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 Issue dateTitle
ML10127017116 March 20102010-03 Draft Written Exam
ML10363055229 December 2010Email, Request for Additional Information on License Amendment Request Extension of Completion Times for One Inoperable RCS Cooling Loop
ML11027010427 January 2011E-mail, Request for Additional Information Round 3, Request to Revise TS 3.4, Reactor Coolant System (Rcs), and TS 3.9, Refueling Operations, Related to Completion Times for One Inoperable RCS Cooling Loop
ML11265026922 September 2011Licensee Handouts for 10/05/2011 Presubmittal Meeting
ML14336A35321 November 20142014-11 Draft Written Exam
ML17240A38015 June 20172017-06-Final Written Exams
ML18094A15529 March 2018Enclosures 2 - 6: Proposed EAL Technical Basis Document, NEI 99-01. Rev. 6., Proposed EAL Matrix Chart/Review Table and Supporting Referenced Document Pages
ML18283A7754 October 2018Attachments 1 & 2: Summary of Changes to ANO Emergency Plan Implementing Document and Procedure OP-1903.010, Rev. 57, Emergency Action Level Classification
ML18317A38219 December 2018Issuance of Amendment No. 313, Revise Technical Specification 3.3.3.6, Post-Accident Instrumentation
ML19136A25113 June 2019Handout for the June 13, 2019 Pre-submittal Public Meeting for Planned License Amendment Request Regarding Fuel Handling Accident Analysis
ML19210E9265 December 1979Forwards Revision to 791120 Ltr Re Implementation Schedule for Lessons Learned Task Force short-term Recommendations. Requests Expedited Concurrence W/Method of Compliance to NUREG-0578
ML19275A85617 October 1979Forwards Responses to NRC 790913 Ltr.Items in Ltr & NUREG- 0578 Are Valid & Appropriate to Increase Safety Margin at Facility.Proposes Two Outages in Series for Each Unit
ML19291B9045 December 1979Forwards Revision of Selected Provisions of 791120 Response to TMI Lessons Learned Task Force Recommendations.Sequential Shutdowns Preferred to Concurrent.Implementation Schedule Encl
ML19331D62926 August 1980Forwards Evaluation of Instrumentation for Detection of Inadequate Core Cooling to Support 800711 Ltr Stating That No Addl Instrumentation Is Needed to Meet NUREG-0578 Requirements
ML19339B70629 October 1980Responds to NRC 800924 Ltr Re Lessons Learned Task Force Short-Term Requirement 2.1.3.b.Existing Instrumentation Is Sufficient to Detect Inadequate Core Cooling.Reactor Vessel Level Indication Is Unwarranted
ML20023A02015 January 2020Rev. 45 to Emergency Plan and Emergency Plan Implementing Procedure
ML20082D4644 April 1995Proposed Tech Specs 3.9.9 Re Reactor Vessel Water Level, Allowing Latching & Unlatching of CEAs W/Less than 23 Ft of Water Over Top of Irradiated Fuel Assemblies
ML20148B96618 January 1980Submits Description of Implementation/Compliance W/Lessons Learned Task Force short-term Recommendations Not Requiring Prior NRC Approval.Util Will Participate in EPRI Program Re plant-specific Data
ML20202B25322 April 1986Emergency Operating Procedure 74-1122058-00, Revs to Abnormal Transient Operating Guidelines
ML20203P6885 May 1986Vols 1 & 2 to Arkansas Nuclear One Unit 2,CRDR Final Summary Rept
ML20205F8032 April 1999Forwards Draft Info Notice Describing Unanticipated Reactor Water Draindown of Listed Plants
ML20205P46415 April 1999Forwards for Review & Comment Draft Info Notice That Describes Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station Unit 2,Arkansas Nuclear One Unit 2 & Ja Fitzpatrick NPP
ML21134A2418 April 20218_AN2-2021-03 Final Written Exam
ML22124A06910 May 2022RVCH Penetration No. 1 Relief Request Public Meeting May 10, 2022 (EPID L-2022-LRM-0036) (Slides)
ML22167A12416 June 2022Emergency Plan Implementing Procedure Revision
ML23142A10624 May 2023Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035
ML23208A21127 July 2023Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions
NEI 99-01, Arkansas Nuclear One Units 1 & 2, Proposed Emergency Action Levels Using NEI 99-01 Revision 5 Scheme18 July 2011Arkansas Nuclear One Units 1 & 2, Proposed Emergency Action Levels Using NEI 99-01 Revision 5 Scheme
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
NUREG-1432, Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-143230 October 2020Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-1432