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Category:Letter
MONTHYEAR05000237/LER-2024-001, Containment Cooling Service Water Valve Failure Resulted in a Condition Prohibited by Technical Specifications and Loss of Safety Function2025-01-27027 January 2025 Containment Cooling Service Water Valve Failure Resulted in a Condition Prohibited by Technical Specifications and Loss of Safety Function ML24351A1452025-01-23023 January 2025 Request to Replace Previously Submitted Documents and Withhold Information from Public Disclosure 05000249/LER-2024-002, Low Pressure Coolant Injection Pump Suction Relief Valve Inoperable as a Primary Containment Isolated Valve Resulted in a Condition Prohibited by Technical Specifications2025-01-21021 January 2025 Low Pressure Coolant Injection Pump Suction Relief Valve Inoperable as a Primary Containment Isolated Valve Resulted in a Condition Prohibited by Technical Specifications ML25017A2302025-01-17017 January 2025 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Dresden Nuclear Power Station, Units 2 & 3 ML24353A1372025-01-15015 January 2025 Proprietary Determination Constellation Energy Generation, LLC 2024 Deferred Premiums IR 05000010/20240012024-12-31031 December 2024 NRC Inspection Report No. 05000010/2024001 ML24344A2742024-12-19019 December 2024 Alternative Request to Use American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case OMN-32 RS-24-135, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-12-18018 December 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24352A2072024-12-17017 December 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24331A2592024-11-27027 November 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III ML24324A3202024-11-19019 November 2024 Letter from R. Mangum, Achp Regarding DNPS Subsequent License Renewal Environmental Review ML24323A0792024-11-15015 November 2024 Transmittal of Dresden, Units 2 and 3, Core Operating Limits Report Cycle 29 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums ML24303A0712024-11-0404 November 2024 Letter to K. Meshigaud, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1342024-11-0101 November 2024 Letter to T. Carnes, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0692024-11-0101 November 2024 Letter to J.A. Crawford, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0202024-11-0101 November 2024 Letter to C. Chavers, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1442024-11-0101 November 2024 Letter to V. Kitcheyna, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0132024-11-0101 November 2024 Letter to B. Barnes, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0642024-11-0101 November 2024 Letter to J. Rupnick, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1172024-11-0101 November 2024 Letter to R. Yob, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0272024-11-0101 November 2024 Letter to D. Rios, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0512024-11-0101 November 2024 Letter to J. Barrett, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1422024-11-0101 November 2024 Letter to V. Jefferson, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0472024-11-0101 November 2024 Letter to G. Cheatham, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0602024-11-0101 November 2024 Letter to J. R. Shotton, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0552024-11-0101 November 2024 Letter to J. Keys, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0492024-11-0101 November 2024 Letter G. Kakkak, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0992024-11-0101 November 2024 Lett to R. Carter, Principal Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1352024-11-0101 November 2024 Letter to T. Rhodd, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station RS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision IR 05000237/20254012024-11-0101 November 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000237/2025401 05000249/2025401 ML24291A0252024-11-0101 November 2024 Letter to R. Blanchard Tribal Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0892024-11-0101 November 2024 Letter to M. J. Wesaw, Chair Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0152024-11-0101 November 2024 Letter to C. Harper, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1462024-11-0101 November 2024 Letter to W. Gravelle, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0172024-11-0101 November 2024 Letter to B. Peters, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0432024-11-0101 November 2024 Letter to E. Elizondo, Sr. Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1102024-11-0101 November 2024 Letter to R. Gasco, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0532024-11-0101 November 2024 Letter to J. Greendeer, President Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0302024-11-0101 November 2024 Letter to D.G. Lankford, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0242024-11-0101 November 2024 Letter to D. Kaskaske, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24291A0202024-10-31031 October 2024 NRC Letter to J. Loichinger Achp Request for Comments Concerning the Environmental Review of DNPS Units 2 and 3 Subsequent License Renewal Application RS-24-126, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4)2024-10-31031 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4) ML24291A0272024-10-31031 October 2024 NRC Letter to C. Mayer Illinois SHPO Request to Initiate Section 106 Consultation for Subsequent License Renewal of Units 2 and 3 IR 05000237/20240032024-10-29029 October 2024 Integrated Inspection Report 05000237/2024003 and 05000249/2024003 RS-24-103, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-10-21021 October 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-102, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-5912024-10-21021 October 2024 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-591 RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests 2025-01-27
