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 Issue dateTitleTopic
L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports29 November 2023Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star ReportsFlow Induced Vibration
Power Uprate
L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report13 June 2023Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report
L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations5 May 2023Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head PenetrationsLiquid penetrant
L-23-086, Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair4 March 2023Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak RepairHot Short
Boric Acid
Stroke time
Probabilistic Risk Assessment
Incorporated by reference
Continuous fire watch
L-23-048, Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report1 March 2023Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
L-22-246, Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO7 December 2022Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCORecently irradiated fuel
L-22-200, Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage21 October 2022Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage
ML22292A02318 October 2022Framatome Inc., Document ANP-2718-007Q1NP, Revision 0, Response to Request for Additional Information on Appendix G Pressure-Temperature Limits for 52 EFPY for Davis-Besse Nuclear Power Station - First Energy Nuclear Operating Company
L-22-229, Response to Request for Additional Information Regarding Request to Withhold Information in Framatome Inc. Document ANP-2718P-007 from Public Disclosure & Affidavit13 October 2022Response to Request for Additional Information Regarding Request to Withhold Information in Framatome Inc. Document ANP-2718P-007 from Public Disclosure & Affidavit
L-22-188, Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage22 August 2022Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling OutageNondestructive Examination
L-22-152, Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan5 July 2022Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan
L-22-124, Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building12 May 2022Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building
ML22094A1154 April 2022Response to a Request for Additional Information Regarding a Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation (EPID No. L-202Hot Short
Battery sizing
Weak link
L-22-059, Response to Request for Additional Information on Proposed Inservice Test Alternative RP-321 March 2022Response to Request for Additional Information on Proposed Inservice Test Alternative RP-3
L-22-079, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations16 March 2022Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations
ML22081A14711 March 2022R22 (March 2022) - Steam Generator Tube Inspection Discussion Points 11 March 2022Grab sample
ML22049A06610 February 2022Response to NRC Questions from 2/1/2022 Regulatory Conference on Failed Field Flash Selector Switch
L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A227 January 2022Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2Boric Acid
Loop seal
Hydrostatic
Operating Basis Earthquake
Nondestructive Examination
Finite Element Analysis
Earthquake
Pressure boundary leak
Through-Wall Leak
Power change
ML21147A14627 May 2021Response to Request for Additional Information Regarding Generic Letter 2004-02Mission time
Coatings
ML21132A24212 May 2021Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request
ML21130A21910 May 2021Request for Additional Information Regarding Steam Generator Tube Inspection Reports (EPIDs L2020-LRO-0055, L-2020-LRO-0082, and L2020-LRO-0083)
L-21-106, Response to Request for Additional Information Regarding Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature Limits22 April 2021Response to Request for Additional Information Regarding Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature LimitsHydrostatic
Pressure and Temperature Limits Report
ML21088A34429 March 2021Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-02Boric Acid
Coatings
L-21-101, Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-0229 March 2021Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-02Boric Acid
Coatings
ML21055A88624 February 2021Response to Request for Additional Information Regarding Steam Generator Inspection 180-Day Report
ML21048A08216 February 2021Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request
L-21-030, Response to Request for Additional Information Regarding an Amendment to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications (EPID L-202027 January 2021Response to Request for Additional Information Regarding an Amendment to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications (EPID L-2020
L-20-277, Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request22 January 2021Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment RequestNondestructive Examination
L-20-313, Response to Request for Additional Information Regarding Request for Exemption -Part 73 Force-on-Force7 December 2020Response to Request for Additional Information Regarding Request for Exemption -Part 73 Force-on-ForceExemption Request
Pandemic
Coronavirus
L-20-293, Response Correction to a Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.1630 November 2020Response Correction to a Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16
L-20-162, Supplemental Response to NRC Generic Letter 2004-0230 November 2020Supplemental Response to NRC Generic Letter 2004-02Boric Acid
Coatings
L-20-276, Response to Request for Additional Information Regarding Steam Generator Inspection Report30 October 2020Response to Request for Additional Information Regarding Steam Generator Inspection Report
L-20-183, Response to Request for Additional Information Regarding License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force23 June 2020Response to Request for Additional Information Regarding License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task ForceInternal Flooding
Probabilistic Risk Assessment
Multiple Spurious Operation
Surveillance Frequency Control Program
Fire Protection Program
L-20-161, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter .9 June 2020Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter .Coatings
Deep Dose Equivalent
Power Uprate
Affidavit
L-20-155, Response to Request for Additional Information Regarding Request for Exemptions to Certain Periodic Training Requirements for Security Personnel (Epids L-2020-LLE-0026 to -0040)6 May 2020Response to Request for Additional Information Regarding Request for Exemptions to Certain Periodic Training Requirements for Security Personnel (Epids L-2020-LLE-0026 to -0040)
L-20-097, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity,.14 April 2020Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity,.Safe Shutdown
Deep Dose Equivalent
Power Uprate
L-20-125, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number SRR-1, Rev. 0, Snubber Testing3 April 2020Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number SRR-1, Rev. 0, Snubber TestingFunctionality Assessment
COVID-19
L-20-041, Response to Request for Additional Information Regarding License Amendment Request to Extend Containment Leakage Test Interval3 February 2020Response to Request for Additional Information Regarding License Amendment Request to Extend Containment Leakage Test Interval
L-19-182, Response to RAI Regarding an Application for Order Consenting to Transfer of License2 August 2019Response to RAI Regarding an Application for Order Consenting to Transfer of LicenseIncorporated by reference
L-19-178, Response to Request for Additional Information Regarding Request for Approval of Decommissioning Quality Assurance Program for the Davis-Besse Nuclear Power Station16 July 2019Response to Request for Additional Information Regarding Request for Approval of Decommissioning Quality Assurance Program for the Davis-Besse Nuclear Power Station
L-19-166, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request for Proposed Post-Shutdown Emergency Plan8 July 2019Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request for Proposed Post-Shutdown Emergency PlanMinimum staff
L-19-160, Response to Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications26 June 2019Response to Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications
L-18-209, Response to Request for Additional Information Regarding Steam Generator Technical Specification License Amendment Request28 October 2018Response to Request for Additional Information Regarding Steam Generator Technical Specification License Amendment Request
L-18-121, Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.25 May 2018Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.Aging Management
L-18-125, Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/02 May 2018Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/0Exemption Request
ML18099A1236 April 2018Response to Request for Additional Information Regarding Request to Modify Rtpts Values
L-18-085, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052 April 2018Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805Hot Short
Safe Shutdown
Fire Barrier
Internal Flooding
Probabilistic Risk Assessment
Operator Manual Action
Multiple Spurious Operation
FLEX
Fire Protection Program
L-18-061, Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement16 March 2018Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier RequirementExemption Request
L-17-375, Response to Request for Additional Information Regarding Request 1-TYP-4-BA-01 to Extend the Inservice Inspection Interval for Certain Reactor Vessel Welds5 January 2018Response to Request for Additional Information Regarding Request 1-TYP-4-BA-01 to Extend the Inservice Inspection Interval for Certain Reactor Vessel Welds
L-17-372, Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088)23 December 2017Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088)
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