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Category:Licensee Event Report (LER)
MONTHYEAR05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure2024-08-27027 August 2024 Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure 05000263/LER-2024-001, Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component2024-04-25025 April 2024 Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component 05000263/LER-2023-003, Condition Prohibited by Technical Specifications Due to Inoperable Main Steam Line Low Pressure Isolation Switch2023-12-0404 December 2023 Condition Prohibited by Technical Specifications Due to Inoperable Main Steam Line Low Pressure Isolation Switch 05000263/LER-2023-002, Reactor Scram and Containment Isolation Due to Valve Responses During Main Turbine Control Valve Testing2023-11-13013 November 2023 Reactor Scram and Containment Isolation Due to Valve Responses During Main Turbine Control Valve Testing 05000263/LER-2023-001, Main Steam Isolation Valve Leakage Exceeds Technical Specification Requirements Due to Stem Scoring2023-05-17017 May 2023 Main Steam Isolation Valve Leakage Exceeds Technical Specification Requirements Due to Stem Scoring 05000263/LER-2022-001, Loss of Control Room Envelope Operability2022-07-0707 July 2022 Loss of Control Room Envelope Operability 05000263/LER-2017-0062018-01-12012 January 2018 Loss of Reactor Protection System Scram Function During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests due to Use of a Test Fixture, LER 17-006-00 for Monticello Regarding Loss of Reactor Protection System Scram Function During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Fixture 05000263/LER-2017-0052017-09-20020 September 2017 Diesel Generator Emergency Service Water System Automatic Transfer to Alternate Shutdown Panel, LER 17-005-00 for Monticello Nuclear Generating Plant Regarding Diesel Generator Emergency Service Water System Automatic Transfer to Alternate Shutdown Panel 05000263/LER-2015-0042017-08-22022 August 2017 Past Inoperability of Turbine Stop Valve Scram Function Exceeded Technical Specification Requirements, LER 15-004-01 for Monticello Regarding Past Inoperability of Turbine Stop Valve Scram Function Exceeded Technical Specification Requirements 05000263/LER-2017-0042017-08-16016 August 2017 High Pressure Coolant Injection Steam Stop Valve Failed to Open During Test, LER 17-004-00 for Monticello Regarding High Pressure Coolant Injection Steam Stop Valve Failed to Open During Test 05000263/LER-2017-0032017-06-14014 June 2017 Main Steam Isolation Valve Leakage Exceeds Technical Specification Limits, LER 17-003-00 for Monticello Regarding Main Steam Isolation Valve Leakage Exceeds Technical Specification Limits 05000263/LER-2017-0022017-06-13013 June 2017 Main Steam Isolation Valve Closure Time Outside of Technical Specification Requirements, LER 17-002-00 for Monticello Nuclear Generating Plant Regarding Main Steam Isolation Valve Closure Time Outside of Technical Specification Requirements 05000263/LER-2017-0012017-06-13013 June 2017 Reactor Scram and Group II Isolation Due to 11 Reactor Feed Pump (RFP) Removal from Service with 12 RFP Isolated, LER 17-001-00 for Monticello Regarding Reactor Scram and Group II Isolation Due to 11 Reactor Feed Pump (RFP) Removal from Service with 12 RFP Isolated 05000263/LER-2016-0012017-05-25025 May 2017 High Pressure Coolant Injection System Cracked Pipe Nipple Caused Oil Leak, LER 16-001-02 for Monticello Regarding High Pressure Coolant Injection System Cracked Pipe Nipple Caused Oil Leak 05000263/LER-2016-0032017-05-25025 May 2017 HPCI Declared Inoperable Due to Excessive Water Level in Turbine, LER 16-003-01 for Monticello Regarding HPCI Declared Inoperable Due to Excessive Water Level in Turbine 05000263/LER-2016-0022016-09-30030 September 2016 Inadequate Appendix R Fire Barrier Impacts Safe Shutdown Capability, LER 16-002-00 for Monticello Regarding Inadequate Appendix R Fire Barrier Impacts Safe