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| Issue date | Title | |
|---|---|---|
| ML12314A392 | 31 October 2012 | 17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 1 of 250 Through Page 80 of 250 |
| 3F0812-05, Interim Report of the Evaluation of a Deviation Pursuant to 10 CFR 21.21(a)(2) | 21 August 2012 | Interim Report of the Evaluation of a Deviation Pursuant to 10 CFR 21.21(a)(2) |
| 3F0412-07, Response to Request for Additional Information to Support NRC Containment and Ventilation Branch (Scvb) Technical Review of the CR-3 Extended Power Uprate LAR | 12 April 2012 | Response to Request for Additional Information to Support NRC Containment and Ventilation Branch (Scvb) Technical Review of the CR-3 Extended Power Uprate LAR |
| ML11321A165 | 27 December 2011 | Nuclear Generating Plant - Issuance of Amendment 239 Regarding Departure from a Method for Evaluating the Auxiliary Building Overhead Crane and Revisions to Associated Commitments |
| ML12009A020 | 14 December 2011 | Emergency Plan Implementing Procedure Revisions |
| ML11256A074 | 20 July 2011 | License Amendment Request #310, Revision 1, Departure from a Method of Evaluation for the Auxiliary Building Overhead Crane, Revisions to Associated Commitments, and Response to Request for Additional Information |
| ML102920068 | 20 September 2010 | Ncr Number 358724, Assignment Number 23, Crystal River, Unit 3 Containment |
| 3F1209-04, Response to Follow-up to Progress Energy RAI Responses on CR-3 SAMA Evaluation | 18 December 2009 | Response to Follow-up to Progress Energy RAI Responses on CR-3 SAMA Evaluation |
| 3F1009-03, Response to Request for Additional Information Regarding Severe Accident Mitigation Alternatives | 9 October 2009 | Response to Request for Additional Information Regarding Severe Accident Mitigation Alternatives |
| ML100750423 | 5 October 2009 | Action Request: CR3 Sgr Hydrodemolition Exposed Cracks |
| ML090080731 | 30 November 2008 | License Renewal Application, Consisting of Applicant'S Environmental Report |
| 3F0208-05, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. | 29 February 2008 | Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. |
| ML060370395 | 9 February 2006 | Request for Additional Information, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors |
| ML052990293 | 19 October 2005 | FAQ Log 10/19/2005 |
| ML052700044 | 21 September 2005 | Attachment 10, FAQ Log 9/21/05 |
| 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. | 30 August 2005 | Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. |
| 3F0705-09, Response to Request for Additional Information Regarding Third 10-Year Inservice Inspection Program - Risk-Informed Inservice Inspection Program for Class 1, ASME Code, Category B-J and B-F Piping Welds - Question 1 | 14 July 2005 | Response to Request for Additional Information Regarding Third 10-Year Inservice Inspection Program - Risk-Informed Inservice Inspection Program for Class 1, ASME Code, Category B-J and B-F Piping Welds - Question 1 |
| ML051530399 | 29 June 2005 | Audit Report |
| IR 05000302/2005006 | 9 June 2005 | IR 05000302-05-006 on 04/25/05 - 04/29/05 and 05/09/05 - 05/13/05 for Crystal River Unit 3; Safety System Design and Performance Capability Inspection |
| ML050560037 | 8 February 2005 | 12-5023272-01, Risk Assessment for Alternate STS End States. |
| ML032530022 | 3 September 2003 | Transmittal of EM-225 Duties of the Technical Support Center Accident Assessment Team |
| 3F0998-01, Provides Notification That Due Date for NRC Commitment Is Being Extended to 981110.Commitment,encl | 3 September 1998 | Provides Notification That Due Date for NRC Commitment Is Being Extended to 981110.Commitment,encl |
