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 Issue dateTitle
ML23303A13627 October 2023Enclosure C - Pnpp Technical Specification Bases, Revision 18
IR 05000440/20230022 August 2023Integrated Inspection Report 05000440/2023002
IR 05000440/202301029 June 2023Comprehensive Engineering Team Inspection Report 05000440/2023010
IR 05000440/202200410 February 2023Integrated Inspection Report 05000440/2022004; and 07200069/2022001 and Exercise of Enforcement Discretion
L-22-271, Emergency Plan20 December 2022Emergency Plan
L-22-254, Emergency Plan for Perry Nuclear Power Plant, Including EAL Matrix Revision 2218 November 2022Emergency Plan for Perry Nuclear Power Plant, Including EAL Matrix Revision 22
L-22-099, Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis1 June 2022Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis
ML20219A12917 August 2020Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai Ichi Accident
IR 05000440/202000214 August 2020Integrated Inspection Report 05000440/2020002
ML20115E2437 May 2020Staff Assessment of Flooding Focused Evaluation
IR 05000440/201801117 December 2018Errata - Perry Nuclear Power Plant - NRC Triennial Fire Protection Inspection Report 05000440/2018011 (DRS-A.Dahbur)
ML18330A17226 November 2018NRC Triennial Fire Protection Inspection Report 05000440/2018011 (DRS)
ML22146A09027 July 2017Retake Admin JPMs
ML22146A07918 July 20172017 Perry Retake Exam Administered Admin JPMs
ML15110A0443 April 20152015 Perry Nuclear Station Initial License Exam Administered Makeup JPMs
ML15061A0822 March 2015Response to Request for Additional Information Regarding a Request to Amend Technical Specification 3.4.11. RCS Pressure and Temperature (Pit) Limits
L-15-023, Response to Request for Additional Information Regarding a Request to Amend Technical Specification 3.4.11, RCS Pressure and Temperature (Pit) Limits27 February 2015Response to Request for Additional Information Regarding a Request to Amend Technical Specification 3.4.11, RCS Pressure and Temperature (Pit) Limits
IR 05000440/20140044 November 2014IR 05000440/2014004, on 07/01/2014 - 09/30/2014, Perry Nuclear Power Plant; Radiological Hazard Assessment and Exposure Controls
ML14141A46030 June 2014Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident
L-14-150, Request for Licensing Action to Amend Technical Specification 3.4.11. RCS Pressure and Temperature (P/T) Limits23 June 2014Request for Licensing Action to Amend Technical Specification 3.4.11. RCS Pressure and Temperature (P/T) Limits
IR 05000440/20120057 February 2013IR 05000440-12-005 & 0720069-12-002, 10/01/2012 - 12/31/2012, Perry Nuclear Power Plant, Maintenance of Emergency Preparedness; Radiological Hazard Assessment and Exposure Controls; Other Activities
L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident27 November 2012FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident
IR 05000440/201200224 April 2012IR 05000440-12-002, on 01/01/2012 - 03/31/2012, Perry Nuclear Power Plant, Outage Activities, Integrated Inspection Report
ML12056A04912 March 2012Enclosure 3 - Recommendation 2.3: Seismic
ML12053A34012 March 2012Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
ML12056A05012 March 2012Enclosure 4 - Recommendation 2.3: Flooding
IR 05000440/201100813 January 2012IR 05000440-11-008, 10/31/2011 - 12/02/2011; Perry Nuclear Power Plant, Component Design Bases Inspection (CDBI)
IR 05000440/20110041 November 2011IR 05000440-11-004, on 07/01/2011 - 09/30/2011; Perry Nuclear Power Plant: Maintenance Risk Assessment and Emergent Work Control; Radiological Hazard Assessment and Exposure Controls; Occupational Dose Assessment and Performance Indicator V
ML11186A90430 June 2011Notification of Potential Part 21 Appendix R Analyses Fails to Recognize Hot-Short Failure Resulting in the Loss of an Essential Electrical Bus
IR 05000440/20090044 November 2009IR 05000440-09-004 on 07/01/2009 - 09/30/2009 for Perry Nuclear Power Plant
L-09-218, Submittal of Technical Specification Bases, Revision 75 October 2009Submittal of Technical Specification Bases, Revision 7
IR 05000440/200800526 January 2009IR 05000440-08-005, on 10/01/2008 - 12/31/2008, Refueling and Other Outage Activities, Follow-up of Events and Notices of Enforcement Discretion
ML08301045427 October 2008IR 05000440-08-004 on 07/01/2008 - 09/30/2008 for Perry
IR 05000440/200700512 February 2008IR 05000440-07-005, on 10/01/2007 - 12/31/2007, Perry, Equipment Alignment, Post-Maintenance Testing, ALARA Planning and Controls; Problem Identification and Resolution, Other Activities
IR 05000440/20060032 August 2006IR 05000440-06-003 on 04/01/2006 - 06/30/2006 for Perry Nuclear Power Plant; Adverse Weather Protection; Surveillance Testing; Event Followup
IR 05000440/20050097 November 2005IR 05000440-05-009 on 07/01/2005 - 9/30/2005 for Perry; Equipment Alignment, Fire Protection, Operator Performance During Non-Routine Evolutions & Events, Surveillance Testing, Occupation Radiation Safety, Identification & Resolution of Pro
ML0519301428 July 2005IR 05000440-05-003; 01/10/2005 - 05/06/2005; Perry Nuclear Power Plant; IP 95003, Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input.
IR 05000440/20050025 May 2005IR 05000440-05-002, on 01/01/2005 - 03/31/2005; Perry Nuclear Power Plant; Evaluations of Changes, Tests, or Experiments; Equipment Alignment; Operator Performance During Non-Routine Evolutions and Events; Post-Maintenance Testing; Refuelin
ML03070060927 January 2003Final As-Administered Administrative Jpms for the Perry Initial Examination - Jan/Feb 2003
ML03078050227 January 2003Inital Submittal of the Written Examination for the Perry Examination - Jan/Feb 2003
ML03078014327 January 2003Initial Submittal of the Administrative Jpms for the Examination - Jan/Feb 2003
ML0305805317 February 2002Initial Ro/Sro Examination 02/2003
ML20198D9719 November 1998Petition Per 10CFR2.206 Requesting That Facility Be Immediately Shut Down & OL Be Suspended or Modified Until Such Time That Facility Design & Licensing Bases Properly Updated to Permit Operation with Failed Fuel Assemblies
ML20216H93614 April 1998Rev 1 to Proposed TS Bases,Reflecting Changes Made Since Original Implementation of TS in Improved Format in June 1996
Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures9 July 1997Inadequate or Inappropriate Interim Fire Protection Compensatory Measures
IR 05000440/199720110 June 1997Insp Rept 50-440/97-201 on 970217-0327.Issues Identified Which Challenged Capability of Sys to Perform Complete Scope DBA Mitigation Actions.Major Areas Inspected:Hpcs & Eec Sys
ML20140F83710 June 1997Insp Rept 50-440/97-201 on 970217-0327.Issues Identified Which Challenged Capability of Sys to Perform Complete Scope DBA Mitigation Actions.Major Areas Inspected:Hpcs & Eec Sys
ML20083A6845 May 1995Proposed Tech Specs Re Changes to App a TSs
ML20044B67722 February 1993LER 93-004-00:on 930121,MOV Testing of Main Steam Line Drain & Bypass Outboard Isolation Valve Indicated That Thrust Less than Design Thrust to Close Valve Under Accident Conditions. Review,Per GL 89-10 in progress.W/930222 Ltr
NRC Generic Letter 1992-026 March 1992NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown.
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