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Category:Licensee Event Report (LER)
MONTHYEAR05000423/LER-2024-002, Door Latch Failure Resulted in Loss of Safety Function for Secondary Containment Boundary2024-11-26026 November 2024 Door Latch Failure Resulted in Loss of Safety Function for Secondary Containment Boundary 05000336/LER-2024-002, Two Main Steam Safety Valves Failed to Lift within the Acceptance Criteria Resulting in a Condition Prohibited by Technical Specifications2024-11-26026 November 2024 Two Main Steam Safety Valves Failed to Lift within the Acceptance Criteria Resulting in a Condition Prohibited by Technical Specifications 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications 05000423/LER-2023-005, Oil Leakage from C RSS Pump Motor Challenged Meeting Its Mission Time Resulting in a Condition Prohibited by Technical Specifications2024-02-0808 February 2024 Oil Leakage from C RSS Pump Motor Challenged Meeting Its Mission Time Resulting in a Condition Prohibited by Technical Specifications 05000423/LER-2023-004, For Millstone Power Station, Unit 3 Regarding Reactor Coolant System Pressure Isolation Valves Operational Leakage Exceeded the Acceptance Criteria Resulting in a Condition Prohibited by Technical Specifications2023-12-19019 December 2023 For Millstone Power Station, Unit 3 Regarding Reactor Coolant System Pressure Isolation Valves Operational Leakage Exceeded the Acceptance Criteria Resulting in a Condition Prohibited by Technical Specifications 05000423/LER-2023-003, RCS Temperature Detector Exceeded Time Response Acceptance Criteria Resulting in a Condition Prohibited by Technical Specifications2023-12-0808 December 2023 RCS Temperature Detector Exceeded Time Response Acceptance Criteria Resulting in a Condition Prohibited by Technical Specifications 05000423/LER-2023-002, Auxiliary Feedwater Control Valve Failure Resulting in a Condition Prohibited by Technical Specifications2023-11-30030 November 2023 Auxiliary Feedwater Control Valve Failure Resulting in a Condition Prohibited by Technical Specifications 05000336/LER-2023-002, Failed Check Valve Resulted in an Unanalyzed Condition2023-08-31031 August 2023 Failed Check Valve Resulted in an Unanalyzed Condition 05000423/LER-2023-001, Automatic Reactor Trip Due to Main Generator Output Breaker Ground Fault2023-07-27027 July 2023 Automatic Reactor Trip Due to Main Generator Output Breaker Ground Fault 05000336/LER-2023-001, For Millstone, Unit 2, Structural Integrity of a Train Service Water Header Piping Could Not Be Demonstrated Causing the Unit to Operate in a Condition Prohibited by Technical Specifications2023-07-0707 July 2023 For Millstone, Unit 2, Structural Integrity of a Train Service Water Header Piping Could Not Be Demonstrated Causing the Unit to Operate in a Condition Prohibited by Technical Specifications 05000423/LER-2022-002, Two Main Steam Safety Valves Installed in Wring Location Resulting in Failure to Lift within the Technical Specification Acceptance Criteria2022-05-31031 May 2022 Two Main Steam Safety Valves Installed in Wring Location Resulting in Failure to Lift within the Technical Specification Acceptance Criteria 05000423/LER-2022-001, Emergency Core Cooling and Reactor Plant Component Cooling Water Systems Inoperable for Time Greater than Allowed by Technical Specifications2022-03-24024 March 2022 Emergency Core Cooling and Reactor Plant Component Cooling Water Systems Inoperable for Time Greater than Allowed by Technical Specifications 05000336/LER-2022-001, Structural