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 Issue dateTitle
ML22250A7097 September 2022Generation Station, Emergency Plan, Revision 74
ML22173A08721 June 2022Generation Station (Pvngs), Units 1, 2, and 3 and Independent Spent Fuel Storage Installation - PVNGS Emergency Plan, Revision 73
ML21356B72122 December 2021Special Report 3-SR-2021-001-00
ML21203A13822 July 2021Generation Station (Pvngs), Units 1, 2, and 3 and Independent Spent Fuel Storage Installation - PVNGS Emergency Plan, Revision 70
ML21203A15222 July 2021Generation Station (Pvngs), Units 1, 2, and 3 and Independent Spent Fuel Storage Installation - PVNGS Emergency Plan, Revision 71
ML18341A1596 December 2018Emergency Plan, Revision 63
ML18269A36225 September 2018ISFSI - Emergency Plan, Revision 62
ML18172A00712 June 2018Independent Spent Fuel Storage Installation - PVNGS Emergency Plan, Revision 61
ML17269A26421 September 2017Enclosure 1: Palo Verde, Units 1, 2, and 3, and ISFSI - Emergency Plan, Revision 60
ML17263B24915 September 2017Emergency Plan, Rev. 59. Part 2 of 2
ML16154A61412 May 2016PVNGS, Units 1, 2, and 3 - Technical Specification Bases, Revision 63
ML16133A62112 May 2016ISFSI - Response to Request for Additional Information Regarding Proposed Changes to Emergency Action Levels
ML16083A25023 March 2016NRR E-mail Capture - Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Official RAIs for EAL LAR
ML15293A3359 October 2015Independent Spent Fuel Storage Installation (ISFSI) - Request for NRC Approval of Proposed Changed to Emergency Action Levels
ML15139A30024 April 2015Technical Specification Bases (TS Bases), Revision 62
ML15027A12219 December 2014Technical Specification (TS) Bases Revision 61
ML14255A06329 August 2014Technical Specification Bases, Revision 60
ML14091A95619 March 2014Technical Specification (TS) Bases Revision 59
ML13357A21818 December 2013Revision 2 to Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML13217A0553 July 2013Enclosure 1 - Technical Specifications Bases, Revision 58
ML13120A50110 April 2013Technical Specification Bases, Revision 57
ML12193A04130 May 2012Technical Specification Bases, Revision 56
ML12193A04225 May 2012Insertion Instructions Technical Specifications Bases, Revision 56, Summary of Changes
ML11287A0341 September 2011Technical Specification Bases Revision 55
ML05311004521 April 2011Current Facility Operating License NPF-41, Tech Specs, Revised 09/28/2017
ML11087195521 April 2011License Renewal - Appendices a, B, C, and D to the Renewed Operating License for Unit 1 (NPF-41)
ML11103A05331 March 2011License Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program
ML11061076326 January 2011PVNGS Technical Specification Bases, Revision 54
ML10335064610 November 2010Technical Specification Bases, Revision 53
ML09083033413 March 2009Revision 1 to Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
ML09035021215 January 2009Amendment Request for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process
ML08071054629 February 2008Palo Verde Nuclear Generating Station (Pvngs), Units 1, 2, and 3, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactor
NOC-AE-07002231, Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46)7 November 2007Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46)
NEI 04-07, Response to Request No. 2 in NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.1 September 2005Response to Request No. 2 in NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
ML0516503242 June 2005Technical Specification Bases Revisions, 30, 31, 32, and 33 Update
ML02260031111 September 2002APS, Palo Verde Units 1, 2, and 3, Technical Specifications Bases Revision 18 Update
ML01101032516 March 2001. Docket Nos. Stn 50-528/529/530 Emergency Plan Implementing Procedure Update. EPIP-07
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
NRC Generic Letter 1998-0228 May 1998NRC 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 Shutdown5 December 1997Recent 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 Shutdown11 December 1996Undetected 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 Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
ML20087H72416 August 1995Comment Opposing Proposed Rule 10CFR2 Re Comment on Revision of NRC Enforcement Policy
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
ML07104001728 April 199459 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 Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
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