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JAFP-21-0014, Exemption Request to Extend the 10-Year ASME Code Updates for the Inservice Inspection, Containment Inservice Inspection, and Inservice Testing Programs3 March 2021Exemption Request to Extend the 10-Year ASME Code Updates for the Inservice Inspection, Containment Inservice Inspection, and Inservice Testing Programs
ML20100J7171 May 2020Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident
ML19168A19629 August 2019Staff Assessment of Flood Hazard Integrated Assessment
ML19239A03523 August 2019NRC-2019-000303 - Resp 1 - Final, Agency Records Subject to the Request Are Enclosed
ML16222A7876 September 2016Unit 1; and Quad Cities Nuclear Power Station, Units 1 and 2 - Review of Certified Fuel Handler Training and Retraining Program
ML16075A32916 March 2016OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations
ML16200A34722 December 2015Confirming Initial License Exam at Quad Cities in April 2016
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
RS-14-077, Response to Request for Additional Information Re Potential Loss of Spent Fuel Pool Cooling5 March 2014Response to Request for Additional Information Re Potential Loss of Spent Fuel Pool Cooling
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
ML13309A23030 September 2013Transcript of 10 CFR Petition Review Board Re(Garding) General Electric Mark I and II (Boiling Water Reactors) Bwrs, 09-30-2013, Pages 1-98(100)
ML12054A73512 March 2012Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
ML12054A69412 March 2012Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents
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
ML12056A04312 March 2012Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark II Containments
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
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-2012-0069, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments12 March 2012Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments
CY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 197114 July 2011G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971
ML11167A1148 June 2011Transcript of 10 CFR 2.206 Petition Review Board Conference Call Re GE Mark 1 Bwrs, June 08, 2011, Pages 1-74
RS-10-172, Additional Information Supporting the Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.12 October 2010Additional Information Supporting the Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.
ML0822000519 July 2008Comment (2) of David P. Helker, on Behalf of Exelon and Amergen, Concerning Draft Regulatory Guide DG-1195, Availability of Electric Power Sources.
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
NRC Generic Letter 1998-0114 January 1999NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants
ML20196A97620 November 1998Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding of Safety-Related Power-operated Gate Valves
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
SVP-98-165, Provides Notification of Completion of Actions Listed in NRC CAL RIII-98-01,in Response to Directions of CAL to Notify NRC in Writing When Actions Listed in CAL Have Been Completed29 April 1998Provides Notification of Completion of Actions Listed in NRC CAL RIII-98-01,in Response to Directions of CAL to Notify NRC in Writing When Actions Listed in CAL Have Been Completed
SVP-98-094, Provides Revised Response to Violations Noted in Insp Repts 50-254/97-14 & 50-265/97-14.Corrective Actions:Performed Instrument Error Analysis & Detailed Calculation to Determine Min Pressure Criteria & Revised Qcos 2900-0113 March 1998Provides Revised Response to Violations Noted in Insp Repts 50-254/97-14 & 50-265/97-14.Corrective Actions:Performed Instrument Error Analysis & Detailed Calculation to Determine Min Pressure Criteria & Revised Qcos 2900-01
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
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
ML20134N25518 November 1996Responds to NRC Final Rept on Spent Fuel Storage Pool Safety Issues
NRC Generic Letter 1996-0518 September 1996NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
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
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
ML0312004432 September 1994Withdrawn - NRC Generic Letter 1994-004: Voluntary Reporting of Additional Occupational Radiation Exposure Data
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