Integrity of Reactor Building Component Cooling Water Cracked Threaded Fitting Could Not Be Established Resulting in System Inoperable Longer than Allowed by Technical Specifications2022-03-18018 March 2022 Structural Integrity of Reactor Building Component Cooling Water Cracked Threaded Fitting Could Not Be Established Resulting in System Inoperable Longer than Allowed by Technical Specifications 05000336/LER-2021-002, Failed Check Valve Resulting in Unnalyzed and Operation Prohibited by Technical Specifications2022-01-0505 January 2022 Failed Check Valve Resulting in Unnalyzed and Operation Prohibited by Technical Specifications 05000336/LER-2021-001, Incorrectly Placed Spent Fuel Assemblies in Unit 2 Spent Fuel Pool2021-09-23023 September 2021 Incorrectly Placed Spent Fuel Assemblies in Unit 2 Spent Fuel Pool 05000423/LER-2020-005, Loss of Safety Function - Secondary Containment2020-11-19019 November 2020 Loss of Safety Function - Secondary Containment 05000423/LER-2020-002, 3, Automatic Reactor Trip Due to Main Generator Ground Fault2020-05-28028 May 2020 3, Automatic Reactor Trip Due to Main Generator Ground Fault 05000423/LER-2020-001, Technical Specification Allowed Outage Time Exceeded by Accident Monitoring Instrument2020-03-0505 March 2020 Technical Specification Allowed Outage Time Exceeded by Accident Monitoring Instrument 05000336/LER-2019-001, Manual Reactor Trip Due to Loss of the a Steam Generator Feed Pump2020-02-19019 February 2020 Manual Reactor Trip Due to Loss of the a Steam Generator Feed Pump 05000423/LER-2019-001, Regarding Plant Shutdown Required by Technical Specifications, Emergency Diesel Generator Exceeded Allowed Outage Time2020-02-13013 February 2020 Regarding Plant Shutdown Required by Technical Specifications, Emergency Diesel Generator Exceeded Allowed Outage Time 05000336/LER-2018-001, Regarding Loss of Both Trains of Control Room Emergency Ventilation Resulting in the Loss of Safety Function2018-12-19019 December 2018 Regarding Loss of Both Trains of Control Room Emergency Ventilation Resulting in the Loss of Safety Function 05000423/LER-2017-001, Regarding Loss of Safety Function - Secondary Containment2017-03-20020 March 2017 Regarding Loss of Safety Function - Secondary Containment 05000336/LER-2016-002, Regarding Manual Reactor Trip Due Loss of Two Circulating Water Pumps2016-09-20020 September 2016 Regarding Manual Reactor Trip Due Loss of Two Circulating Water Pumps 05000423/LER-2016-005, Technical Specification Required Shutdown and Manual Reactor Trip Due to Steam Generator Level Oscillation2016-08-0909 August 2016 Technical Specification Required Shutdown and Manual Reactor Trip Due to Steam Generator Level Oscillation 05000423/LER-2016-004, Manual Reactor Trip Due to Low Hydrogen Gas Pressure in Main Generator2016-07-13013 July 2016 Manual Reactor Trip Due to Low Hydrogen Gas Pressure in Main Generator 05000336/LER-2016-001, Turbine Driven Auxiliary Feedwater Pump Room HELB Door Left Open2016-06-27027 June 2016 Turbine Driven Auxiliary Feedwater Pump Room HELB Door Left Open 05000423/LER-2016-003, Regarding Loss of Safety Function-Supplementary Leak Collection and Release System2016-06-0808 June 2016 Regarding Loss of Safety Function-Supplementary Leak Collection and Release System 05000423/LER-2016-002, Regarding Feedwater Isolation Signal Defeated Due to Wiring Error2016-03-23023 March 2016 Regarding Feedwater Isolation Signal Defeated Due to Wiring Error 05000423/LER-2016-001, Regarding Automatic Reactor Trip on Reactor Coolant System Low Flow