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| {{#Wiki_filter:0 PPL.January 13, 2014 L-2014-013 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attn:. Document,Control Desk Washington, DzC. 20555 R~ec, St. Lucie Unit 1 Docket No. 50-335:.,ate ofEvent'.December. | | {{#Wiki_filter:0 PPL. |
| !:5,:2013. | | January 13, 2014 L-2014-013 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attn:. Document,Control Desk Washington, DzC. 20555 R~ec, |
| .3 ...Technical Specification Special Report The attached special report is being submitted pursuant to the requirements of St. Lucie Unit 1 Technical Specification 3.4.13, Action e, and Technical Specification 6.9.2. This report provides notification of an unplanned power operated relief valve (PORV) lift which mitigated a Reactor Coolant System (RCS) pressure transient that occurred on 12/15/13.The St. Lucie Unit 1 RCS was restored to normal conditions following the event on 12/15/13.Please contact us .Ithere&,ny quostions on this information. | | * St. Lucie Unit 1 Docket No. 50-335 |
| Sincerely | | :.,ate ofEvent'.December. !:5,:2013. .3 ... |
| " Eric S. Katzman,..
| | Technical Specification Special Report The attached special report is being submitted pursuant to the requirements of St. Lucie Unit 1 Technical Specification 3.4.13, Action e, and Technical Specification 6.9.2. This report provides notification of an unplanned power operated relief valve (PORV) lift which mitigated a Reactor Coolant System (RCS) pressure transient that occurred on 12/15/13. |
| Licensing Manager St. Lucie Plant Attachment ESK/lrb Florida Power & Ught Company 6501 S. Ocean Drive, Jensen Beach, FL 34957 St. Lucie Unit 1 L-2014-013 Docket No. 50-335 Attachment Page 1 of 2 I TITLE Unplanned PORV Lift During St. Lucie Unit 1 RCS Pressure Transient II. EVENT DESCRIPTION On 12/15/13, at approximately 1000, St. Lucie Unit 1 was performing Reactor Coolant System (RCS) fill and vent (commonly referred to as pump sweeps) as part of a planned activity to restore the Reactor Coolant System following draining for a Reactor Coolant Pump (RCP) seal replacement on the 1A2 RCP. During the initial RCP start (1A1 RCP) to sweep any air in the RCS into the pressurizer and /or vessel head for venting, a sudden RCS pressure increase was observed from the initial RCS pressure of 310 psia over a very short period of time, resulting in the Power Operated Relief Valve (PORV) lifting with a setpoint of 350 psia. During the transient, actions were taken by operations to reduce RCS pressure and prevent exceeding 350 psia, including attempting to reduce pressure with the pressure controller and securing the running RCP and charging pump. The PORV lifted and reseated multiple times. RCS pressure was stabilized at 200 psia and shutdown cooling was restored, which had been previously secured for the evolution. | | The St. Lucie Unit 1 RCS was restored to normal conditions following the event on 12/15/13. |
| The Limiting Condition for Operation (LCO) 3.4.13, Action e states that: "In the event either the PORVs or the RCS vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or RCS vent(s) on the transient, and any corrective action necessary to prevent recurrence." III. CAUSE OF THE EVENT The PORV lift was due to the performance of the RCS fill and vent reactor coolant pump (RCP)sweep when the steam generator (SG) tubes U-Tubes had not been drained. RCS sweeps are performed to remove gas trapped in the SG U-tubes and relocate it to points in the RCS that can be vented, specifically the reactor head and pressurizer. | | Please contact us .Ithere&,ny quostions on this information. |
| Performing a plant startup without performing RCS sweeps is not common practice, since the SG tubes are typically either drained or remain pressurized during an outage. Since the RCS was not drained below the top of the hot legs during the outage, the SG U-tubes stayed filled and the RCS had fewer air voids than would normally occur during a refueling outage where the entire RCS is drained after defueling for maintenance. | | Sincerely " |
| Consequently, upon RCP start the RCS pressure increased to the PORV lift setpoint. | | Eric S. Katzman,.. |
| '.V St. Lucie Unit 1 L-2014-013 Docket No. 50-335 Attachment Page 2 of 2 IV. ACTIONS TAKEN Short Term: Secured from RCS Fill and Vent Procedure, restored RCS pressure to normal and placed Shutdown Cooling (SDC) in service 12/15/13.Long Term: A procedure change to the RCS fill and vent procedure will be made to require an assessment prior to performing RCS fill and vent RCP sweeps based on the RCS level not going below top of hot leg and RCS head venting, and will add a caution statement concerning the effects of not performing steam generator secondary side drain, fills and cooling. The Unit 2 procedure will be used as a reference for the changes, and the procedures will be aligned to be similar between the units for operator human performance factors. These actions will be tracked and documented in the site corrective action program.V. SCHEDULE FOR RESTORING SYSTEM The St. Lucie Unit 1 RCS was restored to normal conditions following the event on 12/15/13.}} | | Licensing Manager St. Lucie Plant Attachment ESK/lrb Florida Power & Ught Company 6501 S. Ocean Drive, Jensen Beach, FL 34957 |
