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Issue date | Title | |
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ML20073J227 | 26 September 1994 | Application for Amend to License DPR-46,consisting of Proposed Change 136,revising TS LCOs 3.5.C.1 & 3.5.C.4 to Increase Min Pressure at Which HPCI Sys Required to Be Operable |
ML20079J215 | 30 September 1991 | Proposed Tech Specs Clarifying Terms Sys & Subsystems as Terms Apply to Core & Containment Cooling Sys,Addl Safety Related Plant Capabilities & Reactor Water Level Trip Settings |
ML20082G252 | 31 May 1991 | Technical Evaluation Rept,Cooper Nuclear Station,Station Blackout Evaluation, Final Rept |
ML20106C046 | 28 September 1992 | Forwards Response to GL 92-04, Resolution of Issues Re Reactor Vessel Water Level Instrumentation in Bwrs. Util Endorses BWR Owners Group Plans.Hardware & Software Mods Should Not Be Implemented Until Significance Determined |
ML20107D523 | 4 February 1985 | Detailed Control Room Design Review Summary Rept |
ML20115J989 | 18 July 1996 | Forwards Summary Rept of Facility Changes,Tests & Experiments Completed IAW 10CFR50.59(b) Requirements for 1995 Period.Rept Includes Changes Incorporated in Rev 14 of USAR |
ML20128N146 | 19 February 1993 | Ack Receipt of Util Response to Generic Ltr 92-04, Resolution of Issues Re Reactor Vessel Water Level Instrumentation in BWR, |
ML20132G165 | 20 December 1996 | Insp Rept 50-298/96-30 on 961104-1204.No Violations Noted. Major Areas Inspected:Assess Significance of Design Deficiency Described in LER 94-018 & Supplements & Determine If Corrective Actions Sufficient |
ML20134L590 | 14 February 1997 | Provides Corrected Response to 961009,request for Addl Info Re Adequacy & Availability of Design Bases Info for Cooper Nuclear Station |
ML20135C301 | 25 February 1997 | Insp Rept 50-298/96-24 on 961007-970219.Violations Noted. Major Areas Inspected:Licensee Operations,Maint,Engineering & Safety Sys |
ML20138L031 | 10 February 1997 | Forwards Response to 961009 Request for Info,Per 10CFR50.54(f) Re Adequacy & Availability of Design Bases Info |
ML20138R888 | 8 November 1985 | Exam Rept 50-298/OL-85-04 on 850923-26.Exam Results:Four Senior Reactor Operators Passed Exam & One Failed & Two Reactor Operators Passed Exam & One Failed |
ML20148N222 | 28 March 1988 | Insp Rept 50-298/88-06 on 880201-29.Violations Noted.Major Areas Inspected:Licensee Actions on Previous Insp Findings, Operational Safety Verification,Ler Followup,Ie Bulletin 84-02 Followup,Monthly Surveillance & Maint Observations |
ML20151E836 | 11 April 1988 | SALP Rept 50-298/88-01 for 860801-880131 |
ML20151Q062 | 28 July 1998 | Final Version of Improved TS & Bases Re Proposed Change to Conversion to Improved Standard TS |
ML20151X190 | 17 August 1988 | Responds to NRC Re Violations Noted in Insp Rept 50-298/88-20.Corrective actions:H-300 Door Closed,Thereby Correcting Violating Condition & Step Added to Shift Supervisor Responsibilities in Procedure 0.16 |
ML20154R480 | 14 March 1986 | Insp Rept 50-298/86-01 on 860106-10.Potential Violations Noted:Failure to Have Adequate Procedures for Preventive Maint & Failure to Establish Training Program for Electrical & Mechanical Personnel |
ML20196B385 | 17 June 1999 | Summary Rept of Facility Changes,Test & Experiments,Per 10CFR50.59 for Period 970901-990331.Summary of Commitment Changes Made During Same Time Period Also Encl |
ML20196B474 | 17 June 1999 | Proposed Tech Specs Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610 |
ML20203P680 | 22 April 1986 | Summary of 860410 Meeting W/Project Managers & Utils in Bethesda,Md Re Automated Tracking,Integrated Schedules & Tech Specs.Attendees List,Viewgraphs & Meeting Agenda Encl |