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000237/LER-2024-001, Containment Cooling Service Water Valve Failure Resulted in a Condition Prohibited by Technical Specifications and Loss of Safety Function2025-01-27027 January 2025 Containment Cooling Service Water Valve Failure Resulted in a Condition Prohibited by Technical Specifications and Loss of Safety Function 05000249/LER-2024-002, Low Pressure Coolant Injection Pump Suction Relief Valve Inoperable as a Primary Containment Isolated Valve Resulted in a Condition Prohibited by Technical Specifications2025-01-21021 January 2025 Low Pressure Coolant Injection Pump Suction Relief Valve Inoperable as a Primary Containment Isolated Valve Resulted in a Condition Prohibited by Technical Specifications 05000237/LER-2023-001, HPCI Inoperable Due to Air Void Accumulation2024-01-19019 January 2024 HPCI Inoperable Due to Air Void Accumulation 05000237/LER-2022-002-01, Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation2022-10-28028 October 2022 Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation 05000237/LER-2022-001-01, Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure2022-10-28028 October 2022 Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure 05000237/LER-2022-002, Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation2022-09-27027 September 2022 Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation 05000237/LER-2022-001, Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure2022-09-0909 September 2022 Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure 05000249/LER-2021-001-01, Reactor Scram Due to Main Power Transformer Failure2022-06-14014 June 2022 Reactor Scram Due to Main Power Transformer Failure ML20135G7442020-05-14014 May 2020 Final ASP Analysis - Dresden 2 (LER 237-90-006) 05000249/LER-2019-001, Degraded Differential Pressure Indicating Switch in the LPCI Loop Select Logic Caused by Water Damage Results in a Condition Prohibited by Technical Specifications2019-11-19019 November 2019 Degraded Differential Pressure Indicating Switch in the LPCI Loop Select Logic Caused by Water Damage Results in a Condition Prohibited by Technical Specifications 05000237/LER-2019-002, Scram Due to Main Turbine Low Oil Pressure Trip2019-07-0202 July 2019 Scram Due to Main Turbine Low Oil Pressure Trip 05000237/LER-2019-001, Secondary Containment Differential Pressure Exceeded Technical Specification Due to Excess Ventilation Supply Flow2019-03-29029 March 2019 Secondary Containment Differential Pressure Exceeded Technical Specification Due to Excess Ventilation Supply Flow 05000237/LER-2017-002-01, Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage2018-02-15015 February 2018 Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage 05000237/LER-1917-002, Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage Limits2018-01-0202 January 2018 Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage Limits 05000249/LER-1917-001, Regarding Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak2017-11-10010 November 2017 Regarding Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak 05000237/LER-1977-050, /03L-0 for Dresden, Unit 2 Re Local Leak Rate Test of Drywell Personnel Air Lock During Refueling2017-11-0303 November 2017 /03L-0 for Dresden, Unit 2 Re Local Leak Rate Test of Drywell Personnel Air Lock During Refueling 05000249/LER-1977-040, /03L-0 for Dresden 3 Regarding the Circuit Breaker for Service Water Makeup Valve MO-3-4102 to the Isolation Condenser Found in Off Position2017-10-21021 October 2017 /03L-0 for Dresden 3 Regarding the Circuit Breaker for Service Water Makeup Valve MO-3-4102 to the Isolation Condenser Found in Off Position 05000237/LER-1978-028, /01X-1 for Dresden, Units 2 and 3 Re NRC Request for Immediate Actions to Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suct2017-08-28028 August 2017 /01X-1 for Dresden, Units 2 and 3 Re NRC Request for Immediate Actions to Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suction Valves 05000237/LER-1916-003, Cancellation of Licensee Event Report 237/2016-003-00, Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria2017-05-26026 May 2017 Cancellation of Licensee Event Report 237/2016-003-00, Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria 05000237/LER-2016-004, Regarding Reactor Building Differential Pressure Less than Technical Specification Requirement2017-01-0909 January 2017 Regarding Reactor Building Differential Pressure Less than Technical Specification Requirement 05000237/LER-2016-003, Regarding Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria2016-11-18018 November 2016 Regarding Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria 05000249/LER-2016-001, Regarding Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire2016-08-25025 August 2016 Regarding Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire 05000237/LER-2016-002, Regarding HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability2016-07-15015 July 2016 Regarding HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability 05000237/LER-2016-001, Regarding Secondary Containment Differential Pressure Transient2016-04-0808 April 2016 Regarding Secondary Containment Differential Pressure Transient 05000237/LER-2015-005-02, Regarding Unit 2 HPCI Motor Gear Unit Would Not Return to Full Flow During Testing2016-03-31031 March 2016 Regarding Unit 2 HPCI Motor Gear Unit Would Not Return to Full Flow During Testing 05000237/LER-2015-005-01, Regarding HPCI Motor Gear Unit Would Not Return to Full Flow During Testing2016-02-25025 February 2016 Regarding HPCI Motor Gear Unit Would Not Return to Full Flow During Testing 05000237/LER-2015-003, Regarding Turbine Building to Reactor Building Interlock Doors Open Simultaneously2015-10-30030 October 