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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 10CFR2.7905 May 1999Crystal RiverRev 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 Considerations15 June 2011Crystal RiverAttachments 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 1995Crystal RiverForwards 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,Encl16 June 1998Crystal RiverAdvises 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 OTSG18 June 1998Crystal RiverApplication 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 Reactors26 July 2004Crystal River60-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 87-0610 July 1987Crystal RiverSubmits 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 Generators28 August 2008Crystal RiverLicense 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 NRC20 August 1997Crystal RiverForwards 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 Criteria9 September 2005Crystal RiverLicense 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 Information4 September 2013Crystal RiverLicense 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 Reduced13 September 1989Crystal RiverDiscusses 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 TS15 October 1993Crystal RiverProposed Tech Specs Reflecting Results of Numerous Meetings Re Improved TS
3F1202-03, Response to Request for Additional Information Regarding Fall 2001 Steam Generator Inspection2 December 2002Crystal RiverResponse 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 Information21 December 2006Crystal RiverLicense 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 38 December 1994Crystal RiverForwards Rev 21 to Final Safety Analysis Rept for Crystal River Unit 3
BSEP 04-0109, Report of 10CFR50.59 Evaluation and Commitment Changes27 August 2004BrunswickReport 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 2005BrunswickRequest 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 2005BrunswickRequest for License Amendment Technical Specification 3.4.5, RCS Leakage Detection Instrumentation.
BSEP 06-0044, Submittal of Technical Specification Bases Revisions13 April 2006BrunswickSubmittal 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 Instrumentation12 July 2011BrunswickLicense 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 Program29 June 2016BrunswickSupplement 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 2017BrunswickApplication 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 Plant8 August 1997BrunswickResponds 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 Encl13 October 1997BrunswickSuppl 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 2015CatawbaRelief 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/5000/0018 March 2016CatawbaEmergency 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 17-119 April 2017CatawbaEmergency Plan, Revision 17-1
CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations25 May 2017CatawbaThird Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations
CNS-18-017, Emergency Plan, Revision 18-1 and 18-224 March 2018CatawbaEmergency Plan, Revision 18-1 and 18-2
ENS 5257324 February 2017 00:22:00McGuireTechnical Specification Shutdown Due to Rcs Pressure Boundary Leakage
ENS 5719527 June 2024 12:04:00CookAutomatic 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 Integrity2 April 2002HarrisDay 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 Integrity15 May 2002Harris60-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 Programs12 September 2002Harris30-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 2003HarrisLetter 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 Reactors27 July 2004HarrisDay 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 Integrity23 May 2006HarrisLicense 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 Integrity3 October 2006HarrisResponse 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 Integrity24 October 2006HarrisResponse 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 Welds31 January 2007HarrisInspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds
HNP-12-130, Transmittal of Technical Specifications Bases6 December 2012HarrisTransmittal 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 Process24 April 2014HarrisApplication 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 Bases18 May 2015HarrisTransmittal 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 Program5 February 2016HarrisResponse 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 Bases10 August 2016HarrisTransmittal of Technical Specification Bases
IR 05000261/201300531 January 2014RobinsonIR 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 05000261/20170015 May 2017RobinsonNRC Integrated Inspection Report 05000261/2017001
IR 05000269/200200225 July 2002OconeeIR 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 05000269/20030025 May 2003OconeeIR 05000269-03-002, IR 05000270-03-002, IR 05000287-03-002, on 01/05/ - 04/05/2003, Duke Energy Corporation; Oconee; Fire Protection