ML15313A025
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| ML15313A025 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/05/2015 |
| From: | Trafton W J Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NMP2L 2599 LER 14-007-01 | |
| Download: ML15313A025 (8) | |
Similar Documents at Nine Mile Point | |
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Category:Letter
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RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01 Category:Licensee Event Report (LER) MONTHYEARML18018B1152018-01-18018 January 2018
[Table view]Scram Summary 91-01 Relating to a Turbine Trip and Automatic Reactor Scram When the Main Transformer Phase B Developed an Internal Fault on August 13, 1991 ML18018B1122018-01-18018 January 2018 Scram Summary 91-01 Relating to an Event on August 13, 1991 Concerning a Turbine Trip and Automatic Reactor Scram When the Main Transformer Phase B Developed an Internal Fault 05000410/LER-2017-0022017-11-28028 November 2017 Secondary Containment Inoperable Due to Wind Conditions, LER 17-002-00 for Nine Mile Point Nuclear Station, Unit 2 Regarding Secondary Containment Inoperable Due to Wind Conditions 05000220/LER-2017-0032017-11-0202 November 2017 Automatic Reactor Scram due to Reactor Vessel Low Water Level, LER 17-003-00 for Nine Mile Point, Unit 1, Regarding Automatic Reactor Scram due to Reactor Vessel Low Water Level 05000410/LER-2017-0012017-10-0404 October 2017 1 OF 5, LER 17-001-00 for Nine Mile Point Nuclear Station, Unit 2, Regarding Automatic Reactor Scram due to High Reactor Pressure 05000220/LER-2017-0022017-05-18018 May 2017 Manual Reactor Scram Due to Pressure Oscillations, LER 17-002-00 for Nine Mile Point Nuclear Station, Unit 1 Regarding Manual Reactor Scram Due to Pressure Oscillations 05000220/LER-2017-0012017-02-0808 February 2017 Manual Reactor Scram Due to Hiah Turbine Vibration, LER 17-01-00 for Nine Mile Point Unit 1 RE: Manual Reactor Scram Due to High Turbine Vibration NMP1L3129, LER 17-01-00 for Nine Mile Point Unit 1 Manual Reactor Scram Due to High Turbine Vibration2017-02-0808 February 2017 LER 17-01-00 for Nine Mile Point Unit 1 Manual Reactor Scram Due to High Turbine Vibration 05000220/LER-2016-0022016-09-26026 September 2016 Isolation of both Emergency Condensers due to loss of UPS 162B, LER 16-002-00 for Nine Mile Point, Unit 1, Regarding Isolation of Both Emergency Condensers due to Loss of UPS 1628 05000220/LER-2016-0012016-07-12012 July 2016 Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors, LER 16-001-00 for Nine Mile Point Nuclear Station Unit 1 Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors 05000410/LER-2016-0012016-06-0606 June 2016 Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors, LER 16-001-00 for Nine Mile Point, Unit 2, Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors 05000410/LER-2015-0032016-03-31031 March 2016 Primary Containment Isolation Function for some valves not maintained during Surveillance Testing, LER 15-003-01 for Nine Mile Point, Unit 2, Regarding Primary Containment Isolation Function For Some Valves Not Maintained During Surveillance Testing ML1005504842010-02-15015 February 2010 Special Report: Inoperable Suppression Chamber Water Level Instrumentation ML0903605172009-01-21021 January 2009 Special Report: Inoperable Channel of Suppression Chamber Water Level Instrumentation ML0534802052005-12-0202 December 2005 Special Report for Nine Mile Point Unit 1 Re Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0515400362005-05-24024 May 2005 Special Report, Channel #11 of the Containment Hydrogen Monitoring Inoperable for Scheduled Preventive Maintenance ML0509602422004-12-17017 December 2004 Final Precursor Analysis - NMP-1 Grid Loop ML0509602522004-12-17017 December 2004 Final Precursor Analysis - NMP-2 Grid Loop ML0434304492004-11-22022 November 2004 Special Report for Nine Mile Point, Unit 1 Regarding Channel #12 of the Containment Hydrogen Monitoring System Removed from Service for Planned Maintenance ML0425300732004-08-27027 August 2004 Special Report for Nine Mile Point Unit 1 Re Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0418105152004-06-18018 June 2004 Revised Special Report for Nine Mile Point, Unit 1 Re Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0413204992004-05-0404 May 2004 Special Report for Nine Mile Point Unit 1 Regarding Inoperability of Channel #12 of the Containment Hydrogen Monitoring System ML0410603992004-04-0707 April 2004 Special Report, Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Corrective Maintenance ML0336404932003-12-19019 December 2003 Special Report Regarding Channel #11 Containment Hydrogen Monitoring System Being Inoperable for Scheduled Preventive Maintenance ML0221303572002-07-23023 July 2002 Special Report for Nine Mile Point Unit 2 Re Noble Gas Activity Monitoring Instrumentation Inoperable for Greater than 72 Hours ML18018B1112000-03-0707 March 2000 LER 99-019-01 Supplement 1, for Nine Mile Point, Unit 2, Regarding Two Standby Liquid Control Valves Not Tested as Required by Technical Specification 4.0.5 and LER 99-010-01, Supplement 1, Unit 2 Reactor Trip Due to a Feedwater