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 Issue dateTitle
ML15224B2864 September 2015Nuclear Generating Plant - Issuance of Amendment for Operating License and Technical Specification Based on Permanently Shutdown and Defueled Status
3F0913-04, License Amendment Request 315, Revision 0, Permanently Defueled Emergency Plan and Emergency Action Level Scheme, and Request for Exemption to Certain Radiological Emergency Response Plan Requirements Defined by 10 CFR 5026 September 2013License Amendment Request #315, Revision 0, Permanently Defueled Emergency Plan and Emergency Action Level Scheme, and Request for Exemption to Certain Radiological Emergency Response Plan Requirements Defined by 10 CFR 50
3F1112-04, Revisions to the Radiological Emergency Response Plan Implementing Procedures21 November 2012Revisions to the Radiological Emergency Response Plan Implementing Procedures
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 2011Attachments 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
3F1210-11, Radiological Emergency Response Plan, Revision 3023 December 2010Radiological Emergency Response Plan, Revision 30
3F1109-07, Relief Request 09-004-II, Revision 013 November 2009Relief Request 09-004-II, Revision 0
ML08067044714 February 2008Rtk Exam - 05000302-08-301 Final Admin JPMs
ML07141010216 May 2007Tech Spec Pages for Amendment 223 Regarding Steam Generator Tube Inspection Program
3F0307-07, License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information14 March 2007License Amendment Request #264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information
3F0207-07, Pressurizer Dissimilar Welds and Reactor Coolant System Leakage Monitoring22 February 2007Pressurizer Dissimilar Welds and Reactor Coolant System Leakage Monitoring
3F0107-04, Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds29 January 2007Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds
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 2006License Amendment Request #264, Revision 1: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information
3F0506-03, License Amendment Request 264, Revision 0, Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity25 May 2006License Amendment Request #264, Revision 0, Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity
3F0506-05, 2005 Technical Specifications Bases Control Program2 May 20062005 Technical Specifications Bases Control Program
ML04026001619 January 2004Request for Review of BAW-2441, Revision 2, Risk Informed Justification for LCO End-State Changes.
ML03294045529 August 2003August Exam 50-302/2003-301 Draft JPMs & Outlines
ML03294040929 August 2003August Exam 50-302/2003-301 Draft SRO Exam
ML03258031229 August 2003August Exam 50-302/2003-301 SRO Written Exam
ML03294040129 August 2003August Exam 50-302/2003-301 Final Combined Ro/Sro Written Exam with Kas, Answers, References, & Analysis
ML03294044029 August 2003August Exam 50-302/2003-301 Final JPMs
3F0103-03, Response to Request for Additional Information, Bulletin 2002-01, Reactor Pressure Vessel Degradation & Reactor Coolant Pressure Boundary Integrity28 January 2003Response to Request for Additional Information, Bulletin 2002-01, Reactor Pressure Vessel Degradation & Reactor Coolant Pressure Boundary Integrity
3F0702-07, License Amendment Request 257, Revision 0, Emergency Diesel Generator Allowed Outage Time Extension.3 July 2002License Amendment Request #257, Revision 0, Emergency Diesel Generator Allowed Outage Time Extension.
