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Category:Letter
MONTHYEARIR 05000333/20240902024-10-29029 October 2024 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000333/2024090 JAFP-24-0055, Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation2024-10-29029 October 2024 Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation IR 05000333/20244022024-10-28028 October 2024 Material Control and Accounting Program Inspection Report 05000333/2024402 (Cover Letter Only) ML24276A1332024-10-17017 October 2024 Issuance of Amendment No. 357 Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision-4, and Administrative Changes ML24282B0302024-10-11011 October 2024 Project Manager Assignment 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 ML24207A0192024-10-0909 October 2024 SE Addendum Related to the License Amendment No. 338 for Implementation of the Alternative Source Term (DPO-2021-001) JAFP-24-0051, Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-0882024-10-0303 October 2024 Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-088 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24270A0742024-09-30030 September 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0134) - LTR ML24270A1452024-09-26026 September 2024 Notice of Enforcement Discretion for James A. Fitzpatrick Nuclear Power Plant JAFP-24-0046, Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation2024-09-25025 September 2024 Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation JAFP-24-0047, License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software2024-09-25025 September 2024 License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software JAFP-24-0045, Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2024-09-20020 September 2024 Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20240112024-09-19019 September 2024 Follow-up to Inspection Procedure 71153 Report 05000333/2024011 and Preliminary White Finding and Apparent Violation JAFP-24-0044, Core Operating Limits Report Cycle 272024-09-16016 September 2024 Core Operating Limits Report Cycle 27 JAFP-24-0043, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2024-09-12012 September 2024 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues 05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-0404 September 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation ML24165A0382024-09-0404 September 2024 Issuance of Amendment No. 356 Update Fuel Handling Accident Analysis IR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) 05000333/LER-2024-001-01, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-08-21021 August 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report ML24208A0492024-07-30030 July 2024 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Proposed No Significant Hazards Consideration Determination (Letter) JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20244032024-07-18018 July 2024 Biennial Problem Identification and Resolution Inspection Report 05000333/2024403 (Cover Letter Only) IR 05000333/20244012024-07-15015 July 2024 Security Baseline Inspection 05000333/2024401 RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions ML24190A1932024-07-0909 July 2024 Correction Letter of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 ML24184A1662024-07-0303 July 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24136A1162024-06-26026 June 2024 Issuance of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance 05000333/LER-2024-001, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24176A2412024-06-24024 June 2024 Licensed Operator Positive Fitness-for-Duty Test JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations JAFP-24-0026, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance2024-06-12012 June 2024 Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 JAFP-24-0023, 2023 Annual Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000333/20240012024-05-0909 May 2024 Integrated Inspection Report 05000333/2024001 RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 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 JAFP-24-0020, 2023 Annual Radioactive Effluent Release Report2024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report JAFP-24-0019, 2023 REIRS Transmittal of NRC Form 52024-04-18018 April 2024 2023 REIRS Transmittal of NRC Form 5 ML24106A0152024-04-15015 April 2024 Request for Withholding Information from Public Disclosure Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24107A6972024-04-12012 April 2024 Engine Systems, Inc Part 21 Report Re EMD Cylinder Liner Water Leak RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24068A0532024-03-28028 March 2024 Issuance of Amendment No. 354 Revise Technical Specifications Section 3.3.1.2, Source Range Monitors Instrumentation 2024-09-04
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-0404 September 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation 05000333/LER-2024-001-01, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-08-21021 August 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket 05000333/LER-2024-001, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket 05000333/LER-2023-004, For James A. Ftizpatrick Nuclear Power Plant, Misaligned Spacer Prevented Tie Breaker Closing Coil Armature Operation on a Magne-Blast for EDG a Subsystem2023-12-0101 December 2023 For James A. Ftizpatrick Nuclear Power Plant, Misaligned Spacer Prevented Tie Breaker Closing Coil Armature Operation on a Magne-Blast for EDG a Subsystem 05000333/LER-2022-003-02, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low2023-09-0808 September 2023 Safety Relief Valves Lift Setpoint Found Out of Tolerance Low 05000333/LER-2023-002-01, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2023-08-14014 August 2023 