Shutdown Capability 05000263/LER-2014-0022016-07-13013 July 2016 Torus to Drywell Vacuum Breaker Did Not Indicate Closed During Testing, LER 14-002-01 for Monticello Regarding Torus to Drywell Vacuum Breaker Did Not Indicate Closed During Testing 05000263/LER-2014-0032016-07-13013 July 2016 Torus to Drywell Vacuum Breaker Dual Indication During Testing, LER 14-003-01 for Monticello Nuclear Generating Plant RE: Torus to Drywell Vacuum Breaker Dual Indication During Testing 05000263/LER-2015-0072016-01-21021 January 2016 Loss of Residual Heat Removal Capability, LER 15-007-00 for Monticello Regarding Loss of Residual Heat Removal Capability 05000263/LER-2015-0062016-01-21021 January 2016 - Reactor Scram due to Group 1 Isolation from Foreign Material in the Main Steam Flow Instrument Line, LER 15-006-00 for Monticello Regarding Reactor Scram due to Group 1 Isolation from Foreign Material in the Main Steam Flow Instrument Line ML1015505712009-09-12012 September 2009 Event Notification for Monticello on State Offsite Notification Due to Not Meeting Permit Requirements L-MT-05-035, LER 50-004-00 for Monticello Nuclear Generating Plant Regarding Voluntary LER for Control Rod Drive Insert Line Leakage2005-05-12012 May 2005 LER 50-004-00 for Monticello Nuclear Generating Plant Regarding Voluntary LER for Control Rod Drive Insert Line Leakage ML0216100952002-05-15015 May 2002 LERs 02-001-01 & 02-002-01 for Monticello Nuclear Generating Plant Re Mechanical Pressure Regulator Failure Causes Reactor Scram & Application of Instrument Deviation Acceptance Criteria Allowed As-Found Settings to Be Outside Tech Spec Val 2024-08-27
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Power Reactor lEvent Number: 45338 Facility: MONTICELLO Notification Date: 09/10/2009 Region: 3 State: MN Notification Time: 13:06 [ET]
Unit: [1] [ ] [ ] Event Date: 09/10/2009 RX Type: [1] GE-3 Event Time: 09:13 [CDT]
NRC Notified By: WILLIAM STANG Last Update Date: 09/12/2009 HQ OPS Officer: VINCE KLCO Emergency Class: NON EMERGENCY Person (Organization):
10 CFR Section: MARK RING (R3DO) 50.72(b)(2)(xi) - OFFSITE NOTIFICATION SCRAM Initial Current Unit Code RX CRIT PWR Initial RX Mode PWR Current RX Mode 1 N I Y T 1001 Power Operation 1001 Power Operation Event Text STATE OFFSITE NOTIFICATION DUE TO NOT MEETING PERMIT REQUIREMENTS "The Minnesota State Pollution Control Agency and State Department of Emergency Management were notified today, September 10, 2009, that Monticello did not meet the National Pollutant Discharge Elimination System (NPDES) .Permit.
"Samples from a new monitoring well near the reactor building showed low levels of tritium greater than normal background but below Environmental Protection Agency drinking water standards. The concentration of tritium is below any radiological reporting levels established in station procedures.
No elevated levels have been detected in any of the other permanent plant monitoring wells.
Therefore, we have no indications that there has been a release of tritium beyond the site from this source. The station will continue to monitor, sample and investigate the source of the tritium."
The licensee notified the NRC Resident Inspector.
- UPDATE FROM B. CALLSTROM TO V. KLCO AT 1201 ON 9/12/2009 ***
"A subsequent water sample from a new monitoring well near the reactor building indicated a level of 21,300 picocuries/liter of tritium which is slightly above the Environmental Protection Agency drinking water standard for tritium of 20,000 picocuries/liter. No elevated levels have been detected in any of the other permanent plant monitoring wells. Therefore, [the licensee has] no indication that there has been a release of tritium beyond the site from this source. The station will continue to monitor, sample and investigate the source of the tritium.
"This poses no immediate safety concern for plant employees or the general public."
The licensee notified the NRC Resident Inspector.
Notified the R3DO (Ring).