3F0602-05, Response to Request for Additional Information 263, Revision 0, Relocation of Reactor Coolant System Parameters to Core Operating Limits Report & 20 Percent Steam Generator Tube Plugging5 June 2002Response to Request for Additional Information #263, Revision 0, Relocation of Reactor Coolant System Parameters to Core Operating Limits Report & 20 Percent Steam Generator Tube Plugging
3F0502-06, Technical Specifications Bases Control Program31 May 2002Technical Specifications Bases Control Program
3F0502-01, Day Response to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.15 May 2002Day Response to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
IR 05000302/199900513 September 1999Insp Rept 50-302/99-05 on 990704-0814.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support
ML20211L13231 August 1999EAL Basis Document
ML20209F56031 July 1999EAL Basis Document, for Jul 1999
IR 05000302/19990034 June 1999Insp Rept 50-302/99-03 on 990411-0522.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation.Major Areas Inspected:Aspects of Licensee Maint, Operations,Engineering & Plant Support
ML20195B80926 May 1999Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS
ML20154C15830 September 1998Proposed Tech Specs Pages Re LAR 238,to Correct RCS Leakage Detection Capability of RB Atmosphere Gaseous Radioactivity Monitor Described in ITS Bases & FSAR
ML20236W65031 July 1998Emergency Action Level Basis Document
ML20203D16120 February 1998Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS
ML20212F26731 October 1997LAR 214,rev 0 to License DPR-72,proposing Changes to Improved TS & Bases Pages Re Decay Heat Removal Requirements in Mode 4.List of Commitments Also Encl
IR 05000302/199730016 July 1997NRC Operator Licensing Exam Rept 50-302/97-300 for Tests Administered on 970616-19.Out of Four SRO Candidates,Three Passed Written Exams & One Failed
ML20137X53618 April 1997Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS
ML20137G82927 March 1997Proposed Tech Specs 3.4.12 Re RCS Operational Leakage,Ts 5.6 Re Procedures,Programs & Manuals & TS 5.7 Re Reporting Requirements
3F1096-02, Submits Partial Response to RAI Re Potential Overpressurization of Nuclear Svc Closed Cycle Cooling Sys. Rept 0920-208-01,Rev 0, Evaluation of SW Overpressurization Overpressurization, Dtd 920730,encl8 October 1996Submits Partial Response to RAI Re Potential Overpressurization of Nuclear Svc Closed Cycle Cooling Sys. Rept 0920-208-01,Rev 0, Evaluation of SW Overpressurization Overpressurization, Dtd 920730,encl
3F0496-02, Provides Answers to Questions Received in NRC 960111 RAI & Responses to Addl Questions & Request for Documents Received at 960208 Meeting Re Calculation Which Forms Basis for Mut Pressure/Level Limit Curve in Operating Procedure OP-103B4 April 1996Provides Answers to Questions Received in NRC 960111 RAI & Responses to Addl Questions & Request for Documents Received at 960208 Meeting Re Calculation Which Forms Basis for Mut Pressure/Level Limit Curve in Operating Procedure OP-103B
ML20101F59021 March 1996Rev 2 to Proposed Ts,Consisting of Change Request 203, Allowing Restart from Current Refueling Outage
ML20101F63917 March 1996Rev 1 to Proposed Ts,Consisting of Change Request 203, Providing Addl Assurance of Tube Leakage Integrity & Committing to Performing in-situ Pressure Testing of Representative Sample of Tube Indications
3F1093-12, Proposed Tech Specs Reflecting Results of Numerous Meetings Re Improved TS15 October 1993Proposed Tech Specs Reflecting Results of Numerous Meetings Re Improved TS
ML20126F21511 December 1992Insp Rept 50-302/92-27 on 921018-1114.Violations Noted.Major Areas Inspected:Plant Operations,Security,Radiological Controls,Licensee Event Repts,Plant Mods & Licensee Action on Previous Insp Items
NUREG-1434, Forwards Preliminary,Unedited Copy of Section 3.6 Bases for BWR Owners Group BWR/4 & BWR/6 Versions of New STS2 June 1992Forwards Preliminary,Unedited Copy of Section 3.6 Bases for BWR Owners Group BWR/4 & BWR/6 Versions of New STS
IR 05000302/199003620 February 1991Insp Rept 50-302/90-36 on 901219-910125.No Violations Noted. Major Areas Inspected:Plant Operations,Security,Radiological Controls,Lers,Maint & Surveillance Activities
ML20011F17321 February 1990LER 90-001-00:on 900221,RCS Leakage Calculations Indicated That Unidentified Leakage Exceeded Tech Spec Limits.Caused by Failed Packing on Block Valve.Valve Repacked During Feb 1990 Maint outage.W/900221 Ltr
ML20006G00921 February 1990Special Rept 90-02:on 900122,plant Shutdown Initiated Due to Unidentified Leakage in Rcs.Dose Equivalent Iodine Exceeded Tech Spec Limit.Sampling & Analysis of RCS Continued at 4 H Intervals Until Iodine Decreased to Below Tech Spec Levels
ML20011E69931 January 1990Monthly Operating Rept for Jan 1990 for Crystal River Unit 3.W/900212 Ltr
ML19325E81031 October 1989Application for Amend to License DPR-72,consisting of Tech Spec Change Request 174 Re Proposed Heatup,Cooldown & Inservice Leak & Hydrostatic Testing Pressure/Temp Limits. Rept Re Low Temp Overpressure Protection Withheld
ML20247F54111 September 1989Proposed Tech Specs,Deleting Radiological Effluent Tech Specs Requirements