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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
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LER-2002-001, HPCI Not in Standby Operation When Required by the Technical Specifications |
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text
Exelte m.
Exelon Generation Dresden Generating Station 6500 North Dresden Road Morris, IL 60450-9765 Tel 815-942-2920 www.exeloncorp.com Nuclear 10 CFR 50.73 May 22, 2002 RHLTR: #02-0034 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Facility Operating License No. DPR-25 NRC Docket No. 50-249
Subject:
Licensee Event Report 2002-001-00, "HPCI Not in Standby Operation When Required by the Technical Specifications."
Enclosed is Licensee Event Report 2002-001-00, "HPCI Not in Standby Operation When Required by the Technical Specifications," for the Dresden Nuclear Power Station (DNPS). This event 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."
Corrective Actions include:
Provide Operator training on this event and applicable sections of Technical Specifications regarding section 3.0 compliance.
Personnel involved were coached and counseled as to the requirements and interface with Limiting Conditions of Operation in Technical Specification section 3.0.
Reviewed all Technical Specifications Limiting Condition of Operation Applicability sections to identify any sections that could cause a similar event.
Historical operations policy questions will be reviewed to determine if additional training is required to ensure TS compliance.
May 22, 2002 U.S. Nuclear Regulatory Commission Page 2 If you have any questions, please contact Bob Rybak, Regulatory Assurance Manager at (815) 416-2800.
Respectfully, R. J. Hovey Site Vice President Dresden Nuclear Power Station Enclosure cc:
Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Dresden Nuclear Power Station
Abstract
On March 23, 2002, at 1603 hours0.0186 days <br />0.445 hours <br />0.00265 weeks <br />6.099415e-4 months <br />, during reactor startup from a Unit 3 maintenance outage (D3M09), the High Pressure Coolant Injection (HPCI) system was not aligned to standby conditions when reactor steam dome pressure exceeded 150 psig. Technical Specification 3.5.1 requires HPCI to be operable in Modes 1, 2 and 3 when reactor steam dome pressure is >/= 150 psig. Significant maintenance had been performed on the HPCI system during D3M09. This maintenance required the performance of the low pressure HPCI run to validate operability. The operating crew believed HPCI was not operable until the low-pressure run was completed. They also believed there was a 12-hour allowance for HPCI to be inoperable above 150 psig to perform this test. Based on this belief, Operations personnel allocated resources to other activities that were required to be completed prior to reaching the reactor conditions that would support the low-pressure HPCI test, thus the HPCI 3-2301-4 and 3-2301-5 valves (steam supply) were left closed in preparation for the low pressure run.
The isolation valves would have opened upon receipt of an initiation signal and HPCI would have started. Additionally, Low Pressure Coolant Injection and Core Spray systems were in standby and would have injected upon receipt of an initiation signal. Therefore, the safety significance of this event is minimal.U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 COMMISSION EXPIRES 07/31/2004 (7-2001)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
FACILITY NAME (1)
DOCKET NUMBER (2 LER NUMBER (6 PAGE (3)
YEAR SEQUENTIAL REVISION Dresden Nuclear Power Station Unit 3 05000249 NUMBER NUMBER 2002 001 00 2 of 3 (If more space is required, use additional copies of NRC Form 366A)(17)
A.
Plant Conditions Prior to Event:
Unit: 03 Event Date: 03-23-2002 Event Time: 1603 CST Reactor Mode: 2 Mode Name: Startup Power Level: 002 percent Reactor Coolant System Pressure: 150 psig B.
Description of Event
This event is being reported in accordance with 10 CFR 50.73 (a)(2)(i)(B), which requires reporting "any operation or condition which was prohibited by the plant's Technical Specifications."
On March 15, 2002, Unit 3 was shut down to replace seventeen jet pump hold down beams. During the maintenance outage, extensive work was performed on the High Pressure Coolant Injection (HPCI) [BJ] system.
The post maintenance tests (PMT) required a low pressure HPCI surveillance to verify no leaks at system pressure.
On March 23, 2002, Unit 3 commenced a normal unit startup per station procedures. Prior to reactor pressure reaching 150 psig, the Unit Supervisor (US) declared the HPCI system inoperable and questioned whether the HPCI isolation valves, 3-2301-4 and 3-2301-5, were required to be open. This was questioned because the HPCI low-pressure test was scheduled to be performed at 165 psig with 2 turbine bypass valves open. The HPCI system was believed to be inoperable by the US due to the maintenance work performed during the outage.
Technical Specification (TS) 3.5.1 "ECCS-Operating", requires HPCI to be operable in Modes 1, 2 and 3 when reactor steam dome pressure is >/= 150 psig. The US determined that the valves could remain closed. This was based on an incorrect assumption that the system was inoperable until the low-pressure test was completed. The US requested a peer check of his determination. The Operations Outage Manager, Shift Outage Manager and the augmented Senior Reactor Operator performed that peer check. Following the discussion, the 3-2301-4 and 3-2301-5 valves were left in the closed position until the unit had reached the test conditions.
Subsequently, the Shift Operations Superintendent (SOS) arrived while the HPCI low-pressure test was in progress. The SOS reviewed the unit logs and recognized the HPCI system was not aligned to a standby condition prior to the unit reaching 150 psig. The SOS directed the US to amend the log entry that HPCI was inoperable until it was successfully aligned and tested.
