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| Issue date | Title | |
|---|---|---|
| RA-20-0050, Emergency Action Levels CSD-EP-RNP-0101-02, Revision 0 | 13 February 2020 | Emergency Action Levels CSD-EP-RNP-0101-02, Revision 0 |
| ML16336A527 | 1 December 2016 | H.B. Robinson, Unit 2, and ISFSI - Transmittal of Emergency Plan and Emergency Implementing Procedures Revisions and 10 CFR 50.54(q) Summary of Analyses |
| RNP-RA/16-0071, Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis | 20 September 2016 | Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis |
| RA-16-0023, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P | 4 May 2016 | Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P |
| RA-16-0003, Application to Revise Technical Specifications to Adopt Methodology Reports DPC-NF-2010, Revision 3, Nuclear Physics Methodology for Reload Design, and DPC-NE-2011-P, Revision 2, Nuclear Design Methodology Report... | 3 February 2016 | Application to Revise Technical Specifications to Adopt Methodology Reports DPC-NF-2010, Revision 3, Nuclear Physics Methodology for Reload Design, and DPC-NE-2011-P, Revision 2, Nuclear Design Methodology Report... |
| RNP-RA/16-0001, Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analysis, Revision 14 to EPCLA-04, Emergency Action Level Technical Bases Document. | 13 January 2016 | Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analysis, Revision 14 to EPCLA-04, Emergency Action Level Technical Bases Document. |
| ML15224B419 | 21 May 2015 | Initial Exam 2011-301 Draft SRO Written Exam |
| RNP-RA/15-0034, Proposed Changes to Emergency Plan | 13 May 2015 | Proposed Changes to Emergency Plan |
| RA-16-0034, RETRAN-3D --- a Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems Volume 5: Modeling Guidelines | 31 March 2014 | RETRAN-3D --- a Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems Volume 5: Modeling Guidelines |
| RNP-RA/13-0048, Path Forward for Resolution of GSI-191 | 14 May 2013 | Path Forward for Resolution of GSI-191 |
| ML120470144 | 10 February 2012 | Initial Exam 2011-302 Draft SRO Written Exam |
| ML080670419 | 7 March 2008 | CDBI Findings |
| Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick | 5 May 1999 | Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick |
| NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |
| Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown | 5 December 1997 | Recent Events Involving Reactor Coolant System Inventory Control During Shutdown |
| Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown | 11 December 1996 | Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown |
| Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power | 22 October 1996 | Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
| Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
| Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown | 18 June 1996 | Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
| Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
| ML20236L921 | 14 July 1995 | Responds to 950330 TIA 95-002 Request for Technical Assistance in Evaluation of Licensee Position on TS Compliance & Operability of Chemical & Volume Control Sys for Plant,Unit 2.TAC Closed |
| Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 | 15 July 1994 | Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
| Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
| ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |
| Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
| Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
| Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
| ML20128M905 | 17 February 1993 | Forwards Addl Info for ERDS Data Point Library,Consisting of Revised & Replacement Pages |
| ML20106C793 | 22 September 1992 | Provides Data Point Library Re Emergency Response Data Sys. Submittal Completes Emergency Response Data Sys Info Requirements Contained in NUREG-1394,Rev 1 |
| NRC Generic Letter 1992-04 | 19 August 1992 | NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F) |
| Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown | 25 February 1992 | Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown |
| Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units | 23 March 1990 | Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units |
| ML20245D841 | 28 September 1988 | Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920 |
| NRC-86-3095, Part 21 Rept Re Nonupper Head Injection Analog Versions of Reactor Vessel Water Level Instrumentation Sys.Initially Reported on 860109.Changes to Upgrade Steam Density Compensation Circuit Identified | 9 January 1986 | Part 21 Rept Re Nonupper Head Injection Analog Versions of Reactor Vessel Water Level Instrumentation Sys.Initially Reported on 860109.Changes to Upgrade Steam Density Compensation Circuit Identified |
| NRC Generic Letter 1985-09 | 23 May 1985 | NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3 |
| NRC Generic Letter 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
| NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |
| NRC Generic Letter 1985-02 | 17 April 1985 | NRC Generic Letter 1985-002: Staff Recommended Actions Stemming from NRC Integrated Program for the Resolution of Unresolved Safety Issues Regarding Steam Generator Tube Integrity |
| NRC Generic Letter 1985-05 | 31 January 1985 | NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events |
| ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |
| ML20080M828 | 30 September 1983 | Further Answers to First Set of Interrogatories Per Agreement.Certificate of Svc Encl |