2015 Regarding Turbine Building to Reactor Building Interlock Doors Open Simultaneously 05000237/LER-2015-005, Regarding HPCI Motor Gear Unit Would Not Return to Full Flow During Testing2015-10-30030 October 2015 Regarding HPCI Motor Gear Unit Would Not Return to Full Flow During Testing 05000249/LER-2015-001, Regarding Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value2015-10-29029 October 2015 Regarding Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value 05000237/LER-2015-002, Regarding 2C ERV Failed to Actuate During Extent of Condition Testing2015-04-0303 April 2015 Regarding 2C ERV Failed to Actuate During Extent of Condition Testing 05000237/LER-2015-001, Regarding Unit 2 Scram Due to Feedwater Level Control Issues2015-03-0606 March 2015 Regarding Unit 2 Scram Due to Feedwater Level Control Issues 05000249/LER-2014-001, Regarding Electromatic Relief Valve Failing to Actuate During Surveillance Testing2015-01-0505 January 2015 Regarding Electromatic Relief Valve Failing to Actuate During Surveillance Testing 05000237/LER-2014-003, Regarding Reactor Scram During Automatic Voltage Regulator Channel Transfer2014-06-0606 June 2014 Regarding Reactor Scram During Automatic Voltage Regulator Channel Transfer 05000237/LER-2014-002, Regarding Reactor Scram Due to Main Power Transformer Failure2014-06-0606 June 2014 Regarding Reactor Scram Due to Main Power Transformer Failure 05000237/LER-2014-001, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2014-05-27027 May 2014 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-009, Regarding HPCI Failed to Achieve Rated Flow Due to Failure of Stop Valve to Open2014-01-29029 January 2014 Regarding HPCI Failed to Achieve Rated Flow Due to Failure of Stop Valve to Open 05000249/LER-2013-001, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2014-01-27027 January 2014 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-008, Regarding Leak Identified on a Relief Valve During Pressure Test Resulting in a Degraded Principal Safety Barrier2014-01-24024 January 2014 Regarding Leak Identified on a Relief Valve During Pressure Test Resulting in a Degraded Principal Safety Barrier 05000237/LER-2013-007, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2014-01-15015 January 2014 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-005, Regarding Primary Containment Inboard and Outboard Feed Water Isolation Valves Exceed Leakage Limits2014-01-13013 January 2014 Regarding Primary Containment Inboard and Outboard Feed Water Isolation Valves Exceed Leakage Limits 05000237/LER-2013-006, Dressden Nuclear Power Station, Unit 2, Regarding LPCI Swing Bus Auto Transfer Did Not Transfer as Expected2014-01-13013 January 2014 Dressden Nuclear Power Station, Unit 2, Regarding LPCI Swing Bus Auto Transfer Did Not Transfer as Expected 05000237/LER-2013-004, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2014-01-0606 January 2014 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-003, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2013-11-22022 November 2013 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-002, Movement of Control Rods with Control Rod Block Monitor Inoperable2013-09-27027 September 2013 Movement of Control Rods with Control Rod Block Monitor Inoperable 05000237/LER-2013-001, Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2013-08-23023 August 2013 Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2011-005-01, For Dresden, Unit 2, Regarding Standby Liquid Control Explosive Valve Failure2012-12-18018 December 2012 For Dresden, Unit 2, Regarding Standby Liquid Control Explosive Valve Failure 05000237/LER-2012-001, Regarding One Division of APRM Neutron Flux-High Channels Inoperable as a Result of Power Maneuver2012-12-0606 December 2012 Regarding One Division of APRM Neutron Flux-High Channels Inoperable as a Result of Power Maneuver 05000249/LER-2012-001, Regarding Unexpected Isolation of the Isolation Condenser Due to Test Switch Failure2012-09-10010 September 2012 Regarding Unexpected Isolation of the Isolation Condenser Due to Test Switch Failure 05000237/LER-2012-002, Regarding Inlet Steam Drain Pot Drain Line Leaks Result in HPCI Inoperabilities2012-07-23023 July 2012 Regarding Inlet Steam Drain Pot Drain Line Leaks Result in HPCI Inoperabilities 05000237/LER-2011-003, Regarding MSIV Closure Times Outside of Technical Specifications Limits2011-12-16016 December 2011 Regarding MSIV Closure Times Outside of Technical Specifications Limits 2025-01-27
[Table view] |
LER-2014-001, Regarding Electromatic Relief Valve Failing to Actuate During Surveillance Testing |
Event date: |
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Report date: |
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Reporting criterion: |
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(ix)(A)
10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(x)
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)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(v), Loss of Safety Function |
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2492014001R00 - NRC Website |
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Ald o
Dresden Nuclear Power Station 6500 North Dresden Road mw Exe ton Generation Morrs, L 60450 815 942 2920 Telephone www.exeloncorp.com 10 CFR 50.73 SVPLTR # 15-0002 January 5, 2015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Renewed Facility Operating License No. DPR-25 NRC Docket No. 50-249
Subject:
Licensee Event Report 249/2014-001-00, Electromatic Relief Valve Failed to Actuate during Surveillance Testing Enclosed is Licensee Event Report 249/2014-001-00, "Electromatic Relief Valve Failed to Actuate during Surveillance Testing." This report describes an event which is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B), Any operation or condition which was prohibited by the plant's Technical Specifications.