| 3F0898-17, Provides Notification That Due Date for Commitment Re Util 980324 Response to Violations Noted in Insp Rept 50-302/97-12,is Being Extended.Commitment Made by Licensee, Encl | 25 August 1998 | Provides Notification That Due Date for Commitment Re Util 980324 Response to Violations Noted in Insp Rept 50-302/97-12,is Being Extended.Commitment Made by Licensee, Encl |
| 3F0798-07, Forwards Rev 25,vols 1-4,to Crystal River Unit 3 FSAR, Incorporating Exception to 10CFR50.4(b)(6) as Stated in .W/Summary of Changes & Summary of SEs Performed During Submittal Period | 28 July 1998 | Forwards Rev 25,vols 1-4,to Crystal River Unit 3 FSAR, Incorporating Exception to 10CFR50.4(b)(6) as Stated in .W/Summary of Changes & Summary of SEs Performed During Submittal Period |
| 3F0698-05, Responds to NRC Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions | 30 June 1998 | Responds to NRC Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions |
| ML20236Q461 | 30 June 1998 | SER for Crystal River Power Station,Unit 3,individual Plant Exam (Ipe).Concludes That Plant IPE Complete Re Info Requested by GL 88-20 & IPE Results Reasonable Given Plant Design,Operation & History |
| 3F0498-15, Forwards Response to Violations Noted in Insp Rept 50-302/98-02.Corrective Actions:Listing of Plant Equipment Utilized for in-plant Actions,By Tag Number Equipment Noun Name & Plant Location,Compiled from Review of Each EOP | 15 April 1998 | Forwards Response to Violations Noted in Insp Rept 50-302/98-02.Corrective Actions:Listing of Plant Equipment Utilized for in-plant Actions,By Tag Number Equipment Noun Name & Plant Location,Compiled from Review of Each EOP |
| 3F0398-18, Responds to NRC Re Violations Noted in Insp Rept 50-302/97-12.Corrective Actions:Review of EOPs Was Conducted to Identify Actions to Be Performed by Support Organizations | 24 March 1998 | Responds to NRC Re Violations Noted in Insp Rept 50-302/97-12.Corrective Actions:Review of EOPs Was Conducted to Identify Actions to Be Performed by Support Organizations |
| 3F0298-02, Forwards Status of Requirements Stated in SE Submitted W/ License Amend 163.Status of SE Requirements Do Not Invalidate or Alter Any Conclusions,Or Basis of Any Conclusion,Supporting TS Issued in License Amend 163 | 20 February 1998 | Forwards Status of Requirements Stated in SE Submitted W/ License Amend 163.Status of SE Requirements Do Not Invalidate or Alter Any Conclusions,Or Basis of Any Conclusion,Supporting TS Issued in License Amend 163 |
| 3F0198-41, Forwards Vols 1-4,Rev 24 to FSAR for Crystal River Unit 3. Rev Provided as Complete Reissue of FSAR & Pages Marked as Rev 24,dtd 980126.Summary of Changes Made in Fsar,Rev 24 Provided in Attachment A.Rept Will Be Provided by 980213 | 28 January 1998 | Forwards Vols 1-4,Rev 24 to FSAR for Crystal River Unit 3. Rev Provided as Complete Reissue of FSAR & Pages Marked as Rev 24,dtd 980126.Summary of Changes Made in Fsar,Rev 24 Provided in Attachment A.Rept Will Be Provided by 980213 |
| 3F0198-29, Informs That Util in Conjunction W/Framatome Technologies Inc,Completed Confirmation Which Includes Consideration of SG Tube Plugging Levels Specific for CR-3.Util Verified That LOCA Analyses of Record Does Not Require Manual Actuation | 15 January 1998 | Informs That Util in Conjunction W/Framatome Technologies Inc,Completed Confirmation Which Includes Consideration of SG Tube Plugging Levels Specific for CR-3.Util Verified That LOCA Analyses of Record Does Not Require Manual Actuation |
