Pages that link to "Exelon"
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The following pages link to Exelon:
Displayed 50 items.
- RS-14-138, Enclosuresponses to Requests for Additional Information Re Environmental RAI AQ-11 to AQ-15 (as Amended by Exelon Generation Letter RS-14-283) (← links)
- RS-14-235, Response to NRC Request for Additional Information, Set 38, Dated 08/04/2014; LRA Changes from NRR Staff Feedback on 07/30/2014 Telecon; and, LRA Changes from NRC Region Ill IP-71002 Inspection, to Byron, Units 1 & 2, Braidwood, Units 1 & (← links)
- RA-14-032, Braidwood, Units 1 and 2, Attachment 2, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1001, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 2B, and 2C, Pages Bw 3-81 - (← links)
- RS-14-073, Three Mile Island, Unit 1 - Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54{f) Regarding Recommendation 2.1 of the Near-Term Task Force (← links)
- RS-14-039, Quad Cities, Units 1 and 2, Attachment 4 and 5 to RS-14-039, HI-2104790, Rev. 1, Nuclear Group Computer Code Benchmark Calculations, and HI-2125245, Rev. 4, Licensing Report for Quad Cities Criticality Analysis for Inserts-Non Proprietary (← links)
- RS-11-180, Braidwood Units 1 & 2, Byron Units 1 & 2, Clinton Unit 1, Dresden Units 2 & 3, LaSalle Units 1 & 2, Limerick Units 1 & 2, Oyster Creek, Peach Bottom Units 2 & 3, Quad Cities Units 1 & 2 & Three Mile Island Unit 1, Response to NRC Bulletin (← links)
- Press Release-10-102, NRC Accepts Application for Early Site Permit at Victoria County Site in Texas (← links)
- Press Release-10-052, NRC Meeting April 15 in Victoria, Texas, to Discuss Review Process for Early Site Permit Application (← links)
- RS-09-079, Clinton Power Station, Unit 1 - Request for Amendment to Technical Specifications Section 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation, to Eliminate Requirements for Main Steam Line Isolation on High Turbine Building (← links)
- RS-09-036, Dresden, Units 2 & 3, and Quad Cities, Units 1 & 2, Request for License Amendment to Technical Specification (TS) 3.4.5, RCS Leakage Detection Instrumentation, TS 5.6.5, Core Operating Limits Report (Color), and Renewed Facility Operating (← links)
- RA-09-029, Oyster Creek, Supplement to License Amendment Request Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action, and Clarification of (← links)
- RA-09-016, Supplement to License Amendment Request for: Oyster Creek Technical Specification Change Request No. 336, Three Mile Island Unit 1 Technical Specification Change Request No. 330, Deletion of Technical Specification Requirements for Review (← links)
- Kennett Square (← links)
- NEI 99-01, Braidwood, Units 1 and 2, Attachment 2, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1001, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 2B, and 2C, Pages Bw 3-81 - (← links)
- GEH Hitachi (← links)
- NMP2L2588, Nine Mile Point, Unit 2 - Response to Request for Additional Information Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee (← links)
- Press Release-I-07-029 - NRC to Discuss 2006 Assessment for Oyster Creek Nuclear Plant at Public Meeting in Toms River, N.J., on May 23, Press Release-I-07-029 - NRC to Discuss 2006 Assessment for Oyster Creek Nuclear Plant at Public Meeting in Toms (← links)
- NMP1L3186, Nine Mile Point Nuclear Station, Units 1 and 2 - Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents (← links)
- RS-17-156, Quad Cities, Units 1 and 2, Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation (← links)
- RS-17-068, Peach Bottom, Units 2 and 3 - Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation (← links)
- JAFP-17-0063, James A. FitzPatrick - Sixth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number (← links)
- RS-17-065, LaSalle County Station, Units 1 and 2 - Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of (← links)
- RS-16-179, Three Mile Island Nuclear Station, Unit 1 - High Frequency Supplement to Seismic Hazard Screening Report, Response to Nrg Request for Information Pursuant to 1 O CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review (← links)
- RS-16-122, Byron, Units 1 and 2 - Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi (← links)
- LIC-16-0048, Fort Calhoun Station Request for Relaxation of March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and Reliable Spent Fuel Pool Instrumentation (← links)
- LIC-16-0058, Fort Calhoun Station, Unit 1, Intent to Comply with ASME Code Case N-729-1, Alternative Examination Requirements for PWR Reactor Vessel Upper Heads with Nozzles Having Pressure-Retaining Partial-Penetration Welds Section Xi, Division 1, (← links)
- RA-16-042, Oyster Creek - Revision to Commitments Relating to Relaxation of the Phase 1 Schedule Requirements for Order EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident (← links)
- NEI 12-01, Oyster Creek - Response to March 12, 2012, Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, (← links)
- RS-16-012, Peach Bottom, Units 2 and 3 - Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi (← links)
- RS-15-208, Braidwood Station, Units 1 and 2 - Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number (← links)
- RS-15-185, Dresden and LaSalle County - Supplemental Information Regarding Seismic Hazard Risk Evaluation and Seismic Hazard Prioritization Results - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of (← links)
- RS-15-151, Peach Bottom, Units 2 and 3 - Second Six-Month Status Report for Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under (← links)
- RS-15-114, Peach Bottom, Units 2 and 3 - Response to March 12, 2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations of the Near-Term Task Force Review of Insights from the Fukushima (← links)
- JAFP-14-0146, James A. FitzPatrick - First Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number (← links)
- RS-14-301, Three Mile Island, Unit 1 - Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the (← links)
- RS-14-298, LaSalle County, Units 1 & 2 - Expedited Seismic Evaluation Process Report Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi (← links)
- RS-14-032, Report RS-14-032, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal 1 (Annex a) for the Three Mile Island Nuclear Station, Uni (← links)
- RS-14-001, Enclosure 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal 1 (Annex a) for the Peach Bottom, Unit 3. Report No. RS-14-001 (← links)
- JAFP-13-0035, Response to Request for Additional Information on Core for Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment 23 (← links)
- RS-14-007, Braidwood Station, Units 1 and 2 - Second Six-Month Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number (← links)
- RA-13-075, Exelon Generation Company, LLC Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response (← links)
- RS-12-167, Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal 1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 12 of 13 (← links)
- RS-13-067, Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal 1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 11 of 13 (← links)
- RS-12-168, Dresden, Units 2 & 3, Exelon Generation Co., Llc'S 180-day Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi (← links)
- RS-12-166, Clinton Power Station, Unit 1, Exelon Generation Company, LLCs 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights (← links)
- RS-12-199, Braidwood, Units 1 & 2, Bryson, Units 1 and 2, Response to RAI Related to License Amendment Request to Revise Technical Specifications to Exclude Solid State Protection System (Ssps) Input Relays from Channel Operational Test Surveillance (← links)
- RA-12-058, Exelon Generation Company, Llc'S 60-Day Response to March 12, 2012 Request 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 (← links)
- RA-12-057, Exelon Generation Company, Llc'S 60-Day Response to March 12, 2012 Request 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 (← links)
- RS-12-049, Exelon Generation Company, Llc'S 30-Day Response to March 12, 2012 Request 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 (← links)
- RS-11-123, LaSalle County Station, Units 1 and 2, Supplemental Information Related to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions (← links)