Semantic search
Jump to navigation
Jump to search
Issue date | Title | |
---|---|---|
ML15224B286 | 4 September 2015 | Nuclear 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 50 | 26 September 2013 | 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 50 |
3F1112-04, Revisions to the Radiological Emergency Response Plan Implementing Procedures | 21 November 2012 | Revisions 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 Considerations | 15 June 2011 | 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 |
3F1210-11, Radiological Emergency Response Plan, Revision 30 | 23 December 2010 | Radiological Emergency Response Plan, Revision 30 |
3F1109-07, Relief Request 09-004-II, Revision 0 | 13 November 2009 | Relief Request 09-004-II, Revision 0 |
ML080670447 | 14 February 2008 | Rtk Exam - 05000302-08-301 Final Admin JPMs |
ML071410102 | 16 May 2007 | Tech 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 Information | 14 March 2007 | License 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 Monitoring | 22 February 2007 | Pressurizer Dissimilar Welds and Reactor Coolant System Leakage Monitoring |
3F0107-04, Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds | 29 January 2007 | Inspection 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 Information | 21 December 2006 | License 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 Integrity | 25 May 2006 | License Amendment Request #264, Revision 0, Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity |
3F0506-05, 2005 Technical Specifications Bases Control Program | 2 May 2006 | 2005 Technical Specifications Bases Control Program |
ML040260016 | 19 January 2004 | Request for Review of BAW-2441, Revision 2, Risk Informed Justification for LCO End-State Changes. |
ML032940455 | 29 August 2003 | August Exam 50-302/2003-301 Draft JPMs & Outlines |
ML032940409 | 29 August 2003 | August Exam 50-302/2003-301 Draft SRO Exam |
ML032580312 | 29 August 2003 | August Exam 50-302/2003-301 SRO Written Exam |
ML032940401 | 29 August 2003 | August Exam 50-302/2003-301 Final Combined Ro/Sro Written Exam with Kas, Answers, References, & Analysis |
ML032940440 | 29 August 2003 | August 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 Integrity | 28 January 2003 | Response 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 2002 | License 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 Plugging | 5 June 2002 | 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 Plugging |
3F0502-06, Technical Specifications Bases Control Program | 31 May 2002 | Technical 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 2002 | Day Response to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. |
IR 05000302/1999005 | 13 September 1999 | Insp Rept 50-302/99-05 on 990704-0814.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support |
ML20211L132 | 31 August 1999 | EAL Basis Document |
ML20209F560 | 31 July 1999 | EAL Basis Document, for Jul 1999 |
IR 05000302/1999003 | 4 June 1999 | Insp 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 |
ML20195B809 | 26 May 1999 | Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS |
ML20154C158 | 30 September 1998 | Proposed Tech Specs Pages Re LAR 238,to Correct RCS Leakage Detection Capability of RB Atmosphere Gaseous Radioactivity Monitor Described in ITS Bases & FSAR |
ML20236W650 | 31 July 1998 | Emergency Action Level Basis Document |
ML20203D161 | 20 February 1998 | Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS |
ML20212F267 | 31 October 1997 | LAR 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 05000302/1997300 | 16 July 1997 | NRC 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 |
ML20137X536 | 18 April 1997 | Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS |
ML20137G829 | 27 March 1997 | Proposed 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,encl | 8 October 1996 | 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,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-103B | 4 April 1996 | 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-103B |
ML20101F590 | 21 March 1996 | Rev 2 to Proposed Ts,Consisting of Change Request 203, Allowing Restart from Current Refueling Outage |
ML20101F639 | 17 March 1996 | Rev 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 TS | 15 October 1993 | Proposed Tech Specs Reflecting Results of Numerous Meetings Re Improved TS |
ML20126F215 | 11 December 1992 | Insp 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 STS | 2 June 1992 | Forwards Preliminary,Unedited Copy of Section 3.6 Bases for BWR Owners Group BWR/4 & BWR/6 Versions of New STS |
IR 05000302/1990036 | 20 February 1991 | Insp Rept 50-302/90-36 on 901219-910125.No Violations Noted. Major Areas Inspected:Plant Operations,Security,Radiological Controls,Lers,Maint & Surveillance Activities |
ML20011F173 | 21 February 1990 | LER 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 |
ML20006G009 | 21 February 1990 | Special 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 |
ML20011E699 | 31 January 1990 | Monthly Operating Rept for Jan 1990 for Crystal River Unit 3.W/900212 Ltr |
ML19325E810 | 31 October 1989 | Application 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 |
ML20247F541 | 11 September 1989 | Proposed Tech Specs,Deleting Radiological Effluent Tech Specs Requirements |