| ML20198J804 | 10 January 1998 | Integrated Verification Team Rept |
| ML20198J837 | 10 January 1998 | Engineering |
| ML20198J882 | 10 January 1998 | Licensing |
| ML20198H021 | 18 December 1997 | Summarizes 971211-12 Meetings W/Util.Purpose of Meeting to Discuss Status of Actions to Resolve Technical Issues & Progress Toward Readiness for Restart.List of Attendees & Util Handouts Encl |
| ML20197J996 | 5 December 1997 | Summary of 971120 Meeting W/Util in Rockville,Md Re Mgt Corrective Action & Restart Progress.List of Attendees & Meeting Handout Encl |
| ML20203A206 | 4 December 1997 | Insp Rept 50-302/97-14 on 971006-24.Violations Noted. Major Areas Inspected:Operations,Maint & Engineering |
| ML20202D416 | 26 November 1997 | Mod Outage Integrated Verification Team Rept |
| IR 05000302/1997016 | 24 November 1997 | Insp Rept 50-302/97-16 on 970921-1025.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support |
| 3F1197-21, Responds to NRC Verbal RAI for License Amend Request 219, Re Changes to Operating License for Plant,Unit 3 Nuclear Station.Original Determination Submitted W/Request Remains Valid W/No Changes Needed.No New Commitments Made in Ltr | 7 November 1997 | Responds to NRC Verbal RAI for License Amend Request 219, Re Changes to Operating License for Plant,Unit 3 Nuclear Station.Original Determination Submitted W/Request Remains Valid W/No Changes Needed.No New Commitments Made in Ltr |
| ML20217D756 | 1 October 1997 | Safety Evaluation Concluding That Testing of Ingersoll-Dresser Pump Model 8HN194 at Test Facility Demonstrates That Crystal River Decay Heat Pumps of Same Model Can Operate at Flows of 100 Gpm for 30 Days |
| ML20217D751 | 1 October 1997 | Forwards Safety Evaluation Concluding That Crystal River, Unit 3 Heat Pump Can Operate Acceptably at Flows of 100 Gpm for Period of 30 Days |
| ML20211D661 | 17 September 1997 | Summary of 970905 Meeting W/Util in Rockville,Md to Discuss Status of Expected & Active Licensing Submittals Re Plant, Unit 3.Updated Schedule Encl |
| ML20217D334 | 30 July 1997 | Transmits Attachment D to Memo of 970729,which Forwarded Minutes of Crystal River 3 Restart Panel Meeting Held 970722.Memo Did Not Include Attachment D as Result of Inadvertent Error |
| ML20149K028 | 24 July 1997 | Summary of 970722 Meeting W/Florida Power Corp in Rockville, MD Re Overview of Licensee Progress Toward Readiness for Restart,Including Issues Specified in CAL 2-97-01 .Attendance List & Meeting Handouts Encl |
| ML20148U441 | 7 July 1997 | Summary of 970624 Meeting W/Util in Rockville,Md Re Proposed License Amend Relating to High Pressure Injection,Emergency Feedwater & Emergency Diesel Generator Sys.List of Attendees & Handouts Encl |
| ML20141G171 | 27 June 1997 | Summary of Crngp Ninth Meeting Held 970618-19 at Crngp Re Status of Current Insps,Plans for Future Insps & Crngp 3 Checklist.Updated Checklist Encl |
| ML20149H024 | 26 June 1997 | Summary of Restart Panel Meeting Conducted at Crngp on 970619 Re Items Included on NRC Mc 0350 Restart Matrix & FPC Restart List.Meeting Handout & List of Attendees Encl |
| 3F0697-10, TS Change Request 210 to License DPR-72,supporting Operation W/Hardware Changes Primarily Involving Efw,Hpi,Emergency Feedwater Initiation & Control Sys & Edgs,As Well as Associated Licensing & Design Bases Changes | 14 June 1997 | TS Change Request 210 to License DPR-72,supporting Operation W/Hardware Changes Primarily Involving Efw,Hpi,Emergency Feedwater Initiation & Control Sys & Edgs,As Well as Associated Licensing & Design Bases Changes |
| ML20148K796 | 12 June 1997 | Safety Analysis Input to Startup Team Safety Assessment Rept |