GNRO-2017/00038, Focused Evaluation of External Flooding
LR-N16-0161, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal
NLS2016053, Nebraska Public Power Districts Spent Fuel Pool Evaluation Report - Response to Nuclear Regulatory Commission Request for Information
PNP 2015-036, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3, Emergency Preparedness - Staffing,Requested Information Items 1, 2, and 6 - Phase 2 Staffing Assessment
LR-N15-0087, Supplement to the Request for Relaxation from Schedule Requirements of NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events - Hope Creek Generating St
RS-14-147, Additional Information Regarding Response to Bulletin 2012-01, Design Vulnerability in Electric Power System.
RA-13-081, Proposed Resolution for Completion of the Seismic Walkdowns Associated with NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term
LR-N13-0205, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident-Base Case Velocity.
RS-13-077, 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 Accident
RS-13-019, Overall Integrated Plan 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 EA-12-049)
L-PI-13-005, Response to March 12, 2012 Request for Information Enclosure 2, Recommendation 2.1 Flooding, Required Response 1, Integrated Assessment Approach
RS-12-170, Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident
RS-12-176, 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 from the Fukushima Dai-ichi Accident
RA-12-057, Company, LLCs 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 Insights
PNP 2012-034, Entergy Nuclear Operations, Inc. 60-Day Response to the March 12, 2012, Information Request, Action Plan for Completing Emergency Communication and Staffing Assessments
RBG-47828, Response to License Renewal Application NRC Request for Additional Information (RAI) Set 8
BSEP 16-0113, High Frequency Supplement to Seismic Hazard Screening Report, Response to Nrg Request for Information Regarding Recommendation 2.1 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident
NL-15-169, Browns Ferry, Units 1, 2 and 3, Supplemental Environmental Report
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center
L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 2; Supplemental Environmental Report
NOC-AE-10002607, License Renewal Application, Environmental Report
SECY-10-0113, VR-SECY-10-0113 - Closure Options for Generic Safety Issue - 191, Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance
NRC-87-0003, Forwards Confirmatory Analysis of Effects of Blasting Activities at Rockwood Stone,Inc Quarry & Design Calculations & Detailed Evaluation for Offsite Blasting in Relation to Unit 2,in Response to
NLS8900315, Application for Amend to License DPR-46,consisting of Proposed Change 69,revising Setpoint Tolerance on lo-lo Set Safety/Relief Valve Pressure Switches & Format & Location of lo-lo Set Specs Per STS
B12554, Provides Addl Info Re Transportation of Nuclear Fuel & Radwaste to & from Plant Per 10CFR51.52 in Response to NRC 870527 Verbal Request.Environ Impacts Considered Acceptable, Based on Addl Info Discussed
3F0287-12, Responds to 870203 Request for Addl Info Re Requirements of 10CFR51.52, Environ Effects of Transportation of Fuel & Waste, in Support of Request to Extend Term of OL to 40 Yrs from Date of Issuance
ELV-00696, Submits Supplemental Info Re Rev to Tech Spec 5.3.1.Rev Necessary in Order That Higher Enrichment Fuel May Be Used for Plant,Starting W/Cycle 3
U-600317, Responds to Unresolved Items Identified During 850827-29 Pump & Valve Operability Review Team Visit.Responses to 30 Audit Concerns Contained in Draft SER Section 3.10.2.4 & Table 3.10.2.1 Provided
B12451, Submits Addl Info Re Transportation of Nuclear Fuel & Radioactive Waste to & from Facility,Per NRC 870220 Request, Including Initial U-235 Fuel Assembly Enrichment
B12461, Responds to NRC 870302 Request for Addl Info Re 861124 Request to Extend OL for 40 Yrs from Date of Issuance. Environ Impacts of Nuclear Fuel & Radwaste Transportation to & from Plant in Accordance w/10CFR51.52,Table S-4
3F1297-24, Provides Supplemental Info to Support Util Response to NRC Request for Addl Info,Dtd 970128.Clarification to Util RAI Responses,Discussed During NRC Audit USI A-46 & Calculations Encl also.W/10 Oversize Drawings
