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Category:Licensee 30-Day Written Event Report
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Pages in category "Licensee 30-Day Written Event Report"
The following 200 pages are in this category, out of 480 total.
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- 3F0103-07, Special Report 02-02, Waste Gas Decay Tank Explosive Gas Monitoring Instrumentation Inoperable for More than 30 Days
- 3F0810-02, Emergency Response Data System. Provides 30 Day Report Re Addition of Data Point W356 on 07/22/2010 to CR-3 ERDS Data Point Library for RM-L7
- 3F0810-05, Special Report: Seismic Monitoring Instrumentation Inoperability
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- AEP-NRC-2016-46, Day Report of Changes to or Errors in an Evaluation Model
- AEP-NRC-2018-08, Submittal of 30 Day Report Detailing Unsatisfactory Performance of Health and Human Services Certified Lab
- AEP-NRC-2018-25, Submittal of 30-Day Report Detailing a Testing Error by a Health and Human Services Certified Laboratory
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- CNL-15-034, Submittal of 30-Day Report of Changes and Errors to the Calculated Peak Cladding Temperature
- CNL-18-022, Bellefonte, Unit 2 - Containment Vertical Tendon (V281) Failure - Final Report
- CNS-14-035, Submittal of Post Accident Monitoring (PAM) Report
- CNS-17-021, Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days
- CNS-18-006, Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days
- CP-201401435, Revised Safeguards Event 60-Day Report
- CP-201701010, Special Report 1-SR-17-001-00 for Comanche Peak Nuclear Power Plant, Unit 1 Regarding Inoperable Post Accident Monitoring Instrument Report
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- L-07-083, (Bvps): Pipe Rupture Follow-Up Report
- L-11-246, Report of Changes Pursuant to 10 CFR 50.46
- L-13-289, CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure
- L-14-091, Discovery of Tritium in Groundwater, 30-Day Report in Accordance with the Industry Ground Water Protection Initiative
- L-16-149, Post Accident Monitoring Report
- L-17-195, CFR 71.95 Report - Failure to Follow Conditions of TN-RAM Packaging Certificate of Compliance No. 9233
- L-18-002, Special Report: Inoperable Post Accident Monitoring Instrumentation
- L-18-135, Special Report: Inoperable Post Accident Monitoring Instrumentation
- L-2003-196, Special Report Re Inoperable Loose Parts Monitoring Channel, Per Requirements of Updated Final Safety Analyses Report Section 13.7.4.1 Action a
- L-2004-052, Technical Specification Special Report Regarding Radwaste Building Exhaust System Plant Ventilation Exhaust Monitor - Out-of-Service
- L-2004-291, Technical Specification Special Report on Inoperable Containment Sump Wide Range Level Channel B
- L-2005-096, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - Annual Report and 30-Day Report
- L-2007-100, Technical Specification Special Report, Pressurizer Power Operate Relief Valve (PORV)
- L-2007-166, Technical Specification Special Report, Radiation Monitoring Inoperable Greater than 72 Hours
- L-2009-097, LER for St. Lucie, Unit 2 Regarding Technical Specification Special Report, Radiation Monitor Inoperable Greater than 72 Hours
- L-2009-250, Date of Event: October 6, 2009, Technical Specification Special Report, Sodium Hypochlorite Spill Greater than 100 Pounds
- L-2009-289, Submittal of Technical Specification Special Report Reactor Vessel Level Monitoring System a Channel Level Probe (Hjtc) Out of Service
- L-2010-100, Accident Monitoring Instrumentation Special Report
- L-2010-114, Special Report Re Inoperable Main Steam Lines High Range-Noble Gas Effluent Monitor Greater than 7 Days
- L-2010-139, LER, St. Lucie, Unit 1, Submittal of Technical Specification Special Report, Inoperable Containment Sump Wide Range Level Channel B
- L-2010-235, LER, Turkey Point, Units 3 and 4, Special Report - Accident Monitoring Instrumentation Inoperable
- L-2011-345, Technical Specification Special Report, Radiation Monitor Inoperable Greater than 72 Hours
- L-2013-117, Special Report - Accident Monitoring Instrumentation
- L-2013-184, Special Report - Accident Monitoring Instrumentation