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation 05000333/LER-2023-003, Emergency Diesel Generator Fuel Oil Supply Procedure Error B Subsystem2023-06-23023 June 2023 Emergency Diesel Generator Fuel Oil Supply Procedure Error B Subsystem 05000333/LER-2023-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2023-06-13013 June 2023 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation 05000333/LER-1922-003-01, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low2023-04-28028 April 2023 Safety Relief Valves Lift Setpoint Found Out of Tolerance Low 05000333/LER-2023-001, Primary Containment Isolation System Isolation Due to Initiation of Main Condenser Fire Protection Foam System2023-04-19019 April 2023 Primary Containment Isolation System Isolation Due to Initiation of Main Condenser Fire Protection Foam System 05000333/LER-2022-002-01, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation2023-01-31031 January 2023 Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation 05000333/LER-2021-001-01, Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas2023-01-10010 January 2023 Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas 05000333/LER-2022-003, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low2022-11-30030 November 2022 Safety Relief Valves Lift Setpoint Found Out of Tolerance Low 05000333/LER-2022-002, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation2022-11-22022 November 2022 Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation 05000333/LER-2022-001, Exhaust Drain Pot Line Filled with Water Up to HPCI Turbine Due to Relay Failure2022-06-28028 June 2022 Exhaust Drain Pot Line Filled with Water Up to HPCI Turbine Due to Relay Failure 05000333/LER-2021-003, Air Solenoid Valve Condition Results in Main Steam Isolation Valve (MSIV) Fast Closure Test Failure2022-01-14014 January 2022 Air Solenoid Valve Condition Results in Main Steam Isolation Valve (MSIV) Fast Closure Test Failure 05000333/LER-2021-002, Automatic High Pressure Coolant Injection (HPCI) System Function Prevented by Control Circuit Relay Failure2022-01-14014 January 2022 Automatic High Pressure Coolant Injection (HPCI) System Function Prevented by Control Circuit Relay Failure 05000333/LER-2021-001, Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas2021-10-22022 October 2021 Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas 05000333/LER-2020-003-01, High Pressure Coolant Injection Inoperable Due to Oil Leak2021-09-0808 September 2021 High Pressure Coolant Injection Inoperable Due to Oil Leak JAFP-17-0051, LER 17-03-00 for FitzPatrick Regarding Inadvertent Isolation of the High Pressure Coolant Injection System2017-06-0505 June 2017 LER 17-03-00 for FitzPatrick Regarding Inadvertent Isolation of the High Pressure Coolant Injection System 05000333/LER-2017-0012017-03-13013 March 2017 Vent Line Socket Weld Failure, LER 17-001-00 for James A. Fitzpatrick Nuclear Power Plant RE: Vent Line Socket Weld Failure 05000333/LER-2016-0042016-08-23023 August 2016 Transformer Fault Results in Manual Scram and Secondary Containment Vacuum Below Technical Specification Limit, LER 16-004-00 for James A. Fitzpatrick Regarding Transformer Fault Results in Manual Scram and Secondary Containment Vacuum Below Technical Specification Limit 05000333/LER-2016-0032016-08-0303 August 2016 Concurrent Opening of Reactor Building Airlock Doors, LER 16-003-00 for James A. FitzPatrick Regarding Concurrent Opening of Reactor Building Airlock Doors 05000333/LER-2016-0022016-04-25025 April 2016 Sticking DC Pilot in Solenoid Valve Cluster Assembly Results in Slow MSIV Closures, LER 16-002-00 for James A. Fitzpatrick Nuclear Power Plant, Regarding Sticking DC Pilot in Solenoid Valve Cluster Assembly Results in Slowly MSIV Closure 05000333/LER-2016-0012016-03-23023 March 2016 System Actuations during Manual Scram in Response to Frazil Ice Blockage and Residual Transfer, LER 16-001-00 for James A. FitzPatrick Regarding System Actuations during Manual Scram in Response to Frazil Ice Blockage and Residual Transfer 05000333/LER-2015-0082016-02-16016 February 2016 Containment Atmosphere Dilution System Reliability Degraded due to Manufacturer Defect in Temperature Transmitters, LER 15-008-00 for James A. Fitzpatrick Regarding Containment Atmosphere Dilution System Reliability Degraded Due to Manufacturer Defect in Temperature Transmitters 05000333/LER-2015-0062016-02-0404 February 2016 Transitory Secondary Containment Differential Pressure Excursions, LER 15-006-01 for James A. FizPatrick Regarding Transitory Secondary Containment Differential Pressure Excursions 05000333/LER-2015-0072016-02-0101 February 2016 Slow Exhaust Fan Start Leads to Secondary Containment Vacuum Below Technical Specification Limit, LER 15-007-00 for James A. Fitzpatrick Regarding Slow Exhaust Fan Start Leads to Secondary Containment Vacuum Below Technical Specification Limit ML1015505722009-12-28028 December 2009 Event Notification for Fitzpatrick on Offsite Notification for Elevated Tritium Levels ML0509505652004-12-17017 December 2004 Final Precursor Analysis - Fitzpatrick Grip Loop 2024-09-04
[Table view] |
LER-2022-001, Exhaust Drain Pot Line Filled with Water Up to HPCI Turbine Due to Relay Failure |
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10 CFR 50.73(a)(2)(v), Loss of Safety Function |
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text
James A. FitzPatrick NPP Constellation PO Box 110 Lycoming. NY 13093
Timothy C. Peter Site Vice President-JAF
JAFP-22-0034 June 28, 2022
United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-059 NRC Docket No. 50-333
Subject: LER: 2022-001, Exhaust Drain Pot Line Filled with Water up to HPCI Turbine due to Relay Failure
Dear Sir or Madam:
This report is being submitted pursuant to 10 CFR 50. 73(a)(2)(v)(D).