However, on March 25, 2002, a review by site Regulatory Assurance personnel concluded that TS 3.5.1 requires HPCI to be operable in Modes 1, 2 and 3 when reactor steam dome pressure is >/= 150 psig and the plant had operated in a condition that was prohibited by the plant's TS. The Operations decision to consider HPCI inoperable and raise pressure was an incorrect application of the Technical Specifications for this condition. The correct application for this situation is to assume operability after the maintenance work was performed, not enter any LCOs, and to validate that assumption by testing when suitable conditions exist.
C.
Cause of Event
The root cause of this event was a knowledge deficiency associated with HPCI applicability which was complicated by the historical aspects of a TS note and the understanding of intent. The individuals involved focused on the Surveillance Requirements and not the applicability section of the TS. When questioned why theU.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 COMMISSION EXPIRES 0713112004 (7-2001)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
FACILITY NAME (1)
DOCKET NUMBER (2)
L ER NUMBER (6 PAGE (3)
YEAR SEQUENTIAL REVISION Dresden Nuclear Power Station Unit 3 05000249 j
20NUMBER NUMBER 2002 001 00 3 of 3 (If more space is required, use additional copies of NRC Form 366A)(17) focus was on the surveillance, both assumed HPCI operability would be proven during the testing.
(NRC Cause Code E)
To understand how Dresden licensed individuals acquired this mindset, a review of past outages, previous TS questions, correspondence regarding plant commitments, and limiting condition of operation (LCO) practices was conducted. During previous outages (D2R14 and D3R14), DNPS performed a unit start up with HPCI uncoupled.
When the unit reached 150 psig, a 12-hour LCO time clock was entered for testing. Once all testing was complete and HPCI re-coupled, unit start-up progressed. This investigation found a plant commitment letter and an operations policy question discussing this situation. Both state that the footnotes in previous TS 4.0.D allowed the site to extend the applicability for the required function. This guidance was inappropriate and fostered the current mindset. A review of all technical specification LCO applicability sections was performed to determine if similar issues existed for other TS sections. Based on this review, there are appropriate procedures and programs in place to prevent a similar event.
D.
Safety Analysis
The safety significance of this event is minimal. The plant was in startup at low reactor pressure (150-psig) during the period when the HPCI steam supply valves were closed. The Automatic Depressurization System, Isolation Condenser, Core Spray systems, and Low Pressure Coolant Injection system were operable and capable of performing their intended safety function.
E.
Corrective Actions
Provide Operator training on this event and applicable sections of Technical Specifications regarding section 3.0 compliance.
Personnel involved were coached and counseled as to the requirements and interface with Limiting Conditions of Operation in Technical Specification section 3.0.
Reviewed all Technical Specifications Limiting Condition of Operation Applicability sections to identify any sections that could cause a similar event.
Historical operations policy questions will be reviewed to determine if additional training is required to ensure TS compliance.
F.
Previous Occurrences
A search of previous history found that Dresden had started the unit up with the HPCI turbine uncoupled from the pump during D2R14 and D3R14. This would render the HPCI system inoperable and it is similar in that for both events, HPCI was inoperable during a change of condition.
G.
Component Failure Data
N/A
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05000249/LER-2002-001, HPCI Not in Standby Operation When Required by the Technical Specifications | HPCI Not in Standby Operation When Required by the Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000237/LER-2002-001, Re Unit 2 Isolation Condenser Time Delay Relay Surveillance Failures Due to Setpoint Tolerances Specified with No Margin | Re Unit 2 Isolation Condenser Time Delay Relay Surveillance Failures Due to Setpoint Tolerances Specified with No Margin | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000249/LER-2002-002, Reactor Scram Due to Main Shaft Oil Pump Failure | Reactor Scram Due to Main Shaft Oil Pump Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000237/LER-2002-002, Smoke Purge Mode Operation Prevents Safety Function of the Control Room Emergency Ventilation System on April 10, 2002 | Smoke Purge Mode Operation Prevents Safety Function of the Control Room Emergency Ventilation System on April 10, 2002 | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000249/LER-2002-003, Reactor Recirculation Loop a Sensing Line Socket Weld Vibration Fatigue Failure | Reactor Recirculation Loop a Sensing Line Socket Weld Vibration Fatigue Failure | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000237/LER-2002-003, Manual Valve Failures Prevent the Cooling Water Flow to Control Room Refrigeration Condensing Unit | Manual Valve Failures Prevent the Cooling Water Flow to Control Room Refrigeration Condensing Unit | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000249/LER-2002-004, Regarding Main Steam Safety Valves Failed TS as Found Lift Setpoint | Regarding Main Steam Safety Valves Failed TS as Found Lift Setpoint | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000237/LER-2002-004, Re Control Room Ventilation Ductwork Breached During Replacement of Temperature Transmitter | Re Control Room Ventilation Ductwork Breached During Replacement of Temperature Transmitter | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000249/LER-2002-005, High Pressure Coolant Injection System Inoperable Due to Water Hammer Event | High Pressure Coolant Injection System Inoperable Due to Water Hammer Event | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000237/LER-2002-005, Pressure Switches Found Above Technical Specification Allowable Values | Pressure Switches Found Above Technical Specification Allowable Values | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000249/LER-2002-006, Re Reactor Recirculation Loop a Sensing Line Socket Weld Failure | Re Reactor Recirculation Loop a Sensing Line Socket Weld Failure | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
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