- L-2013-215, Technical Specification Special Report - Failure of Channel a Reactor Vessel Level Monitoring System (Rvlms)
- L-2013-217, Revised Technical Specification Special Report, Failure of Channel a Reactor Vessel Level Monitoring System (Rvlms) on June 4, 2013
- L-2013-291, Submittal of Technical Specification Special Report Radiation Monitor Inoperable Greater than 72 Hours
- L-2014-013, Submittal of Technical Specification Special Report
- L-2014-037, Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report
- L-2014-065, Special Report - Accident Monitoring Instrumentation
- L-2014-077, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report
- L-2014-134, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report
- L-2014-248, Technical Specification Special Report Radiation Monitor Inoperable Greater than 72 Hours
- L-2014-359, 10 CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors, 30 Day Special Report
- L-2016-065, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors, - 30 Day Special Report
- L-2016-124, 10 CFR 50.46 30-Day Report for Turkey Point, Seabrook, and Point Beach
- L-2017-069, Special Report - Containment Tendon Corrosion Protection Medium Volume Reduction
- L-2017-102, Submittal of 10 CFR 50.46 - Emergency Core Cooling 30-Day Report
- L-2017-145, CFR 50.46 30-Day Special Report of Changes in Peak Cladding Temperature
- L-2018-005, Submittal of Emergency Core Cooling 30-Day Report
- L-2018-063, CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications
- L-2019-051, Unusual or Important Environmental Event - Turtle Mortalities - February 4, 2019 and February 11, 2019
- L-2019-058, CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report
- L-76-247, Letter Attaching Reportable Occurrence No. 335-B-76-02 Failure to Determine Condenser Delta T.
- L-MT-05-116, Day Special Report: Failure of Wide Range Radiation Monitor Electronic Process Flow Probe
- L-MT-11-039, Submittal of 10 CFR 50.46 Thirty Day Report
- L-MT-13-090, August 2013, 10 CFR 50.46 Thirty-Day Report
- L-MT-14-054, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
- L-MT-16-050, Thirty-Day Notification for Dry Shielded Canister MNP-61 BTH-1-B-2-016 Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel
- L-PI-05-055, 2005 Unit 2 Steam Generator Category C-3 Inspection Results 30-Day Report
- L-PI-06-103, Steam Generator Category C-3 Inspection Results 30-Day Report
- L-PI-14-006, Technical Evaluation to Support LOCA 10 CFR 50.46 30 Day NRC Submittal
- LIC-07-0037, Fort Calhoun Station Unit 1, Special Report on the Containment Tendon Prestressing System, Free Water Found in Dome Tendons
- LIC-09-0028, Omaha Public Power District - 30-Day Report of a Significant Change/Error in the Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46
- LIC-14-0105, Special Report on Inoperability of Containment Accident Radiation Monitor RM-091B for Post Accident Monitoring
- LIC-14-0115, Special Report on Inoperability of Containment Accident Radiation Monitor RM-091A/B for Post Accident Monitoring
- LIC-15-0059, Small Break Loss-of-Coolant Accident (SBLOCA) I Emergency Core Cooling System (ECCS) Evaluation Model Change/Error - 30-Day Report
- LR-N04-0594, Special Report 04-013-00
- LR-N05-0143, Special Report 05-001-01 Regarding the Cause of Failure and Channel Restoration
- LR-N05-0421, Special Report 354/05-006-00 for Hope Creek Generating Station Re South Plant Vent Radiation Monitoring System Being Inoperable for Greater than 72 Hours
- LR-N06-0405, Special Report 311/06-002 Main Stream Line Discharge Monitors (R46s) Inoperable Greater than Seven (7) Days
- LR-N07-0148, Special Report Regarding Auxiliary Boiler Emission Test Failure
- LR-N08-0053, Submittal of Special Report - North Plant Vent Radiation Monitoring System (Rms)
- LR-N08-0164, Special Report - Safety Relief Valve (SRV) Acoustic Monitor
- LR-N09-0267, Special Report 311/2009-001, One Channel of Reactor Vessel Level Instrumentation System (RVLIS) Inoperable Greater than 30 Days
- LR-N10-0353, Submittal of Report Changes in Application of Emergency Core Cooling System Evaluation Models
- LR-N16-0234, 30-Day, 10 CFR 50.46 Report, ECCS Evaluation Model Change
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