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| Issue date | Title | |
|---|---|---|
| ML20147A024 | 15 May 2020 | Amendment 63 to Final Safety Analysis Report, Chapter 7, Instrumentation and Controls |
| RA-18-0248, Response to Request for Additional Information Regarding License Amendment Request for Emergency Action Level Scheme Change | 17 December 2018 | Response to Request for Additional Information Regarding License Amendment Request for Emergency Action Level Scheme Change |
| 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... |
| HNP-16-004, Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme to One Based on Revision 6 of Nuclear Energy Institute 99-01, Development of Emergency.... | 28 January 2016 | Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme to One Based on Revision 6 of Nuclear Energy Institute 99-01, Development of Emergency.... |
| HNP-15-091, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme to One Based on Revision 6 of NEI 99-01, Development of Emergency Action Levels for Non-Passive Reactors | 19 November 2015 | Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme to One Based on Revision 6 of NEI 99-01, Development of Emergency Action Levels for Non-Passive Reactors |
| ML15126A089 | 30 April 2015 | EAL Bases |
| 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 |
| HNP-13-053, Submittal of Path Forward for Resolution of Generic Safety Issue (GSI) - 191 | 16 May 2013 | Submittal of Path Forward for Resolution of Generic Safety Issue (GSI) - 191 |
| ML080670419 | 7 March 2008 | CDBI Findings |
| HNP-05-059, Emergency Response Data System (ERDS) Data Point Library Changes | 12 May 2005 | Emergency Response Data System (ERDS) Data Point Library Changes |
| HNP-02-078, Request for Emergency License Amendment, Revises TSs 3/4.3.3.6 | 29 May 2002 | Request for Emergency License Amendment, Revises TSs 3/4.3.3.6 |
| 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 |
| ML18016A881 | 31 March 1999 | Responds to NRC 990301 Ltr Re Violations Noted in Insp Rept 50-400/98-11.Corrective Actions:Post Trip/Safeguards Actuation Rept for 981023,RT Was Corrected,Required Reviews Completed & Approval Obtained on 990219 |
| 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 |
| ML18016A413 | 18 December 1997 | Rev 10 to ODCM for Shearon Harris Nuclear Power Plant. |
| 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 |
| 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 |
| 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 |
| ML20059C731 | 30 January 1993 | Summary of 391st ACRS Meeting on 921105-07 in Bethesda,Md Re NRC Regulatory Analysis Guidelines & Reactor Operating Events & Occurrences,Shearon Harris Plant Loss of High Head SI & LaSalle Overfill Due to Failure of MFW Pumps to Trip |
| 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 |
| ML18005A793 | 22 February 1989 | Application for Amend to License NPF-63,changing Tech Spec 3.9.8.2, Refueling Operations-Low Water Level, to Delete RHR Flow Requirements Whenever Water Level Below Reactor Vessel Flange,Per Generic Ltr 88-17 |
| ML20245D841 | 28 September 1988 | Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920 |
| ML20235W943 | 13 October 1987 | Summary of Operating Reactors Events Meeting 87-32 on 870922.Notes That Meeting 87-31 Did Not Occur.List of Attendees & Events Discussed & Significant Elements of Events Encl |
| IR 05000400/1987011 | 11 March 1987 | Insp Rept 50-400/87-11 on 870226-0301.No Violations or Deviations Noted.Major Areas Inspected:Key Emergency Organizational Functions & Locations During Full Participation Emergency Preparedness Exercise |
| ML20206J937 | 9 February 1987 | Forwards Quarterly Status Rept for Fourth Quarter of Calendar Year 1986,in Response to Direction Given in House Rept 97-850.NRC Licensing Activity During Period of Rept Includes Issuance of full-power License for Perry Unit 1 |
| ML20210L956 | 5 February 1987 | Forwards NRR Monthly Status Rept,Including Info Available as of 870131.Rept Identifies Potential or Actual Licensing Delay for Shoreham,Comanche Peak Unit 1,Braidwood Unit 1 & Seabrook Unit 1 |
| ML20207M036 | 6 January 1987 | Provides Current Status of Facility Proceeding,Including Admitted Contentions Raising Listed Issues.Aslb Issued Three Initial Decisions & Concluding or Final ASLB Decision Favorable to Applicants |
| ML20215E923 | 19 December 1986 | Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending |
| IA-86-843, Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending | 19 December 1986 | Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending |
| 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 |
| ML18018B768 | 12 September 1984 | Revised Plant Emergency Procedures,Including 1.0 Re Emergency Classifications & Control Procedures & 2.0 Re Emergency Mgt Guides.Three Oversize Figures Encl.Aperture Cards Available in PDR |
| ML20112C584 | 7 September 1984 | Intervenor Exhibit I-JOINT-17,consisting of Undated Attachment I-39(r), NRC Violations, Listing Dates of Response to Notices of Violation for Shearon Harris, Hb Robinson & Brunswick Plants |
| ML20112C301 | 5 September 1984 | Applicant Exhibit A-1,consisting of FSAR Sections 13.0- 13.1.3.2 & 13.4.1-13.5.2.2 |