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 Issue dateTitle
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
ML21361A22620 December 2021Supplemental Information for Revision 22 to Updated Safety Analysis Report, Chapter 7, Instrumentation and Controls Systems
ML21361A22220 December 2021Supplemental Information for Revision 22 to Updated Safety Analysis Report, Chapter 2, Site Characteristics, Sections 2.0 to 2.4 (Redacted)
ML21361A21820 December 2021Supplemental Information for Revision 22 to Updated Safety Analysis Report, Chapter 6, Engineered Safety Features
ML21361A21320 December 2021Supplemental Information for Revision 22 to Updated Safety Analysis Report, Chapter 10, Steam and Power Conversion System
ML21361A20920 December 2021Supplemental Information for Revision 22 to Updated Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
ML21361A19820 December 2021Supplemental Information for Revision 22 to Updated Safety Analysis Report, Chapter 15, Accident Analysis
ML21361A19720 December 2021Supplemental Information for Revision 22 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant Systems and Connected Systems
ML21361A19620 December 2021Supplemental Information for Revision 22 to Updated Safety Analysis Report, List of Figures
ML21361A19420 December 2021Supplemental Information for Revision 22 to Updated Safety Analysis Report, Chapter 8, Electric Power
ML21361A18720 December 2021Supplemental Information for Revision 22 to Updated Safety Analysis Report, Chapter 12, Radiation Protection (Redacted)
ML21307A21628 October 20212 to Updated Safety Analysis Report, Chapter 7, Instrumentation and Controls Systems
ML21307A20828 October 20212 to Updated Safety Analysis Report, Chapter 6, Engineered Safety Features
ML21307A20228 October 20212 to Updated Safety Analysis Report, Chapter 10, Steam and Power Conversion System
ML21307A19828 October 20212 to Updated Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
ML21307A18628 October 20212 to Updated Safety Analysis Report, Chapter 15, Accident Analyses
ML21307A18528 October 20212 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML21307A18428 October 20212 to Updated Safety Analysis Report, Figure List for All Chapters
ML21307A18228 October 20212 to Updated Safety Analysis Report, Chapter 8, Electric Power
ML21106A0187 April 2021Enclosure a - Evaluation Attachment 1 - Proposed Updated Final Safety Analysis Report Text Pages
ML21106A0177 April 2021Enclosure a - Evaluation Attachment 3 - Proposed Updated Final Safety Analysis Report Text Pages
L-20-129, Emergency Plan Amendment Request28 December 2020Emergency Plan Amendment Request
ML17291A70823 October 2017Staff Review of Mitigating Strategies Assessment Report of the Impact of the Re-evaluated Seismic Hazard Developed in Response to the March 12, 2012, 50.54(f) Letter
L-17-046, Revision 20 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection Redacted23 October 2017Revision 20 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection Redacted
ML17234A64623 August 2017Staff Review of High Frequency Confirmation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1
ML16337A3616 December 2016Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1
ML16056A56016 May 2016Unit No.1 - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051
ML16061A3012 March 2016Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: March 15, 2016
ML15240A21227 August 2015NRR E-mail Capture - Resend: Perry Nuclear Power Plant, Unit 1 - Technical Review Checklist Related to Interim ESEP Supporting Implementation of NTTF R2.1, Seismic
ML15238A58625 August 2015NRR E-mail Capture - Perry Nuclear Power Plant, Unit 1 - Technical Review Checklist Related to Interim ESEP Supporting Implementation of NTTF R2.1, Seismic
ML15208A0343 August 2015Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force
ML15148A3761 June 2015Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Published June 9, 2015
ML15082A28823 March 2015Notification of the Intended Use of Lead Use Channels - Operating Cycle 16
L-14-245, Response to Request for Additional Information Regarding Request for Licensing Action on Alternative Accident Source Term Radiological Dose Calculations22 July 2014Response to Request for Additional Information Regarding Request for Licensing Action on Alternative Accident Source Term Radiological Dose Calculations
ML14111A1479 May 2014Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights
ML14090A14520 March 2014Firstenergy Nuclear Operating Co., Enclosure D to L-14-120 - 2734298-R-009, Rev. 1, NTTF 2.1 Seismic Hazard and Screening Report for Perry Nuclear Power Plant, Lake County, Ohio.
ML13338A46022 January 2014Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies
ML14014A20914 January 2014Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Perry Nuclear Power Plant, Unit 1, TAC No.: MF0962 (Revision 1)
L-13-306, Request for Licensing Action Pursuant to 10 CFR 50.59. 50.67. and 50.90: Full Implementation of Alternative Accident Source Term Design Basis Accident Analyses. and an Associated Technical Specification Change6 December 2013Request for Licensing Action Pursuant to 10 CFR 50.59. 50.67. and 50.90: Full Implementation of Alternative Accident Source Term Design Basis Accident Analyses. and an Associated Technical Specification Change
L-13-245, Response to NRC Request for Information Pursuant to 10 CFS 50.54(f) Regarding Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident11 September 2013Response to NRC Request for Information Pursuant to 10 CFS 50.54(f) Regarding Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
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
L-12-312, Notification of the Intended Use of Lead Test Assemblies14 November 2012Notification of the Intended Use of Lead Test Assemblies
ML13008A04928 September 2012Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Appendix a, Resumes and Qualifications, Page A-36
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
ML12056A04712 March 2012Enclosure 1 - Recommendation 2.1: Seismic
ML12056A04912 March 2012Enclosure 3 - Recommendation 2.3: Seismic
ML12040A2837 February 2012Notification of Potential Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance
ML11270006726 September 2011GE-Hitachi Part 21 Reportable Condition Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance
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