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    "query_string": "[[Topic::Reactor Vessel Water Level]] [[Site::Farley]]",
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	Issue date	Title
IA-85-771, Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities	3 January 1986	Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units	23 March 1990	Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown	25 February 1992	Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization	8 April 1993	Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels	10 August 1993	Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications	26 November 1993	Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System	24 May 1994	Undetected Accumulation of Gas in Reactor Coolant System
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1	15 July 1994	Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel	18 January 1996	Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown	18 June 1996	Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves	5 August 1996	Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power	22 October 1996	Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown	11 December 1996	Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown	5 December 1997	Recent Events Involving Reactor Coolant System Inventory Control During Shutdown
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick	5 May 1999	Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
ML031150585	29 January 1985	Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML081820247	23 May 2008	Updated Final Safety Analysis Report, Revision 21, Technical Specifications Bases
ML111960050	2 July 2011	Initial Exam 2011-301 Draft SRO Written Exam
ML14091A144	1 April 2014	Initial Exam 2013-301 Draft RO Written Exam
ML14091A187	1 April 2014	Initial Exam 2013-301 Draft Admin JPMs
ML15138A222	16 April 2015	Emergency Plan, Revision 64, Part 1 of 3
ML15289A227	10 June 2016	Issuance of Amendments Related to TSTF-432-A, Revision 1
ML16049A511	18 February 2016	Initial Exam 2015-301 Final Administrative JPMs
ML16071A136	3 March 2016	Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 3 of 4
ML16071A180	3 March 2016	Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 8
ML16071A195	3 March 2016	Enclosure 6: Clean-Typed EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant
ML17117A370	20 April 2017	Updated Final Safety Analysis Report, Revision 27, Chapter 6 Through Chapter 7
ML17117A374	20 April 2017	Technical Specifications Bases
ML18312A073	30 October 2018	Revision 28 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features and Chapter 7, Instrumentation and Control
ML18312A077	30 October 2018	Technical Specifications Bases
ML19257A503	31 December 1979	Responds to NRC 790913 Ltr Re TMI Lessons Learned Task Force short-term Recommendations.Addresses & Commits to Implementation of NUREG-0578 800101 Requirements
ML19321A692	17 July 1980	Notifies That Util in Process of Finalizing Plans for Instrumentation Sys to Relate Reactor Vessel Water Level to Inadequate Core Cooling.Provides List of Commitments Concerning Instrumentation Sys
ML19340D612	15 December 1980	Proposed Tech Spec Changes to Sections 3.0,4.0 & 6.0, Incorporating Administrative Changes Required by NUREG-0737. Supporting Safety Evaluation Encl
ML20002E096	14 January 1981	Forwards Response to NUREG-0737,in Response to NRC 801031 Ltr.Items Requiring Followup by Unit 2 & Corresponding SER Are Included in Action Item for Requirement
ML20008G342	29 June 1981	Submits Addl Design Info Described in Section 22.5 of SER Suppl 5.Addl Info Re Final Sys Design Not Available Due to Reactor Vessel Water Level Sys Still Under Development & Testing
ML20024C769	5 July 1983	Forwards Comments on SER Re Util Relief Requests from Inservice Testing Requirements.Sers Should Be Revised by 830901 to Ensure That Unit 2 Outage Will Not Be Impacted
ML20028C837	7 January 1983	Forwards Descriptions of Nine Completed License Conditions & Subsequent Commitments Addressing Outstanding Issues Per NUREG-0737.Closure of Completed License Conditions Requested
ML20039D192	22 December 1981	Forwards Commitment Compliance Status of NUREG-0737 Requirements for Facilities
ML20069J218	19 October 1982	Application to Amend License NPF-8,deleting License Conditions Redundant to Generic Regulatory Items.Change Does Not Involve Unreviewed Safety Question.Safety Evaluation Encl
ML20070L845	14 March 1991	Joseph M Farley Nuclear Plant Simulator Certification Rept 1991
ML20071F307	10 March 1983	Provides Results of Reactor Vessel Level Sys Review & Addresses Generic Ltr 82-28.Applicable Provisions of NUREG-0737 Met Except Environ Qualification Criteria of App B.Summary of Feasibility Study Encl
ML20073A558	30 March 1983	Annual Rept for 1982 Required by 10CFR50.59
ML20073K778	6 May 1991	Application for Amends to Licenses NPF-2 & NPF-8,reflecting Southern Nuclear Co,Inc as Operator of Facilities.Discussion of Antitrust Implications & Certificate of Concurrence Encl. Marked-up License NPF-2 Also Encl
ML20090B488	28 February 1992	Forwards Emergency Response Data Sys (ERDS) Communications Description & Survey Questionnaire & ERDS Data Point Library Per & NUREG-1394,Rev 1, ERDS Implementation, Respectively
ML20101H262	22 June 1992	Forwards Response to NRC 920612 Telcon Questions Re ERDS Data Point Library
ML20125A209	28 April 2020	9 to the Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features, and Chapter 7, Instrumentation and Control
ML20125A212	28 April 2020	Revisions to Technical Specification Bases Changes
ML20137Q667	3 January 1986	Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities
ML20235W943	13 October 1987	Summary of Operating Reactors Events Meeting 87-32 on 870922.Notes That Meeting 87-31 Did Not Occur.List of Attendees & Events Discussed & Significant Elements of Events Encl
ML21313A324	28 October 2021	0 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Control

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