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ML21361A20920 December 2021Supplemental Information for Revision 22 to Updated Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
ML21307A19828 October 20212 to Updated Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
ML20219A12917 August 2020Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai Ichi Accident
ML19028A03011 April 2019FENOC - Beaver Valley Power Station, Unit 1 & 2; Davis-Besse Nuclear Power Station Unit 1; and Perry Nuclear Power Plant Unit 1 - Approval of Certified Fuel Handler Training and Retraining Program
ML15307A34923 February 2016Issuance of Amendment Concerning Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control (CAC No. MF3720) (L-14-106)
ML15174A2571 September 2015Letter to Licensees Coordination of Request for Information for Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events
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
ML14030A04620 February 2014Letter from Eric J. Leeds Supplemental Information Related to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1
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
ML13044A5611 March 2013Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Flooding Hazard Reevaluation for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML12054A73512 March 2012Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
ML12054A67912 March 2012Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation
ML12056A04512 March 2012Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
ML12056A04412 March 2012Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status12 March 2012Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
NRC-2012-0068, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events12 March 2012Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
ML09086006528 January 200901/23/09 & 01/28/09 Summary of Telecons Between NRC Staff and Prairie Island License Review Project
ML0525105997 September 2005EA-05-167, EA-05-168, Firstenergy Nuclear Operating Co, Perry Nuclear Power Plant, Response to Disputed Violations
ML0522105158 August 2005Denial of Non-cited Violations Contained in NRC Inspection Report 05000400/2005003
ML0236102009 December 2002License Amendment Request Pursuant to 10 CFR 50.90: Alternative Source Term Update of Design Basis Analysis for Fuel Handling Accident
L-02-041, Annual Financial Reports & Certified Financial Statements for Perry Nuclear Power Plant, Davis-Besse Nuclear Power Station & Beaver Valley Power Station24 April 2002Annual Financial Reports & Certified Financial Statements for Perry Nuclear Power Plant, Davis-Besse Nuclear Power Station & Beaver Valley Power Station
ML03111044913 October 1999Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes
RIS 1999-02, Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes13 October 1999Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes
NRC Generic Letter 1983-1124 June 1999NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis
ML20205P43715 April 1999Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding
ML20203A52127 January 1999Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps
NRC Generic Letter 1998-0114 January 1999NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants
PY-CEI-NRR-2352, Suppl to 980909 LAR to License NPF-58,improving Licensing & Design Basis for Isolation of Feedwater Penetrations, Including Sensitivity Study Performed to Examine Radiological Significance of Leakage Through FW Sys Cvs6 January 1999Suppl to 980909 LAR to License NPF-58,improving Licensing & Design Basis for Isolation of Feedwater Penetrations, Including Sensitivity Study Performed to Examine Radiological Significance of Leakage Through FW Sys Cvs
PY-CEI-NRR-2322, Application for Amend to License NPF-58,stipulating That Water Leakage from Feedwater motor-operated CIVs Will Be Added Into Primary Coolant Sources Outside of Containment Program & Valves Need Not Be Included in Test Program9 September 1998Application for Amend to License NPF-58,stipulating That Water Leakage from Feedwater motor-operated CIVs Will Be Added Into Primary Coolant Sources Outside of Containment Program & Valves Need Not Be Included in Test Program
NRC Generic Letter 1998-0414 July 1998NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i
NRC Generic Letter 1998-0228 May 1998NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
ML00370896420 April 1998Annual Financial Reports and Certified Financial Statements for the Perry Nuclear Power Plant (Docket Number 50-440) and the Davis-Besse Nuclear Power Station (Docket Number 50-346)
PY-CEI-NRR-2269, Comment on Proposed Rule 10CFR50.NRC Should Demonstrate That Not Only Is Code Process Flawed,But That Proposed Change Justified from Cost Versus Safety Protective3 April 1998Comment on Proposed Rule 10CFR50.NRC Should Demonstrate That Not Only Is Code Process Flawed,But That Proposed Change Justified from Cost Versus Safety Protective
NRC Generic Letter 1997-0630 December 1997NRC Generic Letter 1997-006: Degradation of Steam Generator Internals
NRC Generic Letter 1997-0517 December 1997NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques
NRC Generic Letter 1997-0430 September 1997NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules
ML20198L52423 September 1997Insp Rept 50-440/97-08 on 970721-0827.Violations Noted. Major Areas Inspected:Unresolved Items & Insp follow-up Items Identified by Design Insp Conducted from 970127-0327
NRC Generic Letter 1997-0215 May 1997NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report
Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents24 February 1997Implementation of a New Constraint on Radioactive Air Effluents
NRC Generic Letter 1995-0631 January 1997NRC Generic Letter 1995-006: Changes in Operator Licensing Program
NRC Generic Letter 1996-0518 September 1996NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
ML20115J98330 June 1996Individual Plant Examination of External Events for Severe Accident Vulnerabilities for Pnpp
NRC Generic Letter 1996-0426 June 1996NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks
NRC Generic Letter 1996-0331 January 1996NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits
NRC Generic Letter 1989-1024 January 1996NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors
NRC Generic Letter 1996-0110 January 1996NRC Generic Letter 1996-001: Testing of Safety-Related Logic Circuits
ML20101B0003 January 1996Questions Re post-LOCA ECCS Strainer Blockage & Insulation Problem
NRC Generic Letter 1995-1015 December 1995NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation
NRC Generic Letter 1995-0717 August 1995NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves
NRC Generic Letter 1995-0428 April 1995NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues
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