Pages that link to "NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material"
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The following pages link to NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material:
Displayed 50 items.
- NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre (← links)
- NL-18-021, Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability (← links)
- NL-18-016, Watts Bar, Unit 2 - Application to Revise License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03) (← links)
- NL-17-119, Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19) (← links)
- NL-18-011, Indian Point Energy Center - 2017 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report (← links)
- NL-18-021, Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, Qptr, and TS 3.3.1, 'Reactor Trip System (RTS) . (← links)
- NL-17-144, Indian Point Nuclear Generating Unit 2, Proposed License Amendment Regarding Spent Fuel Storage (← links)
- NL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System (← links)
- NL-17-132, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 227-A, Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, Examination Schedule - NEI 03-08 Needed ... (← links)
- NL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23) (← links)
- NL-17-109, Request for Additional Information for Proposed License Amendment Regarding the Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank Entergy Nuclear Operations, Inc. Indian Point Nuclear Generating, Unit (← links)
- NL-17-008, Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014) (← links)
- NL-17-095, 2017 Form OAR-1 Owners Activity Report for Lnservice Inspection and Repairs and Replacements at Indian Point Unit No. 3 (← links)
- NL-17-051, Indian Point, Units 2 & 3, Final Supplemental Environmental Impact Statement New York State Department of State Concurrence with Consistency Certification (← links)
- NL-17-027, Watts Bar, Unit 2, Application to Modify Operating License Condition Regarding the Actions to Resolve Issues Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System (391-WBN-TS-17-06) (← links)
- NL-17-026, Watts Bar, Unit 1 - Application to Modify Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (390-WBN-TS-17-04) (← links)
- NL-17-017, Entergy Nuclear Operations Comments on Proposed Director'S Decision for 10 CFR 2.206 Petition on Indian Point Baffle Former Bolts Filed by the Union of Concerned Scientists (← links)
- NL-17-012, Browns Ferry, Units 1, 2, and 3, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A (← links)
- NL-16-083, Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 3 (← links)
- NL-16-031, Watts Bar, Units 1 and 2 - Application to Modify Technical Specifications Regarding Discrepancies in Control Room Ventilation and Other Administrative Changes to the Technical Specifications (WBN-TS-16-03) (← links)
- NL-16-033, Watts Bar, Unit 2 - Application to Modify Technical Specifications Regarding Steam Generator Minimum Narrow Range Level Error Correction (← links)
- NL-14-104, Revised FLO-2D Analysis to Address the Current LIP Regarding the Flooding Aspects of Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Indian Point Unit Nos. 2 and 3 (← links)
- NL-15-210, Sequoyah Nuclear Plant, Units 1 and 2 - Withdrawal of Proposed Technical Specification Change, Ultimate Heat Sink (UHS) Temperature Limitations Supporting Alternate Essential Raw Cooling Water (ERCW) Loop Alignments (SQN-TS-13-01 and 13-02 (← links)
- NL-15-118, Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 3 (← links)
- NL-15-177, Watts Bar, Unit 2, Submittal of Replacement Pages for Developmental and Final Revision J of the Technical Specification & Technical Specification Bases, and Developmental and Final Revision E of Technical Requirements Manual & Technical Ma (← links)
- NL-15-181, Watts Bar Unit 1, Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mod (← links)
- NL-15-020, Sequoyah, Units 1 and 2 - Supplement to the Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04) and Response to NRC Requests for Additional In (← links)
- NL-15-021, Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems Indian Point Unit Number 2 (← links)
- NL-15-013, Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval (← links)
- NL-14-115, 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 2014 (← links)
- NL-14-116, 10 CFR 72.48(d)(2) Summary Report for Indian Point, Units 1 and 2 April 2. 2012 to March 19, 2014 (← links)
- NL-14-106, 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project Indian Point Nuclear Generating Unit Nos. 2 & 3 (← links)
- NL-14-045, Correction to Entergy Letter NL-14-045, Indian Point Unit Number 2 (← links)
- NL-14-032, Supplemental Information to Proposed Changes to Indian Point 2 Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Over Pressure Requirements Indian Point Unit Number 2 (← links)
- NL-14-009, Sequoyah, Units 1 & 2 and Watts Bar, Unit 1, Response to NRC Request for Additional Information Related to Review of Potential Breaches of Hesco Modular Flood Barriers and Earthen Embankments Affecting the Updated Hydrologic Analysis Resul (← links)
- NL-14-007, Follow-up Response to NRC Request for Additional Information Related to Overall Integrated Plan in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number E (← links)
- NL-13-128, 10 CFR 72.48(d)(2) Report for Indian Point Energy Center Unit No. 3 (← links)
- NL-13-127, 10 CFR 50.59(d) Report for Indian Point Energy Center Unit 3 (← links)
- NL-13-084, Indian Point Nuclear Power Plant, Units 2 and 3, Reassessment of the Seismic Core Damage Frequency (← links)
- NL-13-028, Indian Point, Units 1, 2 and 3 - 2012 Annual Radioactive Effluent Release Report (← links)
- NL-13-037, Indian Point, Units 2 & 3 - Revision to the Response to Request for Additional Information (RAI) Aging Management Programs (← links)
- NL-12-135, 10 CFR 50.59(d) Report for Indian Point, Units 1 & 2 (← links)
- NL-12-123, Indian Point Nuclear Generating Units 1, 2 & 3 - Correction to Previous Responses Regarding Unit 1 Buried Piping and Unit 2 Auxiliary Feedwater Pump Room Fire Event (← links)
- NL-12-097, Indian Point Unit 3, License Amendment Request for Emergency Diesel Generator Fuel Oil System (← links)
- NL-12-107, Application to Renew Operating Licenses for Indian Point Nuclear Power Reactors Unit 2 and Unit 3, General Correspondence - NL-12-107 (← links)
- NL-12-113, Submittal of Revision 14 to Physical Security, Training and Qualification, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program (← links)
- NL-12-066, License Amendment Request - Cyber Security Plan Implementation Schedule Milestones (← links)
- NL-12-020, Indian Point Unit Nos. 1, 2 & 3 - 2011 Annual Radioactive Effluent Release Report (← links)
- NL-12-024, Indian Point Unit 2, Technical Specification 5.6.7 - IP2 Steam Generator Tube Inspection Report - Spring 2012 Refueling Outage (← links)
- NL-12-029, Indian Point Unit 3, Proposed License Amendment to Allow Use of the Backup Spent Fuel Pool Cooling System While the Spent Fuel Pool Cooling System Is Out of Service (← links)