Master .. ML18018B0771997-12-29029 December 1997 Letter Replying to Notice of Violation as Contained in NRC Inspection Report 50-220/97-07 and 50-410/97-07 ML18018B1171991-09-0404 September 1991 NRC UPS Meeting ML18018B2511978-09-29029 September 1978 LER 78-034-00 for Nine Mile Point, Unit 2, Regarding an Environmental Contractor Obtaining 22 Hourly Fish Impingement Samples, and One Two-Hour Sample, Which Is Contrary to the Technical Specification Requiring 24 Hourly Samples ML18018B2521978-08-24024 August 1978 LER 78-030-00, 78-031-00, and 78-032-00 for Nine Mile Point Unit 1 Regarding, Respectively, Unavailability of Feedwater Pump 29-03 While Its Pump Seals Were Replaced, Unavailability of Liquid Poison Pump NP02A While a Frozen Valve .. ML18018B2531978-07-28028 July 1978 LER 78-029-00 for Nine Mile Point, Unit 2, Regarding Discovery of High Drywell Pressure Switches RE04A, RE04B, and RE04C with Setpoints Less Conservative than the Technical Specifications ML18018B2541978-07-25025 July 1978 LER 78-028-00 for Nine Mile Point Unit 1 Regarding Discovery of the Allowable Test Interval of TS 4.1.4c for the Core Spray Power-Operated Valves Had Been Exceeded ML18018B2551978-07-13013 July 1978 LERs 78-025-00, 78-026-00, and 78-027-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery of RE04D with a Setpoint of 3.70 PSIG, Discovery of Numerous Small Leaks in Small Sample and Instrument Pipes, and Discovery of RE22D wit ML18018B2561978-06-21021 June 1978 LER 78-024-00 for Nine Mile Point Unit 1 Regarding Discovery That Test N1-St-Q2,4,5,7,8,9, and 10 Had Not Been Performed During a Review of Quarterly Surveillance Test Results ML18018B2571978-06-12012 June 1978 LERs 78-020-00, 78-021-00, 78-022-00, and 78-023-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery of RE18A with a Setpoint of 135 Inches Wc, Discovery of RE04A and RE04B with a Setpoint of 3.65 PSIG, Discovery of Turbine ... ML18018B2591978-06-0101 June 1978 LER 78-019-00 for Nine Mile Point Unit 1 Regarding Discovery That Hydraulic Snubber 31-HS-1 Had Failed and Was Empty of Hydraulic Fluid and Disconnected from Its Anchor at the Feedwater Pipe ML18018B2581978-05-26026 May 1978 LER 78-009-01 for Nine Mile Point Unit 1 Regarding Replacement of Explosive Charges in the TIP Shear Valves with New Charges and the Resulting Unsatisfactory Ohmmeter Continuity Test for Acceptable Electric Contact ML18018B2601978-04-24024 April 1978 LER 78-018-00 for Nine Mile Point Unit 1 Regarding Discovery of Main Steam High Flow Switch with a Setpoint of 106.2 PSI, Which Is Above the Technical Specification ML18018B2611978-04-0707 April 1978 LERs 78-014,00, 78-016-00, and 78-016-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery That the Fuel Transfer Pump on 102 D/G Would Not Fill the Day Tank, Discovery of RE18C with a Setpoint of 129 Inches Wc, and RE04B .. ML18018B2621978-03-28028 March 1978 LER 78-014-00 and LER 78-015-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery That the Fuel Transfer Pump in 102 D/G Would Not Fill the Day Tank and Discovery That #12 Control Room Air Treatment Fan Would Not Run ML18018B2631978-03-16016 March 1978 LER 78-011-00, LER 78-012-00 and LER 78-013-00 for Nine Mile Point, Unit 1 Re Technical Specification Violations of Section 3.6.2 ML18018B2641978-03-0101 March 1978 LER 78-007-00, LER 78-008-00, LER 78-009-00 and LER 78-010-00 for Nine Mile Point, Unit 1 Re Technical Specification Violations of Listed Sections ML18018B2651978-02-24024 February 1978 LER 78-006-00 for Nine Mile Point, Unit 1 Re During Steady State Operation, Performance of Surveillance Test IC-75 Found a Trip Setpoint of 22.5 Inches Water on One Vacuum Switch in the Vacuum Relief System from the Pressure Suppression Cha ML18018B2661978-02-0707 February 1978 LER 78-004-00 and LER 78-005-00 for Nine Mile Point, Unit 1 Re During Unit Shutdown, Reserve Power Breaker on Power Board II Failed to Close in After Loss of Normal Power and During Plant Outage While Marking Up Outside MSIV 01-03 Discovere ML18094A0301978-01-31031 January 1978 LER 1978-003-03 for Nine Mile Point Unit 1 Re Surveillance Test Found Main Steam High Flow Switch with Setpoint of 107.5 PSI ML18018B1221978-01-31031 January 1978 LER 78-002-00 for Nine Mile Point 1 Regarding Drywell High Pressure Switch RE04A Setpoint Drift and LER 78-003-00 ML18018B2701978-01-13013 January 1978 Submittal of Licensee Event Report LER 78-01 Concerning Delta Temperature of the Discharge Water Exceeded Environmental Tech. Spec ML18094A0291978-01-13013 January 1978 LER 1978-001-00 for Nine Mile Point Station Unit 1 Re Delta Temperature of Discharge Water Exceeded Specification 2.1.5 of Environmental Tech Specs ML18018B1361977-07-21021 July 1977 LER 77-032-00 for Nine Mile Point Unit 1 Regarding a Water Phase Material Sample in the Reactor Vessel Inspection Lapse During Refueling ML18018B1421977-07-14014 July 1977 LER 77-029-00, 77-030-00, 77-031-00, 77-034-00, & 77-035-00 for Nine Mile Point Unit 1 Low-Low-Low Level Set Point Out of Specs on RE-18A, Vacuum Switch Trip & Reset Point on Torus Relief Valves Out of Specs, Weld Leak in Emergency Condense 2018-01-18 |
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