Response to Request for Additional Information Regarding License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity | 3 October 2006 | Harris | Response to Request for Additional Information Regarding License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity |
HNP-06-126, Response to Request for Additional Information (RAI) Regarding License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity | 24 October 2006 | Harris | Response to Request for Additional Information (RAI) Regarding License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity |
HNP-07-015, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds | 31 January 2007 | Harris | Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds |
HNP-12-130, Transmittal of Technical Specifications Bases | 6 December 2012 | Harris | Transmittal of Technical Specifications Bases |
HNP-14-050, Application to Revise Technical Specifications to Adopt TSTF-510-A, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process | 24 April 2014 | Harris | Application to Revise Technical Specifications to Adopt TSTF-510-A, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process |
HNP-15-046, Transmittal of Technical Specifications Bases | 18 May 2015 | Harris | Transmittal of Technical Specifications Bases |
HNP-16-011, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications by Relocating Specific Surveillance Frequency Requirements to a Licensee Controlled Program | 5 February 2016 | Harris | Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications by Relocating Specific Surveillance Frequency Requirements to a Licensee Controlled Program |
HNP-16-064, Transmittal of Technical Specification Bases | 10 August 2016 | Harris | Transmittal of Technical Specification Bases |
IR 05000261/2013005 | 31 January 2014 | Robinson | IR 05000261-13-005 and 05000261-13-502, on 10/01/2013 - 12/31/2013; H.B. Robinson Steam Electric Plant, Unit 2; Adverse Weather Protection, Refueling and Outage Activities, and Radiological Hazard Assessment and Exposure. |
IR 05000261/2017001 | 5 May 2017 | Robinson | NRC Integrated Inspection Report 05000261/2017001 |
IR 05000269/2002002 | 25 July 2002 | Oconee | IR 05000269-02-002, IR 05000270-02-002 & IR 05000287-02-002, on 03/31/2002-06/29/2002, Duke Energy Corporation, Oconee Nuclear Station; Inservice Inspection and Other Activities.. Two non-cited Violations Identified |
IR 05000269/2003002 | 5 May 2003 | Oconee | IR 05000269-03-002, IR 05000270-03-002, IR 05000287-03-002, on 01/05/ - 04/05/2003, Duke Energy Corporation; Oconee; Fire Protection |