| | |
| | St. Lucie Unit 1 L-2014-013 Docket No. 50-335 Attachment Page 1 of 2 I TITLE Unplanned PORV Lift During St. Lucie Unit 1 RCS Pressure Transient II. EVENT DESCRIPTION On 12/15/13, at approximately 1000, St. Lucie Unit 1 was performing Reactor Coolant System (RCS) fill and vent (commonly referred to as pump sweeps) as part of a planned activity to restore the Reactor Coolant System following draining for a Reactor Coolant Pump (RCP) seal replacement on the 1A2 RCP. During the initial RCP start (1A1 RCP) to sweep any air in the RCS into the pressurizer and /or vessel head for venting, a sudden RCS pressure increase was observed from the initial RCS pressure of 310 psia over a very short period of time, resulting in the Power Operated Relief Valve (PORV) lifting with a setpoint of 350 psia. During the transient, actions were taken by operations to reduce RCS pressure and prevent exceeding 350 psia, including attempting to reduce pressure with the pressure controller and securing the running RCP and charging pump. The PORV lifted and reseated multiple times. RCS pressure was stabilized at 200 psia and shutdown cooling was restored, which had been previously secured for the evolution. |
| | The Limiting Condition for Operation (LCO) 3.4.13, Action e states that: |
| | "In the event either the PORVs or the RCS vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or RCS vent(s) on the transient, and any corrective action necessary to prevent recurrence." |
| | III. CAUSE OF THE EVENT The PORV lift was due to the performance of the RCS fill and vent reactor coolant pump (RCP) sweep when the steam generator (SG) tubes U-Tubes had not been drained. RCS sweeps are performed to remove gas trapped in the SG U-tubes and relocate it to points in the RCS that can be vented, specifically the reactor head and pressurizer. Performing a plant startup without performing RCS sweeps is not common practice, since the SG tubes are typically either drained or remain pressurized during an outage. Since the RCS was not drained below the top of the hot legs during the outage, the SG U-tubes stayed filled and the RCS had fewer air voids than would normally occur during a refueling outage where the entire RCS is drained after defueling for maintenance. Consequently, upon RCP start the RCS pressure increased to the PORV lift setpoint. |
| | |
| | '.V St. Lucie Unit 1 L-2014-013 Docket No. 50-335 Attachment Page 2 of 2 IV. ACTIONS TAKEN Short Term: |
| | Secured from RCS Fill and Vent Procedure, restored RCS pressure to normal and placed Shutdown Cooling (SDC) in service 12/15/13. |
| | Long Term: |
| | A procedure change to the RCS fill and vent procedure will be made to require an assessment prior to performing RCS fill and vent RCP sweeps based on the RCS level not going below top of hot leg and RCS head venting, and will add a caution statement concerning the effects of not performing steam generator secondary side drain, fills and cooling. The Unit 2 procedure will be used as a reference for the changes, and the procedures will be aligned to be similar between the units for operator human performance factors. These actions will be tracked and documented in the site corrective action program. |
| | V. SCHEDULE FOR RESTORING SYSTEM The St. Lucie Unit 1 RCS was restored to normal conditions following the event on 12/15/13.}} |
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Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023 Report of 10 CFR 50.59 Plant Changes L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023 Periodic Update of Population Data within 10 and 50 Miles of the Plant L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023 2022 Annual Radioactive Effluent Release Report L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023 2022 Annual Operating Report L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023 Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022 L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022 Unusual or Important Environmental Event - Turtle Mortality L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 2024-01-08