ML20207N366 | 8 January 1987 | Requests Info Sufficient to Demonstrate Adequacy of Sys, Including Alternate Rod Insertion,Standby Liquid Control & Recirculation Pump Trip Sys,Per 10CFR50.62.Safety Evaluation of NEDE-31096-P Encl for Ref |
ML20213F064 | 10 November 1986 | Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl |
ML20235H274 | 31 May 1987 | Mechanical Level Instrument Availability Analysis |
ML20236F802 | 24 June 1998 | Forwards Draft Safety Evaluation on Proposed Conversion of Current TS for CNS to Improved TS (Its).Se Based on Staff Review 970327 Application |
ML20236Q064 | 13 July 1998 | Proposed Tech Specs Re Rev B to Conversion to Improved STS |
ML20236Q766 | 14 July 1998 | Forwards Draft SE Comments Re Proposed Conversion to Improved Std Tech Specs for Plant.Numerous Randomly Numbered Pages of Incoming Submittal Not Included |
ML20247L272 | 15 May 1998 | Insp Rept 50-298/98-02 on 980308-0418.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support |
ML20288A198 | 29 September 2020 | CN-2020-09-FINAL Written Exam |
ML20307A103 | 21 October 2020 | Report of Change and Summary of 50.54(q) Analyses for Emergency Plan Implementing Procedure 5.7.1, Revision 66 |
ML20318A168 | 21 October 2020 | Report of Change and Summary of 50.54( Q) Analyses Emergency Plan Implementing Procedure 5.7.1, Revision 66 |
ML20324A039 | 29 September 2020 | CN-2020-09-DRAFT Outlines |
ML20324A041 | 29 September 2020 | CN-2020-09-DRAFT Written Exam |
ML21130A064 | 21 April 2021 | 0 to Updated Final Safety Analysis Report, USAR Appendix G, Nuclear Safety Operational Analysis |
ML21130A067 | 21 April 2021 | 0 to Updated Final Safety Analysis Report, Section I, Introduction and Summary |
ML21130A068 | 21 April 2021 | 0 to Updated Final Safety Analysis Report, USAR Section VII, Control and Instrumentation |
ML21130A070 | 21 April 2021 | 0 to Updated Final Safety Analysis Report, Section VI, Emergency Core Cooling Systems |
ML21130A083 | 21 April 2021 | 0 to Updated Final Safety Analysis Report, Section IV, Reactor Coolant System |
ML21130A101 | 21 April 2021 | 0 to Updated Final Safety Analysis Report, USAR Section Xiv, Station Safety Analysis |
ML21208A422 | 25 June 2021 | CN-2021-06 Final Written Exam |
ML21230A349 | 25 June 2021 | CN-2021-06 Draft Written Exam |
ML21340A236 | 20 December 2021 | Issuance of Amendment No. 270 Adoption of Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements |
ML23129A266 | 20 April 2023 | 1 to Updated Safety Analysis Report, Appendix G, Nuclear Safety Operational Analysis |
ML23129A269 | 20 April 2023 | 1 to Updated Safety Analysis Report, Section I, Introduction and Summary |
ML23129A270 | 20 April 2023 | 1 to Updated Safety Analysis Report, Section VII, Control and Instrumentation |
ML23129A272 | 20 April 2023 | 1 to Updated Safety Analysis Report, Section VI, Emergency Core Cooling Systems |
ML23129A286 | 20 April 2023 | 1 to Updated Safety Analysis Report, Section IV, Reactor Coolant System |
ML23129A303 | 20 April 2023 | 1 to Updated Safety Analysis Report, Section Xiv, Station Safety Analysis |
NLS2002129, License Amendment Request to Revise TS-Safety Limit Minimum Critical Power Ratio, Cooper Nuclear Station | 15 November 2002 | License Amendment Request to Revise TS-Safety Limit Minimum Critical Power Ratio, Cooper Nuclear Station |
NLS2004007, License Amendment Request - One-Time Extension of Surveillance Requirements | 30 January 2004 | License Amendment Request - One-Time Extension of Surveillance Requirements |
NLS2004099, License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio | 25 October 2004 | License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio |