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Category:Letter
MONTHYEARPLA-8150, Independent Spent Fuel Storage - Installation Decommissioning Funding Plan Updated PLA-81502024-12-10010 December 2024 Independent Spent Fuel Storage - Installation Decommissioning Funding Plan Updated PLA-8150 IR 05000387/20244022024-12-0505 December 2024 Cyber Security Inspection Report 05000387/2024402 and 05000388/2024402 (Cover Letter Only) PLA-8153, Response to Preliminary White Finding and Apparent Violation Documented in NRC Inspection Report 2024012, EA-24-111 PLA-81532024-12-0404 December 2024 Response to Preliminary White Finding and Apparent Violation Documented in NRC Inspection Report 2024012, EA-24-111 PLA-8153 IR 05000387/20240122024-11-25025 November 2024 Follow-Up to Inspection Procedure 71111.12 Inspection Report 05000387/2024012 and 05000388/2024012 and Preliminary White Finding and Apparent Violation IR 05000387/20244202024-11-20020 November 2024 Security Baseline Inspection Report 05000387/2024420 and 05000388/2024420 Cover Letter IR 05000387/20245012024-11-13013 November 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000387/2024501 and 05000388/2024501 IR 05000387/20240102024-11-13013 November 2024 Biennial Problem Identification and Resolution Inspection Report 05000387/2024010 and 05000388/2024010 IR 05000387/20240032024-11-12012 November 2024 Integrated Inspection Report 05000387/2024003 and 05000388/2024003 PLA-8135, Specification 5.5.12, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type Leak Rate Testing Frequencies and Permanently Extend the Drywell Bypass Leakage Test Frequency - PLA-81352024-11-0101 November 2024 Specification 5.5.12, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type Leak Rate Testing Frequencies and Permanently Extend the Drywell Bypass Leakage Test Frequency - PLA-8135 ML24289A1252024-10-22022 October 2024 – Authorized Alternative to Requirements of the ASME OM Code PLA-8145, Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-81452024-10-21021 October 2024 Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-8145 ML24291A1562024-10-16016 October 2024 Missed Annual Inventory Required by 40 CFR 266, Subpart in PLE 0026645 PLA-8148, Registration for the Use of Spent Fuel Storage Casks 311, 308, and 3102024-10-15015 October 2024 Registration for the Use of Spent Fuel Storage Casks 311, 308, and 310 PLA-8141, Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-81412024-09-18018 September 2024 Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-8141 PLA-8142, Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-81422024-09-18018 September 2024 Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-8142 ML24260A2312024-09-17017 September 2024 Senior Reactor and Reactor Operator Initial License Examinations 05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor2024-09-16016 September 2024 B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24233A2192024-09-0303 September 2024 – Authorized Alternative to Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code IR 05000387/20240052024-08-29029 August 2024 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2024005 and 05000388/2024005) 05000387/LER-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2024-001-01, Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear2024-08-21021 August 2024 Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear IR 05000387/20240022024-08-12012 August 2024 Integrated Inspection Report 05000387/2024002 and 05000388/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification PLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) ML24197A0982024-07-15015 July 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000387/2024010 and 05000388/2024010 ML24127A2262024-05-29029 May 2024 Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563 PLA-8126, Response to Request for Confirmation of Information Regarding Relief Request 1RR062024-05-29029 May 2024 Response to Request for Confirmation of Information Regarding Relief Request 1RR06 PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122)2024-05-28028 May 2024 Annual Radiological Environmental Operating Report (PLA-8122) PLA-8115, Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)2024-05-23023 May 2024 Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115) 05000387/LER-2024-001, Main Steam Isolation Valve Leakage2024-05-23023 May 2024 Main Steam Isolation Valve Leakage IR 05000387/20240012024-05-13013 May 2024 Integrated Inspection Report 05000387/2024001 and 05000388/2024001 IR 05000387/20244042024-05-0707 May 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404 PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024 Re 2023 Annual Report of Radiation Exposure PLA-8094, Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-80942024-04-22022 April 2024 Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094 PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024 2023 Annual Radiological Environmental Operating Report (PLA-8095) ML24082A1372024-04-22022 April 2024 Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes PLA-8113, Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113)2024-04-11011 April 2024 Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113) PLA-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024 Annual Environmental Operating Report (Nonradiological) PLA-8102 PLA-8112, Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-81122024-04-0909 April 2024 Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112 PLA-8110, Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)2024-04-0404 April 2024 Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110) PLA-8100, Property Insurance Program (PLA-8100)2024-04-0101 April 2024 Property Insurance Program (PLA-8100) PLA-8098, Annual Financial Report (PLA-8098)2024-04-0101 April 2024 Annual Financial Report (PLA-8098) PLA-8109, Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109)2024-03-21021 March 2024 Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109) ML24067A2512024-03-19019 March 2024 Authorized Alternative to Requirements of the ASME Code PLA-8107, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance2024-03-19019 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance ML24044A2532024-03-14014 March 2024 Associated Independent Spent Fuel Storage Installation – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0077 (Security Notifications, Reports, and Recordkeeping & Suspicious Activity Reporting)) IR 05000387/20240112024-02-29029 February 2024 Commercial Grade Dedication Inspection Report 05000387/2024011 and 05000388/2024011 IR 05000387/20230062024-02-28028 February 2024 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2023006 and 05000388/2023006) 2024-09-06
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor2024-09-16016 September 2024 B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor 05000387/LER-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2024-001-01, Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear2024-08-21021 August 2024 Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear 05000387/LER-2024-001, Main Steam Isolation Valve Leakage2024-05-23023 May 2024 Main Steam Isolation Valve Leakage 05000387/LER-2023-004, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-01-0909 January 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2023-003, D Diesel Generator Inoperable Due to Clogged Fuel Injectors2023-11-0909 November 2023 D Diesel Generator Inoperable Due to Clogged Fuel Injectors 05000387/LER-2023-002, Unplanned Lnoperability of the High Pressure Coolant Injection (HPCI) System Due Failure of the HPCI Turbine Stop Valve to Fully Close, Most Likely Due to Internal Corrosion and2023-06-0606 June 2023 Unplanned Lnoperability of the High Pressure Coolant Injection (HPCI) System Due Failure of the HPCI Turbine Stop Valve to Fully Close, Most Likely Due to Internal Corrosion And. 05000388/LER-2023-001, Secondary Containment Bypass Leakage Limit Exceeded Due Inadequate Procedure Guidance Resulting in Failure of the Inboard Containment Isolation Valve to Close and Pressurize2023-05-25025 May 2023 Secondary Containment Bypass Leakage Limit Exceeded Due Inadequate Procedure Guidance Resulting in Failure of the Inboard Containment Isolation Valve to Close and Pressurize 05000387/LER-2023-001, Inadvertent Contact Between Relay Cover and Relay Trip Contacts Resulted in Automatic Actuation of the ‘B’ Emergency Diesel Generator2023-05-22022 May 2023 Inadvertent Contact Between Relay Cover and Relay Trip Contacts Resulted in Automatic Actuation of the ‘B’ Emergency Diesel Generator 05000387/LER-2022-003, Inoperable 13.8kV Startup Transformer Due to Misaligned Load Tap Charger Local/Remote Control Switch2022-12-19019 December 2022 Inoperable 13.8kV Startup Transformer Due to Misaligned Load Tap Charger Local/Remote Control Switch 05000387/LER-2022-002-01, Automatic Reactor Scram Due to Reactor Protection System Actuation on High Reactor Vessel Pressure Signal Following Inadvertent Closure of Inboard Main Steam Isolation Valve2022-12-0505 December 2022 Automatic Reactor Scram Due to Reactor Protection System Actuation on High Reactor Vessel Pressure Signal Following Inadvertent Closure of Inboard Main Steam Isolation Valve 05000388/LER-2022-001, Re Inadequate Performance of Loss of Safety Determination Resulting in Both Divisions of Core Spray Being Inoperable2022-11-23023 November 2022 Re Inadequate Performance of Loss of Safety Determination Resulting in Both Divisions of Core Spray Being Inoperable 05000388/LER-2021-004-01, From Susquehanna Steam Electric Station, Unit 2 Main Turbine Pressure Regulator Inoperable for Longer than Allowed by Technical Specifications Due to Inadequate Valve Modification2022-11-0303 November 2022 From Susquehanna Steam Electric Station, Unit 2 Main Turbine Pressure Regulator Inoperable for Longer than Allowed by Technical Specifications Due to Inadequate Valve Modification 05000387/LER-2022-001-01, From Susquehanna Steam Electric Station Unit 1 - Main Steam Line Isolation Valve Leakage Due to Seating Surfaces Wear and Material Deposits2022-08-10010 August 2022 From Susquehanna Steam Electric Station Unit 1 - Main Steam Line Isolation Valve Leakage Due to Seating Surfaces Wear and Material Deposits 05000387/LER-2022-002, Automatic Reactor Scram Due to High Reactor Vessel Pressure Following Inadvertent Closure of Inboard Main Steam Isolation Valve2022-07-21021 July 2022 Automatic Reactor Scram Due to High Reactor Vessel Pressure Following Inadvertent Closure of Inboard Main Steam Isolation Valve 05000387/LER-2022-001, Main Steam Isolation Valve Leakage2022-06-0101 June 2022 Main Steam Isolation Valve Leakage 05000388/LER-2021-005-01, Condition Prohibited by Technical Specification Due to Setpoint Drift Attributed to Age Related Degradation2022-04-11011 April 2022 Condition Prohibited by Technical Specification Due to Setpoint Drift Attributed to Age Related Degradation 05000387/LER-2021-005-01, Automatic Reactor Scram Due to Turbine Control Valve Fast Closure2022-03-30030 March 2022 Automatic Reactor Scram Due to Turbine Control Valve Fast Closure 05000388/LER-2021-003-01, Automatic Reactor Scram Due to Main Turbine Trip Caused by Inadvertent Trip of the Main Generator Output Breakers2022-03-24024 March 2022 Automatic Reactor Scram Due to Main Turbine Trip Caused by Inadvertent Trip of the Main Generator Output Breakers 05000388/LER-2021-001-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch2022-03-21021 March 2022 Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch 05000387/LER-2021-004-01, Loss of 1B RHRSW Pump Due to Cable Damage During Excavation Activities2022-03-21021 March 2022 Loss of 1B RHRSW Pump Due to Cable Damage During Excavation Activities 05000388/LER-2021-005, Condition Prohibited by Technical Specification Due to Setpoint Drift2022-02-11011 February 2022 Condition Prohibited by Technical Specification Due to Setpoint Drift 05000388/LER-2021-002-01, Loss of Secondary Containment Due to Failed Differential Pressure Transmitter2022-02-0808 February 2022 Loss of Secondary Containment Due to Failed Differential Pressure Transmitter 05000387/LER-2021-005, Automatic Reactor Scram Due to Turbine Control Valve Fast Closure2022-01-26026 January 2022 Automatic Reactor Scram Due to Turbine Control Valve Fast Closure PLA-7976, Automatic Reactor Scram Due to Main Turbine Trip2021-12-0909 December 2021 Automatic Reactor Scram Due to Main Turbine Trip PLA-7977, Main Turbine Pressure Regulator Inoperable for Longer than Allowed by Technical Specifications2021-12-0909 December 2021 Main Turbine Pressure Regulator Inoperable for Longer than Allowed by Technical Specifications 05000387/LER-2021-004, Loss of 1B RHRSW Pump Due to Cable Damage During Excavation Activities2021-12-0101 December 2021 Loss of 1B RHRSW Pump Due to Cable Damage During Excavation Activities 05000387/LER-2021-003-01, Automatic Reactor Scram Due to Main Turbine Trip Caused by a C Isophase Bus Ground Fault2021-11-11011 November 2021 Automatic Reactor Scram Due to Main Turbine Trip Caused by a C Isophase Bus Ground Fault 05000388/LER-2021-002, Re Loss of Secondary Containment2021-10-28028 October 2021 Re Loss of Secondary Containment 05000387/LER-2021-003, Automatic Reactor Scram Due to Main Turbine Trip2021-09-16016 September 2021 Automatic Reactor Scram Due to Main Turbine Trip 05000388/LER-2021-001, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch2021-09-0101 September 2021 Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch 05000388/LER-2020-002-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch Caused by Lack of Requirements for Acclimation of the Instrument to the Operating Environment2021-07-0101 July 2021 Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch Caused by Lack of Requirements for Acclimation of the Instrument to the Operating Environment 05000387/LER-2017-010-02, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches2021-07-0101 July 2021 Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches 05000387/LER-2018-005-02, (SSES) Unit 1 Re Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches2021-07-0101 July 2021 (SSES) Unit 1 