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARL-2019-051, Unusual or Important Environmental Event - Turtle Mortalities - February 4, 2019 and February 11, 20192019-02-27027 February 2019 Unusual or Important Environmental Event - Turtle Mortalities - February 4, 2019 and February 11, 2019 L-2018-063, CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications2018-03-26026 March 2018 CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications L-2018-005, Submittal of Emergency Core Cooling 30-Day Report2018-01-12012 January 2018 Submittal of Emergency Core Cooling 30-Day Report L-2014-248, Technical Specification Special Report Radiation Monitor Inoperable Greater than 72 Hours2014-07-28028 July 2014 Technical Specification Special Report Radiation Monitor Inoperable Greater than 72 Hours L-2014-134, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report2014-05-12012 May 2014 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report L-2014-013, Submittal of Technical Specification Special Report2014-01-13013 January 2014 Submittal of Technical Specification Special Report L-2011-345, Technical Specification Special Report, Radiation Monitor Inoperable Greater than 72 Hours2013-12-23023 December 2013 Technical Specification Special Report, Radiation Monitor Inoperable Greater than 72 Hours L-2013-291, Submittal of Technical Specification Special Report Radiation Monitor Inoperable Greater than 72 Hours2013-10-0101 October 2013 Submittal of Technical Specification Special Report Radiation Monitor Inoperable Greater than 72 Hours L-2013-217, Revised Technical Specification Special Report, Failure of Channel a Reactor Vessel Level Monitoring System (Rvlms) on June 4, 20132013-07-0303 July 2013 Revised Technical Specification Special Report, Failure of Channel a Reactor Vessel Level Monitoring System (Rvlms) on June 4, 2013 L-2013-215, Technical Specification Special Report - Failure of Channel a Reactor Vessel Level Monitoring System (Rvlms)2013-06-0404 June 2013 Technical Specification Special Report - Failure of Channel a Reactor Vessel Level Monitoring System (Rvlms) L-2010-139, LER, St. Lucie, Unit 1, Submittal of Technical Specification Special Report, Inoperable Containment Sump Wide Range Level Channel B2010-06-28028 June 2010 LER, St. Lucie, Unit 1, Submittal of Technical Specification Special Report, Inoperable Containment Sump Wide Range Level Channel B L-2009-289, Submittal of Technical Specification Special Report Reactor Vessel Level Monitoring System a Channel Level Probe (Hjtc) Out of Service2009-12-14014 December 2009 Submittal of Technical Specification Special Report Reactor Vessel Level Monitoring System a Channel Level Probe (Hjtc) Out of Service L-2009-250, Date of Event: October 6, 2009, Technical Specification Special Report, Sodium Hypochlorite Spill Greater than 100 Pounds2009-11-0505 November 2009 Date of Event: October 6, 2009, Technical Specification Special Report, Sodium Hypochlorite Spill Greater than 100 Pounds L-2009-097, LER for St. Lucie, Unit 2 Regarding Technical Specification Special Report, Radiation Monitor Inoperable Greater than 72 Hours2009-04-20020 April 2009 LER for St. Lucie, Unit 2 Regarding Technical Specification Special Report, Radiation Monitor Inoperable Greater than 72 Hours L-2007-166, Technical Specification Special Report, Radiation Monitoring Inoperable Greater than 72 Hours2007-10-18018 October 2007 Technical Specification Special Report, Radiation Monitoring Inoperable Greater than 72 Hours L-2007-100, Technical Specification Special Report, Pressurizer Power Operate Relief Valve (PORV)2007-06-13013 June 2007 Technical Specification Special Report, Pressurizer Power Operate Relief Valve (PORV) L-2004-291, Technical Specification Special Report on Inoperable Containment Sump Wide Range Level Channel B2004-12-22022 December 2004 Technical Specification Special Report on Inoperable Containment Sump Wide Range Level Channel B L-2004-052, Technical Specification Special Report Regarding Radwaste Building Exhaust System Plant Ventilation Exhaust Monitor - Out-of-Service2004-02-23023 February 2004 Technical Specification Special Report Regarding Radwaste Building Exhaust System Plant Ventilation Exhaust Monitor - Out-of-Service L-2003-196, Special Report Re Inoperable Loose Parts Monitoring Channel, Per Requirements of Updated Final Safety Analyses Report Section 13.7.4.1 Action a2003-07-23023 July 2003 Special Report Re Inoperable Loose Parts Monitoring Channel, Per Requirements of Updated Final Safety Analyses Report Section 13.7.4.1 Action a ML18113A2701977-02-25025 February 1977 Forwards Non-Routine Radioactive Effluent Report ML18113A2861977-01-20020 January 1977 Forwards Non-Routine Environmental Operating Report Titled Impingement of Aquatic Organisms ML18088A9381976-07-29029 July 1976 Letter Attaching Reportable Occurrence 335-B-76-03 St. Lucie Unit 1 Date of Occurrence: July 1, 1976 Volume Control Tank. L-76-247, Letter Attaching Reportable Occurrence No. 335-B-76-02 Failure to Determine Condenser Delta T.1976-07-0707 July 1976 Letter Attaching Reportable Occurrence No. 335-B-76-02 Failure to Determine Condenser Delta T. 2019-02-27
[Table view] |
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January 13, 2014 L-2014-013 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attn:. Document,Control Desk Washington, DzC. 20555 R~ec,
- St. Lucie Unit 1 Docket No. 50-335
- .,ate ofEvent'.December. !:5,:2013. .3 ...
