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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
ML20122A24018 May 2020Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Ichi Accident
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
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
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)
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
RS-13-002, Response to Request for Additional Information Related to License Amendment Request to Technical Specification 3.7.3, Ultimate Heat Sink.18 January 2013Response to Request for Additional Information Related to License Amendment Request to Technical Specification 3.7.3, Ultimate Heat Sink.
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-2012-0069, 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
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
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.
RS-07-016, Response to LaSalle County Station, Units 1 & 2 - Denial of License Amendment24 January 2007Response to LaSalle County Station, Units 1 & 2 - Denial of License Amendment
IR 05000373/200300329 July 2003IR 05000373-03-003, IR 05000374-03-003, on 04/01/2003 - 06/30/2003, Exelon, LaSalle County Station, Units 1 & 2, Operator Workaround. No Violations Noted
ML03057002329 April 2003TIA, Response to Task Interface Agreement 2001-14, Evaluation of LaSalle Water Hammer Analysis
ML03064001528 April 2003TIA, Evaluation of LaSalle Water Hammer Analysis, Revision 1
RS-03-006, Response to Task Interface Agreement 2001-14, Evaluation of LaSalle Water Hammer Analysis.13 January 2003Response to Task Interface Agreement 2001-14, Evaluation of LaSalle Water Hammer Analysis.
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
ML20196B14423 November 1998Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Bindings 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
ML20236L8046 July 1998Safety Evaluation Granting Licensee 980304 Request for Second 10-yr Interval Pump & Valve IST Program Plan,Rev 2, Including Changes to 2 ASME Boiler & Pressure Vessel Code Relief Requests Previously Submitted in Rev 1
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
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
ML20197A48616 December 1997Provides Supplemental Response to NRC Final Rept of Spent Fuel Storage Pool Safety Issues Lasalle,Units 1 & 2.Rev 1 to Calculation L-001378, Calculated Probability for Sustained Boiling in LaSalle Fuel Pools, Encl
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
ML22112A07531 January 1997Abb System 80+ Design Control Document - Volume 23
ML22112A08131 January 1997Abb System 80+ Design Control Document - Volume 22
ML20135D4666 December 1996Safety Evaluation Granting Relief Request RP-01 & Alternative Testing Imposed Per 10CFR50.55a(f)(6)(i) Based on Impracticality of Performing Required Testing
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
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