Re Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches 05000387/LER-2021-002, Inoperability of Computer Room Floor Cooling Fan Caused by Extended Operation with Worn Belts Due to Less than Adequate Preventive Maintenance Replacement Interval2021-06-28028 June 2021 Inoperability of Computer Room Floor Cooling Fan Caused by Extended Operation with Worn Belts Due to Less than Adequate Preventive Maintenance Replacement Interval 05000387/LER-2021-001, Electri Station, Unplanned Lnoperability of the High Pressure Coolant Injection (HPCI) System Due to a Primary Containment Isolation (PCIV) Valve Failure to Stroke Full Closed On-demand Due to an Intermittent Break2021-05-0606 May 2021 Electri Station, Unplanned Lnoperability of the High Pressure Coolant Injection (HPCI) System Due to a Primary Containment Isolation (PCIV) Valve Failure to Stroke Full Closed On-demand Due to an Intermittent Break 05000387/LER-2020-002-01, Inoperability of Unit 1 B Residual Heat Removal Service Water Pump Due to the Circuit Breaker Spring Charging Motor Contact Actuator Being Out of Adjustment2021-02-10010 February 2021 Inoperability of Unit 1 B Residual Heat Removal Service Water Pump Due to the Circuit Breaker Spring Charging Motor Contact Actuator Being Out of Adjustment 05000387/LER-2020-003, Condition Prohibited by Technical Specifications Due to Inoperable Turbine Stop Valve and Turbine Control Valve Instrumentation2020-12-21021 December 2020 Condition Prohibited by Technical Specifications Due to Inoperable Turbine Stop Valve and Turbine Control Valve Instrumentation 05000388/LER-2020-001-01, Manual Scram Due to Rising Main Condenser Backpressure Caused by Failure of an Offgas Recombiner Inlet Valve2020-11-0505 November 2020 Manual Scram Due to Rising Main Condenser Backpressure Caused by Failure of an Offgas Recombiner Inlet Valve PLA-7901, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch2020-10-0707 October 2020 Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch 05000387/LER-2020-001, Automatic Reactor Scram Due to Main Turbine Trip2020-07-0101 July 2020 Automatic Reactor Scram Due to Main Turbine Trip 05000388/LER-2020-001, Manual Reactor Scram Due to Rising Main Condenser Backpressure2020-04-0707 April 2020 Manual Reactor Scram Due to Rising Main Condenser Backpressure 05000387/LER-2019-002-01, 1 for Susquehanna Steam Electric Station, Unit 1, Lnoperability of C Emergency Service Water Pump2019-12-18018 December 2019 1 for Susquehanna Steam Electric Station, Unit 1, Lnoperability of C Emergency Service Water Pump 05000387/LER-2018-005-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches2019-12-16016 December 2019 Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches 05000387/LER-2019-001-01, Loss of Both Control Structure Chillers Due to Misaligned Breaker Stab2019-12-11011 December 2019 Loss of Both Control Structure Chillers Due to Misaligned Breaker Stab 05000387/LER-2019-003, D Diesel Generator Inoperable Due to Inadequate Post-Maintenance Test2019-12-11011 December 2019 D Diesel Generator Inoperable Due to Inadequate Post-Maintenance Test 05000387/LER-2019-002, Inoperability of C Emergency Service Water Pump2019-10-28028 October 2019 Inoperability of C Emergency Service Water Pump 05000388/LER-2019-002, Valid Actuation of the Primary Containment Isolation System Due to a Trip of Reactor Protection System Bus 2B2019-08-22022 August 2019 Valid Actuation of the Primary Containment Isolation System Due to a Trip of Reactor Protection System Bus 2B 05000387/LER-2019-001, Loss of Both Control Structure Chillers2019-07-18018 July 2019 Loss of Both Control Structure Chillers 05000388/LER-2019-001-01, Main Steam Isolation Valve Leakage2019-07-10010 July 2019 Main Steam Isolation Valve Leakage 2024-09-16
[Table view] |
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Kevin Cimorelli Site Vice President Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, P A 18603 Tel. 570.542.3795 Fax 570.542.1504 Kevin.Cimorel1i@TalenEnergy.com SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387(388)/2019-003-00 UNIT 1 LICENSE NO. NPF-14 UNIT 2 LICENSE NO. NPF-22 PLA-7828 TALEN~
ENERGY 10 CPR 50.73 Docket No. 50-387 and 50-388 Attached is Licensee Event Report (LER) 50-387(388)/2019-003-00. This LER reports a condition in which the D Diesel Generator was slow to start and reach required frequency. This condition was determined to be reportable in accordance with 10 CPR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications and 10 CPR 50.73(a)(2)(v) as an event or condition which could have prevented the fulfillment of a safety function. There were no actual consequences to the health and safety of the public as a result of this event.
This letter contains no new or revised regulatory commitments.
