Semantic search

Jump to navigation Jump to search
 Issue dateTitle
ML22340A16030 November 2022Technical Specifications Bases, List of Effective Pages
ML22340A20230 November 2022Technical Specifications Bases, List of Effective Pages
ML21125A57619 April 20219 Technical Specification Bases, List of Effective Pages (Unit 2)
ML21125A53419 April 20210 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System
ML21125A54819 April 20212 to Technical Specifications Bases, List of Effective Pages (Unit 1)
ML21077A01016 March 2021Handout for Pre-Submittal Meeting with NRC and DC Cook Plant in March 19, 2021
ML17346A7668 December 2017Enclosures 2 & 3 to AEP-NRC-2017-56 - Response to Request for Additional Information Regarding the License Amendment Request to Revise Emergency Action Levels and EAL Technical Basis Manual
ML14357A44723 April 2013Emergency Plan, Revision 32, Part 1 of 3
IR 05000315/20120032 August 2012IR 05000315-12-003, 05000316-12-003, 04/01/2012 - 06/30/2012, D.C. Cook Nuclear Power Plant, Units 1 & 2
ML11188A14629 June 2011Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Without Attachments C, E, G, I & W
ML0806704197 March 2008CDBI Findings
ML05144051015 April 2005Attachment 1, Volume 8, Rev. 1, Cook Nuclear Power Plant Units 1 & 2, Improved Technical Specifications Conversion, ITS Section 3.3 - Instrumentation
ML0412003926 April 2004CNP Units 1 and 2 Improved Technical Specifications Conversion, Volume 14, Rev 0, ITS Section 3.9 Refueling Operations.
ML04056052317 February 2004Revision 4, Change 2 to PMP-2080-EPP-101, Emergency Classification.
ML0329004448 October 2003Transmittal of Emergency Plan Implementing Procedures
ML03267061418 September 2003to PMP-2080-EPP-101, Emergency Classification.
ML03147026419 April 2003Revised Emergency Plan Implementing Procedures. Rev 7 to PMI-2080 Through Rev 4 of PMP-2080-EPP-108
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
ML17333A5872 October 1996Expresses Apologies for Pages Being Omitted from Out Aep: NRC:1192D Ltr Submitted 960927
ML17333A59327 September 1996Clarifies Emergency Action Level (EAL) Statement as Requested by NRC Staff on 960926
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
ML17332A58428 February 1995DC Cook Nuclear Plant IPE for External Events Revised Fire Pra.
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
ML17331B43013 June 1994Rev 0 to DC Cook Nuclear Plant E-Plan Classification Vs NUMARC/NESP-007 Deviation Basis Document.
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
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
ML20118C0131 October 1992Forwards Detailed Info on Level Instrumentation for ERDS, Per 920828 Discussion Re Approval Status of ERDS Data Point Library.Encl Info Includes,Rvlis,Sg Level,Pressurizer Level, Containment Sump Levels & Borated Water Storage Tank Level
ML17334B44624 September 1992Application for Amends to Licenses DPR-58 & DPR-74,deleting TS Table 3.6-1, Containment Isolation Valves,Per Guidance Provided in GL 91-08, Removal of Component Lists from Ts. Lists of Valves Will Be Incorporated Into Plant Procedures
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)
ML20101G23117 June 1992Provides Data Point Library for DC Cook Nuclear Plant in Response to 10CFR50,App E,Section VI
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
ML17328A7709 November 1990Updates 881005 Submittal Re Reg Guide 1.97.Licensee Completed All Upgrade Work Shown in Table Portion W/Listed Exceptions
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units23 March 1990Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units
ML17325B0879 January 1989Forwards Response to Generic Ltr 88-17, Loss of DHR, Including Actions & Controls That Will Be Implemented Prior to Operating in Reduced Inventory Condition W/Irradiated Fuel in Reactor Vessel
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 Identified9 January 1986Part 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
IR 05000316/200403031 May 1985Insp Repts 50-352/85-16 & 50-353/85-04 on 850316-0430. Violation Noted:Inadequate cross-discipline Review Capability in Plant Operations Review Subcommittee Reviewing Rev 2 to Procedures Re Sodium Pentaborate Analysis
NRC Generic Letter 1985-0823 May 1985NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format
NRC Generic Letter 1985-0923 May 1985NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3
NRC Generic Letter 1985-072 May 1985NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications
IR 05000316/200401124 April 1985Insp Rept 50-416/85-09 on 850316-0411.Violations Noted: Steps in Sp 06-EL-1E31-M-0001 Performed Out of Sequence Resulting in ESF Containment Isolation Valve Actuation & Causing Isolation of RCIC Sys
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
Retrieved from "https://kanterella.com/Special:Ask/-5B-5BTopic::Reactor-20Vessel-20Water-20Level-5D-5D-20-5B-5BSite::Cook-5D-5D/-3FIssue-20date/-3FTitle/mainlabel%3D/order%3Ddescending/sort%3Dissue-20date/offset%3D0/format%3Dtable/searchlabel%3DCook"