Technical Specification Special Report The attached special report is being submitted pursuant to the requirements of St. Lucie Unit 1 Technical Specification 3.4.13, Action e, and Technical Specification 6.9.2. This report provides notification of an unplanned power operated relief valve (PORV) lift which mitigated a Reactor Coolant System (RCS) pressure transient that occurred on 12/15/13.
The St. Lucie Unit 1 RCS was restored to normal conditions following the event on 12/15/13.
Please contact us .Ithere&,ny quostions on this information.
Sincerely "
Eric S. Katzman,..
Licensing Manager St. Lucie Plant Attachment ESK/lrb Florida Power & Ught Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
St. Lucie Unit 1 L-2014-013 Docket No. 50-335 Attachment Page 1 of 2 I TITLE Unplanned PORV Lift During St. Lucie Unit 1 RCS Pressure Transient II. EVENT DESCRIPTION On 12/15/13, at approximately 1000, St. Lucie Unit 1 was performing Reactor Coolant System (RCS) fill and vent (commonly referred to as pump sweeps) as part of a planned activity to restore the Reactor Coolant System following draining for a Reactor Coolant Pump (RCP) seal replacement on the 1A2 RCP. During the initial RCP start (1A1 RCP) to sweep any air in the RCS into the pressurizer and /or vessel head for venting, a sudden RCS pressure increase was observed from the initial RCS pressure of 310 psia over a very short period of time, resulting in the Power Operated Relief Valve (PORV) lifting with a setpoint of 350 psia. During the transient, actions were taken by operations to reduce RCS pressure and prevent exceeding 350 psia, including attempting to reduce pressure with the pressure controller and securing the running RCP and charging pump. The PORV lifted and reseated multiple times. RCS pressure was stabilized at 200 psia and shutdown cooling was restored, which had been previously secured for the evolution.
The Limiting Condition for Operation (LCO) 3.4.13, Action e states that:
"In the event either the PORVs or the RCS vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or RCS vent(s) on the transient, and any corrective action necessary to prevent recurrence."
III. CAUSE OF THE EVENT The PORV lift was due to the performance of the RCS fill and vent reactor coolant pump (RCP) sweep when the steam generator (SG) tubes U-Tubes had not been drained. RCS sweeps are performed to remove gas trapped in the SG U-tubes and relocate it to points in the RCS that can be vented, specifically the reactor head and pressurizer. Performing a plant startup without performing RCS sweeps is not common practice, since the SG tubes are typically either drained or remain pressurized during an outage. Since the RCS was not drained below the top of the hot legs during the outage, the SG U-tubes stayed filled and the RCS had fewer air voids than would normally occur during a refueling outage where the entire RCS is drained after defueling for maintenance. Consequently, upon RCP start the RCS pressure increased to the PORV lift setpoint.
'.V St. Lucie Unit 1 L-2014-013 Docket No. 50-335 Attachment Page 2 of 2 IV. ACTIONS TAKEN Short Term:
Secured from RCS Fill and Vent Procedure, restored RCS pressure to normal and placed Shutdown Cooling (SDC) in service 12/15/13.
Long Term:
A procedure change to the RCS fill and vent procedure will be made to require an assessment prior to performing RCS fill and vent RCP sweeps based on the RCS level not going below top of hot leg and RCS head venting, and will add a caution statement concerning the effects of not performing steam generator secondary side drain, fills and cooling. The Unit 2 procedure will be used as a reference for the changes, and the procedures will be aligned to be similar between the units for operator human performance factors. These actions will be tracked and documented in the site corrective action program.
V. SCHEDULE FOR RESTORING SYSTEM The St. Lucie Unit 1 RCS was restored to normal conditions following the event on 12/15/13.