K. Cimorelli Attachment: LER 50-387(388)/2019-003-00 Copy:
NRC Region I Ms. L. H. Micewski, NRC Sr. Resident Inspector Ms. S. Goetz, NRC Project Manager Mr. M. Shields, PA DEP/BRP 12/11/2019
NRC FORM 366 (04-2018)
NRC FORM 366 (04-2018)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
LICENSEE EVENT REPORT (LER)
(See Page 2 for required number of digits/characters for each block)
(See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
- 1. Facility Name Susquehanna Steam Electric Station Unit 1
- 2. Docket Number 05000387
- 3. Page 1 OF 3
- 4. Title D Diesel Generator Inoperable due to Inadequate Post-Maintenance Test
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved Month Day Year Year Sequential Number Rev No.
Month Day Year Facility Name Susquehanna Steam Electric Station Unit 2 Docket Number 05000388 10 13 2019 2019 003 00 12 11 2019 Facility Name Docket Number 05000
- 9. Operating Mode 1
)
No Abstract (Limit to 1400 spaces, i.e., approximately 14 single-spaced typewritten lines)
On October 13, 2019, at 10:08, during performance of surveillance testing, the D Diesel Generator (DG) failed to reach the required frequency within the time specified by the acceptance criteria. Operators declared Surveillance Requirement 3.8.1.7 failed and entered Technical Specification (TS) Limiting Condition for Operation (LCO) 3.8.1, Condition B, on both Susquehanna Steam Electric Station units for the inoperable D DG. The other three DGs (A, B, and C) were verified to be OPERABLE before operators commenced a subsequent test of the D DG at 12:12, during which the D DG met all required acceptance criteria. The D DG was declared OPERABLE at 17:56 and LCO 3.8.1, Condition B, was exited for both units.
The failure to reach the required frequency within the acceptance criteria was the result of inadequate oil pressure in the D DG mechanical governor internals which was caused by an inadequate Post Maintenance Test (PMT).
The condition of the inoperable D DG was determined to have existed since September 17, 2019, and the event was determined to be reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by TS.
Due to a concurrent inoperability of the C DG, the event was also determined to be reportable in accordance with 10 CFR 50.73(a)(2)(v) as an event or condition which could have prevented the fulfillment of a safety function.
Corrective actions include procedure updates to ensure adequate PMTs are performed in the future.
There were no actual safety consequences associated with this event.
CONDITIONS PRIOR TO EVENT
Unit 1 - Mode 1, approximately 100 percent Rated Thermal Power Unit 2 - Mode 1, approximately 100 percent Rated Thermal Power There were no structures, systems, or components that were inoperable at the start of the event that contributed to the event.
EVENT DESCRIPTION
On October 13, 2019, at 10:08, operators started the D Diesel Generator (DG) [EIIS Code/Component Code:
EK/DG] in accordance with the applicable surveillance procedure. The D DG reached the required frequency at a time of 10.75 seconds, which exceeds the acceptance criteria of 10 seconds. Operators declared Surveillance Requirement (SR) 3.8.1.7 failed and entered Technical Specification (TS) Limiting Condition of Operation (LCO) 3.8.1, Condition B, on both Susquehanna Steam Electric Station (SSES) units for the inoperable D DG. The other three DGs (A, B, and C) were verified to be OPERABLE before operators commenced a subsequent test of the D DG at 12:12, during which the D DG met all required acceptance criteria. The D DG was declared operable at 17:56 and LCO 3.8.1, Condition B, was exited for both units.
Upon engine start, the engine cranked until the mechanical governor [EIIS Code/Component Code: EK/65]
lever arm was able to travel to the maximum fuel position. The mechanical governor is not designed to hold pressure during standby; since the engine is not operating, there is no pressure being generated in the mechanical governor. During the next engine start, the governor will need to build up internal pressure prior to being able to move the output lever arm back to the maximum fuel position.
On September 17, 2019, work was performed on the D DG which required draining the starting air receivers.
Upon completion of the work, a Post-Maintenance Test (PMT) was performed to verify leak-tightness and proper operation of the Emergency Service Water System supply valve [EIIS Code/Component Code: BI/V]
to the intercoolers. However, no PMT DG run was performed. Absent a PMT DG run, the DG mechanical governor was not primed with governor oil. This condition rendered the D DG inoperable due to its impact on the ability to reach the required frequency within 10 seconds.
