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    "query_string": "[[Topic::Reactor Vessel Water Level]] [[Site::Three Mile Island]]",
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	Issue date	Title
ENS 43780		Unusual Event Declared Due to Unexpected Reactor Vessel Water Level Change During a Refueling Outage with Irradiated Fuel in the Core
IR 05000289/1982006	4 June 1982	IE Insp Rept 50-289/82-06 on 820413-0511.No Noncompliance Noted.Major Areas Inspected:Previous Insp Findings,Plant Operations During long-term Shutdown Including Facility Log & Tours & RCS Insp & Requalification
IR 05000289/1986006	8 July 1986	Insp Rept 50-289/86-06 on 860411-0516.Violation Noted:Senior Reactor Operator Not in Control Room at All Times W/Rcs Greater than 200 F.Deviation Noted:One Supervisor Not Trained within Last 2 Yrs
IR 05000289/1986021	12 February 1987	Safety Insp Rept 50-289/86-21 on 861031-1205.No Violations Noted.Major Areas Inspected:Plant Operations at Power & in Cold Shutdown,Including Fire Door operability,10CFR50,App R Meeting,Core Flood Sys & Refueling Preparation
IR 05000289/1988005	13 July 1988	Insp Rept 50-289/88-05 on 880515-06-11 & 17.No Violations Noted.Major Areas Inspected:Loss of Main Feedwater Regulating Valve Differential Pressure Transmitter & Resulting Transient
IR 05000289/1988013	23 August 1988	Safety Insp Rept 50-289/88-13 on 880612-0715.Violations Noted.Major Areas Inspected:Power Operations,Outage Activities & Transition from One Mode to Another,Including Plant Operations,Equipment Operability & Security Program
IR 05000289/2007005	11 February 2008	IR 05000289-07-005, on 10/01/2007 - 12/31/2007; Three Mile Island, Unit 1; Operability Evaluations, Refueling and Other Outage Activities, Surveillance Testing, and Event Follow-Up
IR 05000320/1985017	12 November 1985	Exam Rept 50-320/85-17 on 850813 & 14,1018,21 & 22.Exam Results:One Reactor Operator & Five of Six Limited Fuel Handling Senior Reactor Candidates Passed
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
ML021130468	15 April 2002	Revision 36 to EPIP-TMI-.03, Emergency Notifications and Call Outs.
ML023500312	2 December 2002	Amergen TMI Emergency Plan Implementing Procedure EPIP-TMI-03, Revision 37, Emergency Notification and Call Outs
ML030580500	13 February 2003	January 2003 Monthly Operating Report for Three Mile Island Unit 1
ML031150585	29 January 1985	Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML032260023	6 August 2003	License Amendment Request, Technical Specification Change Request No. 319 - Reactor Building Tendon Surveillance Criteria & Miscellaneous Administrative Changes and Corrections
ML032820166	30 September 2003	(TMI-1), Tech Spec Pages for Amendment 246 Containment Isolation Valves
ML032820285	30 September 2003	Technical Specification Pages for Three Mile Island Nuclear Station, Unit No. 1 (TMI-1), Issuance of Amendment 246 Containment Isolation Valves
ML033290315	13 November 2003	October 2003 Monthly Operating Report for Three Mile Island, Unit 1
ML033560302	9 December 2003	Exelon/Amergen 180-Day Response to NRC Generic Letter 2003-01, Control Room Habitability.
ML042010072	13 July 2004	Technical Specifications, Reactor Building Tendon Surveillance Criteria
ML050980229	17 June 2005	License Amendment - Monthly Operating Reports and Annual Occupational Radiation Reports
ML051750658	17 June 2005	Tech Spec Pages for Amendment - Monthly Operating Reports and Annual Occupational Radiation Reports
ML061290050	24 April 2006	Submittal of Changes to Technical Specification Bases
ML070860968	22 March 2007	Technical Specification Change Request No. 335, Incorporating Revised Limit or the Variable Low Reactor Coolant System Pressure-Temperature Core Protection Safety Limit
ML070930360	31 January 2005	Cps/Usar, Appendix D, Requirements Resulting from TMI-2 Accident, Revision 11
ML072880418	15 October 2007	Tech Spec Pages for Amendment 262 Regarding Reactor Coolant System Pressure-Temperature Limit
ML080670419	7 March 2008	CDBI Findings
ML080790674	19 March 2008	Slides, NRC Annual Performance Assessment of Three Mile Island - 2007 Reactor Oversight Program.
ML081270219	28 April 2008	Submittal of Changes to Technical Specifications Bases
ML092710463	22 October 2009	Renewed Facility Operating License
ML103120069	12 January 2011	Issuance of Amendment Request to Relocate Surveillance Frequencies to a Licensee Controlled Program
ML121080437	7 May 2012	Issuance of Amendment Administrative Technical Specification Changes
ML12116A189	28 February 2012	Draft Written Exam (Folder 2)
ML12137A348	30 April 2012	Final Written Examination with Answer Key (401-5 Format) (Folder 2)
ML14164A056	30 May 2014	Attachment 11: Discussion of Revision to the Radiological Emergency Plan Annex for Three Mile Island Nuclear Station, Page TMI 3-80 Through End
ML14164A079	30 May 2014	Attachment 11: Discussion of Revision to the Radiological Emergency Plan Annex for Three Mile Island Nuclear Station, Cover Through Page TMI 3-79
ML16280A402	6 October 2016	License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing.
ML18108A176	13 April 2018	Submittal of Changes to Technical Specifications Bases

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