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Issue date | Title | |
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ML101270171 | 16 March 2010 | 2010-03 Draft Written Exam |
ML103630552 | 29 December 2010 | Email, Request for Additional Information on License Amendment Request Extension of Completion Times for One Inoperable RCS Cooling Loop |
ML110270104 | 27 January 2011 | E-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 |
ML112650269 | 22 September 2011 | Licensee Handouts for 10/05/2011 Presubmittal Meeting |
ML14336A353 | 21 November 2014 | 2014-11 Draft Written Exam |
ML17240A380 | 15 June 2017 | 2017-06-Final Written Exams |
ML18094A155 | 29 March 2018 | Enclosures 2 - 6: Proposed EAL Technical Basis Document, NEI 99-01. Rev. 6., Proposed EAL Matrix Chart/Review Table and Supporting Referenced Document Pages |
ML18283A775 | 4 October 2018 | Attachments 1 & 2: Summary of Changes to ANO Emergency Plan Implementing Document and Procedure OP-1903.010, Rev. 57, Emergency Action Level Classification |
ML18317A382 | 19 December 2018 | Issuance of Amendment No. 313, Revise Technical Specification 3.3.3.6, Post-Accident Instrumentation |
ML19136A251 | 13 June 2019 | Handout for the June 13, 2019 Pre-submittal Public Meeting for Planned License Amendment Request Regarding Fuel Handling Accident Analysis |
ML19210E926 | 5 December 1979 | Forwards 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 |
ML19275A856 | 17 October 1979 | Forwards 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 |
ML19291B904 | 5 December 1979 | Forwards Revision of Selected Provisions of 791120 Response to TMI Lessons Learned Task Force Recommendations.Sequential Shutdowns Preferred to Concurrent.Implementation Schedule Encl |
ML19331D629 | 26 August 1980 | Forwards 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 |
ML19339B706 | 29 October 1980 | Responds 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 |
ML20023A020 | 15 January 2020 | Rev. 45 to Emergency Plan and Emergency Plan Implementing Procedure |
ML20082D464 | 4 April 1995 | Proposed 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 |
ML20148B966 | 18 January 1980 | Submits 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 |
ML20202B253 | 22 April 1986 | Emergency Operating Procedure 74-1122058-00, Revs to Abnormal Transient Operating Guidelines |
ML20203P688 | 5 May 1986 | Vols 1 & 2 to Arkansas Nuclear One Unit 2,CRDR Final Summary Rept |
ML20205F803 | 2 April 1999 | Forwards Draft Info Notice Describing Unanticipated Reactor Water Draindown of Listed Plants |
ML20205P464 | 15 April 1999 | Forwards 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 |
ML21134A241 | 8 April 2021 | 8_AN2-2021-03 Final Written Exam |
ML22124A069 | 10 May 2022 | RVCH Penetration No. 1 Relief Request Public Meeting May 10, 2022 (EPID L-2022-LRM-0036) (Slides) |
ML22167A124 | 16 June 2022 | Emergency Plan Implementing Procedure Revision |
ML23142A106 | 24 May 2023 | Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035 |
ML23208A211 | 27 July 2023 | Entergy 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 Scheme | 18 July 2011 | Arkansas Nuclear One Units 1 & 2, Proposed Emergency Action Levels Using NEI 99-01 Revision 5 Scheme |
NRC Generic Letter 1985-02 | 17 April 1985 | NRC 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 1985-05 | 31 January 1985 | NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events |
NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |
NRC Generic Letter 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
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) |
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 |
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-1432 | 30 October 2020 | Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-1432 |