Semantic search
Jump to navigation
Jump to search
Issue date | Title | |
---|---|---|
ML13066A036 | 27 February 2013 | Southern California Edison'S Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis.. |
ML12103A036 | 9 April 2012 | Independent Spent Fuel Storage Installation - Revisions to Emergency Plan Implementing Procedures |
ML120130624 | 28 October 2011 | 2011-11-Final Written Exam |
ML120470686 | 28 October 2011 | 2011-11-Draft Written Exam |
ML11251A099 | 29 July 2011 | Attachment 1, Volume 6, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Section 3.3, Instrumentation |
ML093200611 | 16 November 2009 | 2009-10 - Final Written Exam |
ML093200649 | 16 November 2009 | SO-2009-10-DRAFT Written Exam |
ML080670419 | 7 March 2008 | CDBI Findings |
ML051790253 | 23 June 2005 | Cycle 13 Technical Specification Bases Page Updates |
ML051440065 | 18 May 2005 | Technical Specifications, Correction to Amendment Nos. 194 and 185 |
ML051310380 | 28 April 2005 | 04-2005-Final Written RO-SRO Examination |
ML051110265 | 19 April 2005 | Proposed Change Number (PCN) 550 Technical Specification Pages |
ML050960139 | 29 March 2005 | 4 TS Pages - SONGS Amds. 194/185 Elimination of Requirements, Etc |
ML043510203 | 10 December 2004 | Proposed Change Number (PCN) 550 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Monitors Using the Consolidated Line Item Improvement Process |
ML041110355 | 16 April 2004 | Special Report for Southern California Edison (SCE) San Onofre Nuclear Generating Station, Unit 3 Inoperable Reactor Vessel Water Level Instrumentation |
ML032120094 | 28 July 2003 | Cycle 12 Technical Specification Bases Page Updates |
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 |
ML20199L340 | 22 January 1999 | Forwards Facility Submitted Outline,Initial Exam & as Given Operating Exam for Test Administered on 981115-20 at San Onofre Nuclear Generation Station |
ML20151W680 | 10 September 1998 | Proposed Tech Specs Eliminating Requirements for Hydrogen Control Sys from Low Power Plant License Conditions 2.C(19)i & from TSs 3.3.11 & 3.6.7 |
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 |
ML20198R028 | 30 May 1997 | Proposed Tech Specs Re Revised Bases Pages for Songs,Units 2 & 3 |
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 |
ML20116K758 | 13 August 1996 | Discusses Planned Course of Action to Address Inoperability of Reactor Water Level Probe |
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
ML20113C256 | 25 June 1996 | Proposed Tech Specs,Revising TS 3.3.11, Pami, & 5.5.2.13, Diesel Fuel Oil Testing Program |
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 |
ML20112D461 | 3 June 1996 | Proposed Tech Specs,Reinstating Provisions of Current SONGS TS Revised as Part of NRC Amends 127 & 116 |
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 |
ML20083P103 | 19 May 1995 | Informs NRC of Util Planned Course of Action to Address Inoperability of Plant RCS Rwl Probe During Unit 3 Cycle 8 & 9 Refueling Outages |
ML20072K932 | 25 August 1994 | Proposed Tech Specs Supporting TS Improvement Program |
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 |
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 |
ML20246D033 | 11 May 1989 | Commission Response to J Bates Subcommittee on Energy & Power Question 9 from |
ML20246D047 | 11 May 1989 | Commission Response to J Bates Subcommittee on Energy & Power Question 11 from |
ML20246D050 | 11 May 1989 | Commission Response to J Bates Subcommittee on Energy & Power Question 12 from |
ML20207L931 | 8 January 1987 | Requests Submittal of Info Demonstrating Adequacy of Alternate Rod Insertion,Standby Liquid Control & Recirculation Pump Trip Sys.Deviations from BWR Owners Group Alternatives Must Be Justified |
ML20205C389 | 21 July 1986 | Responds to NRC Re Violations Noted in Insp Repts 50-361/86-11 & 50-362/86-11.Corrective Actions:Shutdown Cooling Sys Refilled,Vented & Flow Restored.Tygon Level Indicator Properly Reinstalled |
ML20206R942 | 20 June 1986 | Notice of Violation from Insp on 860328-0512 |
IR 05000361/1986011 | 20 June 1986 | Insp Repts 50-361/86-11 & 50-362/86-11 on 860328-0512. Violation Noted:Water Level Indicator Installed W/O Appropriate Procedure & Failure to Comply W/Station Procedure for Reactor Startup |
ML20236K333 | 30 April 1986 | Forwards Draft Encl 3 Writeup on Loss of DHR at Facility Per 860425 Memo from J Martin to J Heltemes as Possible Inclusion in Rept for First Quarter CY86 AO Rept to Congress |
ML20236K324 | 29 April 1986 | Forwards Draft Encl 3 Writeup on Loss of DHR at Facility as Discussed in 860425 Memo from J Martins to J Heltemes for Inclusion in Rept for First Quarter CY86 AO Rept |