There are no regulatory commitments contained in this submittal.
Should you have any questions concerning this letter, please contact Mr. Bruce Franzen at (815) 416-2800.
Respectfully, Shane M. Marik Site Vice President Dresden Nuclear Power Station Enclosure: Licensee Event Report 249/2014-001-00 cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station
/I NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017 (02-2014)
Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections L
N EV T R P T (Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by LICENSEE EVENT REPO T (LER) intemet e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and (See Page 2 for required number of Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. It a means used to impose an information collection does not display a currently valid OMB digits/characters for each block) control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Dresden Nuclear Power Station, Unit 3 05000249 1 OF 3
- 4. TITLE Electromatic Relief Valve Failed to Actuate during Surveillance Testing
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MNH DY YA YER SQETA RE
.YER FACILITY NAME IDOCKET NUMBER MO YEAR YEAR NUMBER NO.
ONTH DAY YEAR FACILITY NAME DOCKET NUMBER 11 06 2014 2014 001
- - 00 01 05 15
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
El 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii) 5l 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
[E 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71 (a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71 (a)(5) 000 El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
Z 50.73(a)(2)(i)(B)
[1 50.73(a)(2)(v)(D)
Specifyin Abstract be3oworin
PLANT AND SYSTEM IDENTIFICATION
Dresden Nuclear Power Station (DNPS), Unit 3, is a General Electric Company Boiling Water Reactor with a licensed maximum power level of 2957 megawatts thermal. The Energy Industry Identification System codes used in the text are identified as [XX].
A.
Plant Conditions Prior to Event:
Unit: 03 Reactor Mode: 5 Event Date: 11-06-2014 Mode Name: Refuel Event Time: 09:12 CST Power Level: 000 percent B.
Description of Event
On November 6, 2014, with the reactor in mode 5, Operations identified that an electromatic actuator failed to actuate during the performance of scheduled surveillance testing. The surveillance involves an operator manually actuating the ERV from the main control room with operators staged in the field. The operators in the field reported an audible click when the manual actuation was initiated. However, when the demand signal was given, the actuator plunger did not move and the valve did not open.
This event is being reported under 10 CFR 50.73(a)(2)(i)(B) "Any operation or condition which was prohibited by the plant's Technical Specifications."
C.
Cause of Event
The cause of this event is under investigation and will be updated in the Supplemental Report.
D.
Safety Analysis
The failure of the 3E ERV to actuate is a non-consequential critical component failure and a Maintenance Rule Functional Failure. The safety significance of the failure will be further investigated when the apparent cause report is complete.
4
E.
Corrective Actions
The failed ERV was replaced with a Hardened design during the Refueling Outage. Additional corrective actions will be updated in the Supplemental Report.
F.
Previous Occurrences
Previous occurrences are being investigated as part of the apparent cause investigation and will be updated in the Supplemental Report.
G.
Component Failure Data
Manufacturer Model S/N Type Dresser Industries 1525VX-3-OS108 BK7082 Relief Valve
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05000249/LER-2014-001, Regarding Electromatic Relief Valve Failing to Actuate During Surveillance Testing | Regarding Electromatic Relief Valve Failing to Actuate During Surveillance Testing | 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000237/LER-2014-001, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously | Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously | 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000237/LER-2014-002, Regarding Reactor Scram Due to Main Power Transformer Failure | Regarding Reactor Scram Due to Main Power Transformer 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000237/LER-2014-003, Regarding Reactor Scram During Automatic Voltage Regulator Channel Transfer | Regarding Reactor Scram During Automatic Voltage Regulator Channel Transfer | 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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