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The following file is a duplicate of this file (more details):
The following 91 pages use this file:
- Exelon
- JAFP-12-0122, Core Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment #23
- 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
- JAFP-13-0126, Core Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan Revision, License Renewal Commitment #23
- 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
- JAFP-16-0172, Response to Request for Additional Information Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Implementation of BWRVIP-05
- 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
- JAFP-17-0104, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4 Path 4: GMRS ≪ 2xSSE
- JPN-98-046, Submits Response to NRC 981029 RAI Re ISI Program Relief Request #10
- L-95-007, Supplement to Response to NRC Generic Letter 95-07 Pressure Locking and Thermal Binding of Safety Related Power Operated Gate Valves, Topical Report # 105
- LIC-06-0087, Fort Calhoun, Unit 1, Revised License Amendment Request, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process and Deletion of Sleeving as a SGT
- 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
- 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,
- M060906, SRM-M060906 - Affirmation Session: I. SECY-06-0166 PG&E Diablo Canyon ISFSI, Motion by San Luis Obispo Mothers for Peace, Sierra Club & Peg Pinard; Ii. SECY-06-0169 Amergen Energy Co. LLC License Renewal for Oyster Creek; Iii. SECY-06-0174
- 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,
- 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 -
- NMP1L3058, Supplemental Response to Request for Additional Information #1 - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements...
- 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
- NMP1L3380, Special Report: Containment High Range Radiation Monitor Instrumentation Channel #11 Inoperable
- 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
- NRC-2015-0190, EnclosuDraft-FRN Exemption [Letter to J. Sauger Response to Request for Exemption from Portions of Title 10 of the Code of Federal Regulations Sections 72.212(a)(2), 72.212(b)(5), 72.212(b)(11), and 72.214]
- NRC-2017-0006, FOIA/PA-2017-0698 (NRC-2017-000696) - Request for Digital Copies of All Non-public Records Dated 06/01/2017-06/30/2017 Regarding HPCS Valve LaSalle Unit 1 (Docket #50-373) and the Reactor Shutdown That Month
- NRC-2018-0169, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order for Fr Publication on
- NUREG-0488, Forwards Environ Tech Spec for Subj Facil,Prepared by NRC Staff.Applicant Has Agreed to Imposition of the Spec.W/Encl 780311 Order W/Cert of Svc,751114 Joint Motion to Terminate Hearing & Tech Spec#NUREG-0488
- PNO-I-02-020, Unusual Event Due to a Hydrogen Gas Ignition in the Off-Gas System (#39348)
- PNO-I-03-016, Oyster Creek Bargaining Unit Strike at Oyster Creek (#39876)
- 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
- 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
- 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
- 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
- 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
- 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
- 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 -
- 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
- RA-19-011, Request for Exemption from 10 CFR 50.54(w)(1 Concerning On-Site Property Damage Insurance and Request for Exemption from 10 CFR 140.11 (a)(4), Concerning Offsite Primary and Secondary Liability Insurance
- 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
- 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
- RS-10-008, Clinton Power Station, Unit 1, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425,
- RS-10-030, Byron, Units 1 and 2, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision
- RS-11-050, Braidwood, Units 1 and 2 - Third 10-Year Inservice Inspection Interval Relief Request I3R-08, Alternative Requirements to ASME Section Xi Appendix Vii (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from
- 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
- 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
- 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
- RS-12-070, Response to Follow-up RAI Questions Related to Exelon Response to RAI Question #7
- RS-12-077, Response to Request for Additional Information Regarding Relief Request 14R-19, Regarding the Flaw Evaluation (RAI #7)
- 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
- 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
- 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
- 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
- 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
- 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
- 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
- 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
- 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
- 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
- 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)
- 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 &
- 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
- 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
- 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
- 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
- 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
- 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
- RS-15-235, Revised Response to Request for Additional Information (RAI) #TR-09 Re License Renewal Application, Environmental Review
- RS-15-289, Nine Mile Point, Unit 2 - High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10CFR 0.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the
- 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
- RS-16-083, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.2 Path 2: GMRS ≪ SSE with High Frequency Exceedances
- RS-16-084, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.2 Path 2: GMRS ≪ SSE with High Frequency Exceedances
- RS-16-085, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.2 Path 2: GMRS ≪Sse with High Frequency Exceedances
- RS-16-086, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.2 Path 2: GMRS ≪ SSE with High Frequency Exceedances
- 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
- RS-16-168, Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information NEI 12-06, Appendix H, Revision 2, H.4.2 Path 2: GMRS ≪ SSE with High Frequency Exceedances
- RS-16-169, Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.4 Path 4: GMRS ≪ 2xSSE (Partial Submittal - High Frequency Work Scope)
- RS-16-170, Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.4 Path 4: GMRS ≪ 2xSSE (Partial Submittal - High Frequency Work Scope)
- RS-16-171, Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.2 Path 2: GMRS ≪ 2xSSE with High Frequency Exceedances
- RS-16-172, Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.2 Path 2: GMRS ≪Sse with High Frequency Exceedances
- 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
- 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
- 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
- RS-17-091, Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.4 Path 4: GMRS ≪ 2xSSE
- RS-17-092, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 4, H.4.4 Path 4: GMRS ≪ 2xSSE
- RS-17-093, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 4, H.4.4 Path 4: GMRS ≪ 2xSSE
- RS-17-119, Byron, Units 1 and 2 - Full Action Request Report AR 792213, MSLB Calc. Energy Release Error, Redacted
- 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
- RS-18-099, NEI 12-06, Appendix H, Revision 4, H.4.5 Path 5: GMRS ≫ 2 X SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information
- RS-18-118, Supplemental Information Related to Application to Revise Technical Specifications to Adopt TSTF-542 Reactor Pressure Vessel Water Inventory Control
- RS-18-147, Supplement #2 to License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies
- RS-19-004, Supplement #3 to License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies
- TMI-10-002, Retake - Draft - Outlines (Facility Letter Dated 1/8/10) Folder 2)
- TMI-16-090, Submittal of Inspection Plan for Reactor Internals, A/Lai #7 Component Evaluation
- U-603084, Submits follow-up to Util 980504 Proposed Amend to License NPF-62 (LS-98-001),providing Description of Testing Program Developed for Static Var Compensators & Minor Corrections Identified for 980504 Submittal.Corrected Bases Pp Encl