There are no new regulatory commitments contained in this report.
Questions concerning this report may be addressed to Mr. Richard Sullivan, Regulatory Assurance Manager, at (315) 349-6562.
TCP/RS
Enclosure : LER: 2022-001, Exhaust Drain Pot Line Filled with Water up to HPCI Turbine due to Relay Failure
cc : USNRC, Region I Administrator USNRC, Project Manager USNRC, Resident Inspector INPO Records Center (IRIS)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2023 (08-2020)
James A. FitzPatrick Nuclear Power Plant 05000333 1 OF 3
- 4. Title LER: 2022-001, Exhaust Drain Pot Line Filled with Water up to H PCI Turbine due to Relay Failure
- 5. Event Date 6. LER Number 7. Report Date 8. Other Facilities Involved Revision Facility Name Docket Number Month Day Year Year Sequential Number No. Month Day Year N/A N/A
Facility Name Docket Number 04 29 2022 2022 - 001 - 00 N/A N/A
- 9. Operating Mode 10. Power Level 1 100 No Yes (If yes, complete 15. Expected Submission date)
Abstract (Limit to 1560 spaces, i.e., approximately 15 single-spaced typewritten lines)
At 1251 EDT on April 29, 2022, while troubleshooting the failur e of the High Pressure Coolant Injection (HPCI)
Exhaust Drain Pot High Level Alarm to clear, it was discovered that the High Pressure Coolant Injection exhaust line condensate drain system was not functioning as des igned to support removal of condensate from the turbine exhaust. Troubleshooting determined that a logic re lay failed to start the HPCI Gland Seal Condensate pump. This resulted in some water accumulation in th e turbine casing.
Subsequently, the High Pressure Coolant Injection System was de clared inoperable. The turbine casing was manually drained and the failed relay was replaced. The system was restored to Operable.
As a result, this condition is being reported under 10 CFR 50.7 2(b)(3)(v)(D) as a condition that could have prevented fulfillment of the safety function at the time of dis covery.
NRC FORM 366 (08-2020)
Background
The High Pressure Coolant Injection (HPCI) System [EIIS Identif ier: BJ] at James A. FitzPatrick Nuclear Power Plant (JAF) is a part of the Emergency Core Cooling System (ECC S); HPCI provides and maintains an adequate coolant inventory inside the Reactor Pressure Vessel [ RPV] to prevent damage to the reactor core under postulated accident scenarios. The system is comprised of various components which include pumps, valves, piping, and instrumentation. The HPCI system is powered by a steam turbine using steam from the reactor. Steam is pressurized up to the admission valve 23MOV-1 4 which will open to admit steam to the HPCI turbine on a system initiation signal.
HPCI has a Gland Exhaust System to collect steam leakage from t he turbine shaft seals, turbine control & stop valve stems, and turbine exhaust casing drains. The system work s with the HPCI exhaust Drain Pot to collect condensation from the bonnets of several valves and the HPCI tu rbine casing. The condensation is collected in the Gland Seal Condenser, and then pumped to Radwaste while in a standby lineup.
