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 Issue dateTitle
ML17300A76130 March 1987Special Rept 1-SR-87-016:on 870303,Tech Spec 3.3.3.6 Action 32 Entered Due to Inoperability of Both Channels of Reactor Vessel Water Level Instrumentation.On 870305,time for Restoring Channels to Svc Exceeded.Cause Unknown
ML17303A1811 December 1986Reactor Containment Bldg Integrated Leak Rate Test Summary Technical Rept. W/861208 Ltr
ML17304A36622 August 1988Special Rept 3-SR-88-004:on 880725,reactor Vessel Water Level Sys Channel B Declared Inoperable.Caused by Previous Failures on 880219 & 0706 of Malfunctioning Heated Junction Thermocouples Mechanism.Channel Will Be Restored
ML17304A7347 November 1988Special Rept 3-SR-88-007:on 881024,reactor Vessel Water Level Sys Declared Inoperable for More than 48 H.Caused by Malfunction in Communications Board.Board Replaced & Installed on 881028
ML17304B1017 April 1989Special Rept 1-SR-89-001:on 890306,Channel B Reactor Vessel Water Level Sys Inoperable for Period Greater than 7 Days. Approved Work Document Initiated to Determine Cause of Improper Operation of Sys.Channel Will Be Replaced
ML17304B2455 June 1989Special Rept 3-SR-88-007-01:on 881024,inoperability of Both Channels of Reactor Vessel Water Level Sys Occurred for Period of Greater than 48 H.Caused by Malfunctioning of Communications Board.Replacement Board Installed
ML17305A48316 January 1990Special Rept 2-SR-89-009:on 891212,Channel a of Quality SPDS Could Not Be Calibr & Declared Inoperable.On 891215, Trouble Alarm Received from Power Supply to Channel A.Sys Inoperable for More than 7 Days
ML17305A72630 April 1990Application for Amend to License NPF-41,lowering Min Shutdown Cooling Flow Specs for Mode 5 Loops Not Filled & Require Closing Valve to Isolate Major Source of Nonborated Makeup Water from RCS
ML17305A81624 April 19901990 Emergency Preparedness Evaluated Exercise.
ML17305A9969 August 1990Special Rept 2-SR-89-009:on 891212,Channel a Reactor Vessel Water Level Sys Declared Inoperable & 7-day Limit Exceeded on 891219.Modem Found to Have Drifted Out of Tolerance. Channel a Modem Replaced & Calibr
ML17305B21120 November 1990Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS Surveillance Requirements 4.4.1.4.1.2, 4.4.1.4.2,4.9.8.1 & 4.9.8.2 to Modify Min Shutdown Cooling Sys for Protection Against Boron Dilution Event
ML17310A5215 August 1993Proposed Tech Specs Requesting to Change Word Pressurizer to RCS for Item #4 in Both Tables 3.3-10 & 4.3-7
ML18172A00712 June 2018Independent Spent Fuel Storage Installation - PVNGS Emergency Plan, Revision 61
ML18269A36225 September 2018ISFSI - Emergency Plan, Revision 62
ML18341A1596 December 2018Emergency Plan, Revision 63
ML20085L36728 October 1991Emergency Response Data Sys (ERDS) Implementation Program Plan for Palo Verde Nuclear Generating Station
ML20087H72416 August 1995Comment Opposing Proposed Rule 10CFR2 Re Comment on Revision of NRC Enforcement Policy
ML20129J77819 February 1985Forwards Std Accident Monitoring Instrumentation Tech Specs, Incorporating Heated Junction Thermocouple Sys & C-E Design for Reactor Vessel Level Monitoring Sys.Tech Specs Based on Tech Specs Approved by NRC for Palo Verde Unit 1
ML20205G0076 August 1986Special Rept 2-SR-86-018:on 860705,reactor Vessel Water Level Sys Inoperable for More than 7 Days.Caused by Connection of Channel B Heated Junction Thermocouples in Reverse Order.Connection Corrected
ML20206B21331 March 1987Technical Specifications for Palo Verde Nuclear Generating Station,Unit 3.Docket No. 50-530.(Arizona Public Service Company)
ML20213F06410 November 1986Summary 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
ML20247A89716 March 1989Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl
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
ML21356B72122 December 2021Special Report 3-SR-2021-001-00
ML22173A08721 June 2022Generation Station (Pvngs), Units 1, 2, and 3 and Independent Spent Fuel Storage Installation - PVNGS Emergency Plan, Revision 73
ML22250A7097 September 2022Generation Station, Emergency Plan, Revision 74
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.
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)
NRC Generic Letter 1985-0217 April 1985NRC 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 1985-0531 January 1985NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events
NRC Generic Letter 1985-072 May 1985NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications
NRC Generic Letter 1985-0823 May 1985NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format
NRC Generic Letter 1992-0419 August 1992NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F)
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
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