Due to Loss of B Reactor Coolant Pump2016-03-16016 March 2016 Regarding Automatic Reactor Trip on Reactor Coolant System Low Flow Due to Loss of B Reactor Coolant Pump 05000336/LER-2015-003, Regarding Valid Actuation of the Reactor Protection System2016-01-0707 January 2016 Regarding Valid Actuation of the Reactor Protection System 05000336/LER-2015-002, Regarding Degraded Emergency Core Cooling System Check Valve2015-08-10010 August 2015 Regarding Degraded Emergency Core Cooling System Check Valve 05000336/LER-2015-001, Regarding Historical Oil Leakage from C RBCCW Pump Bearings Challenged Meeting Mission Time2015-06-16016 June 2015 Regarding Historical Oil Leakage from C RBCCW Pump Bearings Challenged Meeting Mission Time 05000423/LER-2015-001, Regarding Unlatched Dual Train HELB Door Results in Potential Loss of Safety Function2015-04-20020 April 2015 Regarding Unlatched Dual Train HELB Door Results in Potential Loss of Safety Function 05000423/LER-2014-004, Regarding Unlatched Dual Train HELB Door Results in Potential Loss of Safety Function2015-02-0909 February 2015 Regarding Unlatched Dual Train HELB Door Results in Potential Loss of Safety Function 05000336/LER-2014-007, Regarding Completion of Plant Shutdown Required by Technical Specifications2014-09-24024 September 2014 Regarding Completion of Plant Shutdown Required by Technical Specifications 05000336/LER-2014-006, Regarding Millstone Power Station Dual Unit Reactor Trip on Loss of Offsite Power2014-07-24024 July 2014 Regarding Millstone Power Station Dual Unit Reactor Trip on Loss of Offsite Power 05000336/LER-2014-005, Regarding Train a Containment Spray Inoperable Due to Gas Voids2014-07-16016 July 2014 Regarding Train a Containment Spray Inoperable Due to Gas Voids 05000423/LER-2014-003, Regarding Turbine Driven Auxiliary Feedwater Pump Operability Impacted by Incorrect Bearing2014-06-30030 June 2014 Regarding Turbine Driven Auxiliary Feedwater Pump Operability Impacted by Incorrect Bearing 05000336/LER-2014-004, Regarding Foreign Material Found in a Motor Lead Rendered a Motor Driven Auxiliary Feedwater Pump Inoperable2014-06-0909 June 2014 Regarding Foreign Material Found in a Motor Lead Rendered a Motor Driven Auxiliary Feedwater Pump Inoperable 05000336/LER-2014-003, Regarding Loss of Safety Function Due to Inoperable Enclosure Building2014-06-0202 June 2014 Regarding Loss of Safety Function Due to Inoperable Enclosure Building 05000336/LER-2014-002, 2 Regarding DC Circuit Hot Shorts2014-05-0505 May 2014 2 Regarding DC Circuit Hot Shorts 05000423/LER-2014-002, Regarding DC Circuit Hot Shorts2014-05-0505 May 2014 Regarding DC Circuit Hot Shorts 05000336/LER-2014-001, Regarding Completion of Plant Shutdown Required by Technical Specifications2014-03-31031 March 2014 Regarding Completion of Plant Shutdown Required by Technical Specifications 05000423/LER-2014-001, Limiting Condition for Operation Exceeded Upon Approval of Enforcement Discretion2014-03-17017 March 2014 Limiting Condition for Operation Exceeded Upon Approval of Enforcement Discretion 05000423/LER-2013-009, Regarding Secondary Containment Boundary Breach Could Have Prevented Safety Function2014-01-15015 January 2014 Regarding Secondary Containment Boundary Breach Could Have Prevented Safety Function 05000336/LER-2013-004, Unit 2 Regarding Reactor Trip While Backwashing D Waterbox2013-12-19019 December 2013 Unit 2 Regarding Reactor Trip While Backwashing D Waterbox 2024-09-26
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Dominion Nuclear Connecticut, Inc.