23LS-98 senses level in the Exhaust Drain Pot, causes Annunciat or ARP-09-3-3-18 (HPCI Exhaust Drain Pot Level High) and opens a valve to allow the Drain Pot to drain t o the Gland Seal Condenser.
23LS-100 senses level in the Gland Seal Condenser, energizes 23 A-K31, and auto starts the 23P-141 (HPCI Gland Seal Condensate Pump) to pump the Gland Seal Condenser to Radwaste.
Event Description
On April 28, 2022, at 2245, control room annunciator ARP-09-3-3 -18, HPCI drain pot water level alarm was received. Troubleshooting determined that HPCI logic relay 23A K31 failed to activate the HPCI Gland Seal Condensate pump to remove condensate from the turbine exhaust. As a result, water from 23MOV-14 steam leakby had accumulated in the HPCI turbine casing.
The crew placed the HPCI auxiliary oil pump in Pull to Lock to mitigate any potential impact to personnel while draining the HPCI exhaust. The Pull to Lock switch position pre vents the HPCI turbine from starting. The HPCI Exhaust Drain Pot was manually drained by Operations. Fol lowing draining, the HPCI system was declared operable.
The condition was reported as a condition which could have prev ented fulfillment of a safety function to mitigate the consequences of an accident per 10 CFR 50.72(b)(3) (v)(D), as submitted by ENS 55871.
Event Analysis
Level switch 23LS-100 senses water level in the HPCI gland seal condenser. On a high level, the level switch actuates relay 23A-K31 which alarms in the control room and sta rts the HPCI gland seal condenser pump (23P-141). The pump removes the condensate by pumping the water to the radwaste system. Troubleshooting determined that 23A-K31 had failed, preventing the auto start o f 23P-141. This caused the HPCI exhaust drain pot to fill with condensate and subsequently a volume of condensate also accumulated in the HPCI turbine casing.
The potential effects of water in the HPCI turbine casing is th at a slug of water could cause a HPCI exhaust rupture disk diaphragm to be damaged upon HPCI initiation. Anot her potential effect of water in the turbine NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2023 (08-2020)
James A. FitzPatrick Nuclear Power Plant 05000 - 333 NUMBER N0.
2022 - 001 - 00 exhaust line is that it could cause abnormal turbine operation due to high exhaust pressure. The backup of water into the HPCI turbine is a condition that could have prev ented the operation of HPCI and is reportable per 10 CFR 50.73(a)(2)(v)(D).
Cause
The direct cause of this event was a failure of 23A-K31 from ac tuating 23P-141 to pump down the condensate water before it filled the HPCI exhaust drain pot.
Similar Events
Condition Report: AR 04381156,Suspected leakage past 23MOV-14, dated October 31, 2020
FAILED COMPONENT IDENTIFICATION:
Manufacturer: General Electric Manufacturer Model Number: CR2820B SERIES A Manufacturer Code: G080 Component Code: RLY FitzPatrick Component ID: 23A-K31
Corrective Actions
Completed Actions Operators manually drained the HPCI Drain Pot The HPCI Logic Relay 23A-K31 was replaced Planned Actions Evaluate PM strategy for affected relay and condensate drain sy stem.
Perform further analysis on impacts of water in HPCI turbine ca sing.
Operations refresher training on Abnormal Condition Monitoring Plans.
Safety Significance
Nuclear safety - There were no actual consequences caused by this condition. The potential consequence during a postulated accident scenario is when HPCI actuates, th e water present in the turbine could damage or prevent the system operation. While HPCI is operating, the a bility to drain water through the drain pot is not required for continued system operation since excess water accu mulation is pushed out with steam exhaust.
The risk for this event is restricted to the period when the re lay failed to automatically actuate the pump to remove water which was determined to be less than 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.
References Issue Report - IR 04496616, HPCI Exhaust Drain Pot Level Hi Tro ubleshooting, dated April 29, 2022
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05000333/LER-2022-001, Exhaust Drain Pot Line Filled with Water Up to HPCI Turbine Due to Relay Failure | Exhaust Drain Pot Line Filled with Water Up to HPCI Turbine Due to Relay Failure | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000333/LER-2022-002-01, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation | Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000333/LER-2022-002, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation | Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000333/LER-2022-003-02, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low | Safety Relief Valves Lift Setpoint Found Out of Tolerance Low | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000333/LER-2022-003, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low | Safety Relief Valves Lift Setpoint Found Out of Tolerance Low | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
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