ST-HL-AE-2113, Forwards Revs to FSAR App 7A.S Re Suppl to NUREG-0737, Incorporating Editorial Corrections & Technical Clarifications to Provide Consistency W/Emergency Plan. Conclusions Previously Reached in SER Remain Valid
2CAN089605, Forwards TS Changes Allowing Fuel Enrichments for ANO-2 of Up to 5.0 Weight & U-235 for Review & Approval
JPN-91-071, Forwards Rev 0,Vols 1 & 2 of SIR-90-063, Qualification of Inconel 82 Temperbead Weld Overlay Repair W/Reduced Preheat & No Post Weld Heating & Appendices
W3P88-1343, Application for Amend to License NPF-38,consisting of Proposed Tech Spec Change NPF-38-84,revising Section 5.3.1, Fuel Assemblies. Fee Paid
PY-CEI-NRR-1571, Proposed Tech Specs,Revising Frequency Re Semiannual Radioactive Effluent Release Rept
LD-92-123, Forwards Section 17.3, Design Reliability Assurance Program Plan for Sys 80+ Standard Design, Rev 1 & Responses to 79 Issues Identified in Dser for Sys 80+
NSD-NRC-98-5642, Forwards Rev 4 of Section 2.1 of AP600 Certified Design Matl, ,for Staff Review.Revised Section Is Based on Changes to Rev 3,dtd 970516
05000260/LER-1988-006-01, :on 880824,reactor Protection Sys (RPS) Circuit Protector 2C2 Tripped,Deenergizing RPS Bus.Cause Not Determined.Reactor Protection Circuit Protector Reset & Firing Board Replaced
DCL-89-155, Response to Re Backfitting of Nuclear Power Reactors
05000322/LER-1990-005, :on 900418,noted That on 791205,830808,851218, 861201,870703 & 890119 & 0510,conductor Failures Occurred. Caused by Loss or Reduction of Insulation Resistance or Loss of Continuity for Conductors in Assemblies
NRC-93-0060, Comment on Proposed Generic Communication, Line Item TS Improvements to Reduce Testing During Power Operation. Requests That Section 8.4 of Proposed Generic Ltr Be Modified
05000334/LER-1980-069-01, /01T-0:on 800920,during Surveillance test,motor- Driven Fire Pump Malfunctioned.Caused by Cooling Loss to Motor Bearing,Due to Clogged Water Supply Valve.Isolation Valve Cleared & Supply Line Checked
L-82-428, Forwards Response to IE Bulletin 80-11, Masonry Wall Design, Supplementing Response to NRC 820805 Request for Addl Info
L-87-168, Forwards Response to NRC 870204 Request for Addl Info Re Util 860228 Request to Extend Date of Expiration of OL So That 40-yr Term of License Begins W/Issuance of OL Rather than Date of Issuance of CP
RS-15-221, Revisions to License Renewal Application, Applicants Environmental Report - Operating License Renewal Stage
LR-N14-0051, PSEG Nuclear LLCs Seismic Hazard and Screening 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 Fukushima
RA-14-016, 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) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from the
RS-14-069, 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-
RS-14-071, 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
RS-14-073, 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 Review of
LG-13-145, Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns
LR-N13-0206, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f). Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident.
RA-12-117, 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 from the Fukushima Dai-ichi Accident
RC-12-0174, Final Flooding Walk Down Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.3 of the Near
W3F1-2012-0101, Flooding Walkdown Report - Entergy’S 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-12-172, 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 from the Fukushima Dai-ichi Accident
LR-N12-0172, PSEG Nuclear LLCs 90-Day Response to NRC Request for Information Pursuant to Title 10 Ofthe Code of Federal Regulations 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acci
NL-12-1076, Southern Nuclear Operating Company Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Flooding Aspects of Recommendations 2.1 and 2.3 of the Near-Term Task Force Review of Insights from the Fukushima
BW100044, Radioactive Effluent Release Report
BSEP 02-0067, Response to Request for Additional Information Regarding Request for License Amendments - Extended Power Uprate
LR-N13-0083, Response to March 12, 2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, .