Dominion N Iill kunc lP )owIr Station RosC I'Cri-- l(otd
\\X'Wjcrtird, (7I 06385 MAR I 4 2002 Docket No. 50-423 B18593 RE: 10 CFR 50.73(a)(2)(i)(B)
U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 3 Licensee Event Report 2002-001-00 Control Room Emergency Ventilation System Surveillance Failure This letter forwards Licensee Event Report (LER) 2002-001-00, documenting an event that was discovered at Millstone Nuclear Power
- Station, Unit No.
3, on January 25, 2002. This LER is being submitted to document a condition determined to be reportable in accordance with 10 CFR 50.73(a)(2)(i)(B).
There are no regulatory commitments contained within this letter.
Should you have any questions regarding this submittal, please contact Mr. David W. Dodson at (860) 447-1791, extension 2346.
Very truly yours, DOMINION NUCLEAR CONNECTICUT, INC.
GS ~lI)`warz<,Sgor Nuclear Station Operations and Maintenance Attachment (1):
LER 2002-001-00 cc:
H. J. Miller, Region I Administrator V. Nerses, NRC Senior Project Manager, Millstone Unit No. 3 NRC Senior Resident Inspector, Millstone Unit No. 3
Docket No. 50-423 B18593 Millstone Nuclear Power Station, Unit No. 3 LER 2002-001-00
NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY 0MB NO. 3150-0104 EXPIRES 7-31-2004
, the NRC may not conduct or sponsor, (See reverse for required number of digits/characters for each block) and a person is not required to respond to, the information collection.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Millstone Nuclear Power Station - Unit 3 05000423 1 OF 3
TITLE (4)
Control Room Emergency Ventilation System Surveillance Failure EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
MO DAY YEAR YEAR SEQUENTIAL REV MO DAY YEAR FACILITY NAME lOCKET NUMBER NUMBER NO. L 05000 01 25 2002 2002 -
001 - 00 03 14 2002 FACILITY NAME l DOCKET NUMBER 05000 OPERATING 1
THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR 5: (Check all that apply) (11)
MODE (9) 20.2201 (b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER 100 20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL (10) 20.2203(a)(1) 50.36(c)(1 )(i)(A) 50.73(a)(2)(iv)(A) 73.71 (a)(4) 20.2203(a)(2)(i) 50.36(c)(1 )(ii)(A)
=
50.73(a)(2)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)
OTHER 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
Specify in Abstract below or 20.2203(a)(2)(iv) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) in (If rmore space is required, use additional copies of NRC Foln 366A) (17)
V. Previous Occurrences
No previous similar events/conditions were identified.
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
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05000336/LER-2002-001, Two Reactor Coolant System Pressure Boundary Leakage Events on 02/19/2002 and 02/22/202 | Two Reactor Coolant System Pressure Boundary Leakage Events on 02/19/2002 and 02/22/202 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | 05000423/LER-2002-001, Re Control Room Emergency Ventilation System Surveillance Failure | Re Control Room Emergency Ventilation System Surveillance Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | 05000423/LER-2002-002, Breaker Mechanism Failure Results in Inoperable Emergency Diesel Generator | Breaker Mechanism Failure Results in Inoperable Emergency Diesel Generator | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | 05000336/LER-2002-003, Failure to Comply with Technical Specification Action Statement for One Diesel Generator Inoperable | Failure to Comply with Technical Specification Action Statement for One Diesel Generator Inoperable | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | 05000423/LER-2002-003-01, From Millstone Power Station Unit 3 Regarding Inadequate Validation of Fire Safe Shutdown Analysis Assumptions | From Millstone Power Station Unit 3 Regarding Inadequate Validation of Fire Safe Shutdown Analysis Assumptions | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) | 05000336/LER-2002-004, Unit 2 Regarding Reactor Shutdown Due to Entry Into TS 3.0.3 | Unit 2 Regarding Reactor Shutdown Due to Entry Into TS 3.0.3 | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) | 05000336/LER-2002-005, Automatic Reactor Trip Due to Low Steam Generator Level During Power Ascension | Automatic Reactor Trip Due to Low Steam Generator Level During Power Ascension | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System |
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