SSES TS LCO 3.8.1 requires, in part, that four DGs are OPERABLE in MODES 1, 2, and 3. Condition B requires that an inoperable DG be restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or that each unit be shut down to MODE 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The D DG was inoperable from September 17, 2019, until it was declared OPERABLE at 17:56 on October 13, 2019. Both SSES units remained in MODE 1 during the 26-day period which exceeds the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed by Condition B. As a result, this condition was determined to be reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by TS.
The C DG was also inoperable from 07:54 on October 2, 2019, through 23:40 on October 3, due to a fuel oil leak and again from 20:14 on October 7 through 01:16 on October 8 during DG swap following repairs to the Page 3 of 3 (04-2018)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET (See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
- 3. LER NUMBER Susquehanna Steam Electric Station Unit 1 05000-387 YEAR SEQUENTIAL NUMBER REV NO.
2019 003 00 leak. SSES TS LCO 3.8.1, Condition E requires that, with two or more DGs inoperable, at least three DGs be restored to an OPERABLE status within two hours or that each unit be shut down to MODE 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The C and D DGs were concurrently inoperable for a period of approximately 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> which exceeds the 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> allowed by Condition E (the second concurrent inoperability lasted approximately five hours, which is less than the 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allotted by Conditions E and F).
Furthermore, with the C and D DG concurrently inoperable, the condition was also determined to be reportable in accordance with 10 CFR 50.73(a)(2)(v) as an event or condition which could have prevented the fulfillment of a safety function.
CAUSE OF EVENT
The cause of the slow start was an inadequate PMT after a starting air clearance resulted in depressurization of the governor oil. Work on the D DG on September 17, 2019, required control air to be taken out of service, thereby allowing pressure to bleed out of the mechanical governor until the next D DG start on October 13, 2019. Without a PMT DG run, the oil pressure was not restored in the DG mechanical governor.
ANALYSIS/SAFETY SIGNIFICANCE
The safety function of the DGs is to provide power to equipment as assumed in the safety analyses described in Chapter 15 of the Susquehanna Updated Final Safety Analysis Report. In this case, the accident analyses assume the DGs start within 25.1 seconds of a valid start signal. The start time of 10.75 seconds observed during the October 13, 2019, test is within that assumed in the accident analyses.
Therefore, the safety function of the D DG was maintained and, despite the concurrent inoperability of the C and D DGs, three DGs were always available to perform their safety function.
Based on engineering analysis, this event will not be counted as a safety system functional failure under the NRC Reactor Oversight Process Performance Indicator.
CORRECTIVE ACTIONS
Corrective actions include procedure changes to require a PMT DG run whenever the starting air system is removed from service.
PREVIOUS OCCURRENCES
LER 50-387(388)/2016-008-00, Inoperability of Diesel Generator Due to Misalignment of MOC [Mechanism-Operated Cell] Switch Contacts Due to Inadequate Post Maintenance Testing, dated May 19, 2016 LER 50-387(388)/2015-001-00, Inoperability of the B Emergency Diesel Generator due to Fuel Oil Leakage, dated April 25, 2015 LER 50-387(388)/2011-004-00, C Emergency Diesel Generator Inoperable, dated February 13, 2012
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05000387/LER-2019-001-01, Loss of Both Control Structure Chillers Due to Misaligned Breaker Stab | Loss of Both Control Structure Chillers Due to Misaligned Breaker Stab | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000387/LER-2019-001, Loss of Both Control Structure Chillers | Loss of Both Control Structure Chillers | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000388/LER-2019-001-01, Main Steam Isolation Valve Leakage | Main Steam Isolation Valve Leakage | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000387/LER-2019-002-01, 1 for Susquehanna Steam Electric Station, Unit 1, Lnoperability of C Emergency Service Water Pump | 1 for Susquehanna Steam Electric Station, Unit 1, Lnoperability of C Emergency Service Water Pump | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000387/LER-2019-002, Inoperability of C Emergency Service Water Pump | Inoperability of C Emergency Service Water Pump | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000388/LER-2019-002, Valid Actuation of the Primary Containment Isolation System Due to a Trip of Reactor Protection System Bus 2B | Valid Actuation of the Primary Containment Isolation System Due to a Trip of Reactor Protection System Bus 2B | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv)(B)(2) | 05000387/LER-2019-003, D Diesel Generator Inoperable Due to Inadequate Post-Maintenance Test | D Diesel Generator Inoperable Due to Inadequate Post-Maintenance Test | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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