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Category:Letter
MONTHYEARIR 05000335/20250102024-10-21021 October 2024 Notification of St. Lucie Plant Units 1 & 2 Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000335/2025010 and 05000389/2025010 L-2024-085, Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results2024-10-15015 October 2024 Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results L-2024-165, Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made2024-10-14014 October 2024 Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) ML24255A3092024-09-30030 September 2024 SLRA - Revised SE Letter L-2024-155, Subsequent License Renewal Application, Third Annual Update2024-09-27027 September 2024 Subsequent License Renewal Application, Third Annual Update L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes 05000335/LER-2024-001, Unplanned Reactor Scram2024-09-25025 September 2024 Unplanned Reactor Scram IR 05000335/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000335/2024011 and 05000389/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 552024-09-0909 September 2024 Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55 IR 05000335/20240052024-08-22022 August 2024 Updated Inspection Plan for St. Lucie, Units 1 & 2 - Report 05000335/2024005 and 05000389/2024005 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal IR 05000335/20240022024-08-13013 August 2024 Integrated Inspection Report 05000335-2024002 and 05000389-2024002 L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review 05000389/LER-2024-003, Unplanned Reactor Scram2024-08-0505 August 2024 Unplanned Reactor Scram L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-117, Safety Injection Tank Vent Through Wall Leakage2024-07-11011 July 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review ML24172A1562024-06-27027 June 2024 Relief Request - PSL2-I5-RR-01 Proposed Alternative to Amse Code XI Code Examination Requirements - System Leakage Test of Reactor Pressure Vessel Bottom Head and Class 1 and 2 Piping in Covered Trenches L-2024-104, Response to Request for Additional Information, St. Luce 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 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce 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 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports IR 05000335/20244012024-06-0303 June 2024 Security Baseline Inspection Report 05000335/2024401 and 05000389/2024401 ML24135A0642024-05-17017 May 2024 Correction Letter - Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation IR 05000335/20240012024-05-10010 May 2024 Integrated Inspection Report 05000335/2024001 and 05000389/2024001 ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report ML24108A0632024-04-18018 April 2024 – Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report ML24093A2612024-04-0202 April 2024 – Investigation Summary, Office of Investigations Case Number 2-2023-005 L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes 2024-09-09
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000335/LER-2024-001, Unplanned Reactor Scram2024-09-25025 September 2024 Unplanned Reactor Scram 05000389/LER-2024-003, Unplanned Reactor Scram2024-08-0505 August 2024 Unplanned Reactor Scram L-2024-117, Safety Injection Tank Vent Through Wall Leakage2024-07-11011 July 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-027, Safety Injection Tank Vent Through Wall Leakage2024-02-29029 February 2024 Safety Injection Tank Vent Through Wall Leakage 05000335/LER-2016-0032017-08-15015 August 2017 Generator Lockout Relay Actuation During Power Ascension Results in Reactor Trip, LER 16-003-01 for St. Lucie, Unit 1, Regarding Generator Lockout Relay Actuation During Power Ascension Results in Reactor Trip 05000389/LER-2017-0012017-04-27027 April 2017 Delay in Initiating Immediate Technical Specification Required Action During Fuel Movements, LER 17-001-00 for St. Lucie, Unit 2 Regarding Delay in Initiating Immediate Technical Specification Required Action During Fuel Movements 05000335/LER-2016-0012016-07-29029 July 2016 Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical Specifications, LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical.... L-2016-152, LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Te2016-07-29029 July 2016 LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Tech L-2010-255, Letter St. Lucie, Unit 2, Technical Specification Special Report Inoperable Reactor Water Level Monitoring System Channel Failed2010-11-0101 November 2010 Letter St. Lucie, Unit 2, Technical Specification Special Report Inoperable Reactor Water Level Monitoring System Channel Failed ML0414104442004-05-18018 May 2004 Technical Specification Special Report Inoperable Reactor Water Level Monitoring System Channel ML18127A6421978-09-22022 September 1978 LER 1978-032-00 for St. Lucie Unit 1, on 08/30/78 Concerning Daily Calibration of Nuc & ^T PWR (Technical Specification 4.3.1.1.1) Was Inadvertently Missed During One Surveillance Interval Encompassing Short Maintenance Outage & Subsequent ML18127A6431978-09-18018 September 1978 LER 1978-031-00 for St. Lucie Unit 1, on 08/16/78 Concerning the Ginca Code Operator Used Incorrect Flux Inputs in Arriving at the Incore Setpoints ML18127A6461978-09-0808 September 1978 LER 1978-030-00 for St. Lucie Unit 1, on 08/10/78 Concerning. the Surveillance Requirement of Specification 4.4.8 Which Requires an Isotopic Analysis for Iodine in the Primary Coolant, Was Inadvertently Missed ML18127A6471978-08-30030 August 1978 LER 1978-025-00 for St. Lucie Unit 1, on 07/31/78 Concerning Containment Vacuum Relief Valve (FCV-25-8) Instrument Air Supply Low Pressure Alarm Was Received. Cause Was Diaphragm Leak in Solenoid Valve Which Controls Instrument Air Supply ML18127A6481978-08-28028 August 1978 LER 1978-026-00 for St. Lucie Unit 1, on 07/30/78 Concerning During PWR Operation Digital Data Processing System Malfunctioned Resulting in Loss of CEA Backup Position Indication & Incore Flux Detector System Used to Monitor Flux D ML18127A6491978-08-25025 August 1978 LER 1978-025-00 for St. Lucie Unit 1, on 07/28/78 Concerning Notification by Applicant'S Vendor of Potential Problem with Certain Motor Operated Valves ML18127A6501978-08-0808 August 1978 LER 1978-011-01 for St. Lucie Unit 1, Update Concerning When Upper Guide Structure Was Removed (Refueling Shutdown), 3 (of 45) Incore Instrument Thimbles Remained in the Core ML18127A6511978-08-0707 August 1978 LER 1978-025-00 for St. Lucie Unit 1, on 07/24/78 Concerning an Error in the Analysis for the Cask Drop Accident Which Makes the Technical Specification 3.9.14 Non-Conservative ML18127A6521978-07-24024 July 1978 LER 1978-024-00 for St. Lucie Unit 1, on 06/25/78 Concerning During Plant Startup from a Short Maintenance, Dose Equivalent Iodine Exceeded Technical Specification 3.4.8.A Limit of 1.0 Uci/Gram Dose Equivalent ML18127A6531978-07-14014 July 1978 LER 1978-010-00 for St. Lucie Unit 1, One Channel of Steam Generator Low Pressure Measurement for Main Steam Isolation Signal Failed Requiring Action in Accordance with Technical Specification 3. 3. 2. I. B ML18127A6551978-07-13013 July 1978 LER 1978-022-00 for St. Lucie Unit 1, on 06/15/78 Concerning During PWR Operation, the Digital Data Processing System Malfunctioned Due to Malfunctioning Multiplexer Card ML18127A6541978-07-13013 July 1978 LER 1978-023-00 for St. Lucie Unit 1, on 05/15/78 Concerning During Testing Humidity Control Heaters on the Shield Bldg Ventilation System (B Train) Tripped on High Temperatures Due to High Temperature Caused by Low Flow ML18127A6561978-07-0808 July 1978 LER 1978-021-00 for St. Lucie Unit 1, on 06/08/78 Concerning During PWR Ascension Testing Following Refueling Outage CEA #65 Dropped Four Times Due to Failure of One or More of Its Coil PWR Programmer Timing Module, Integral Timer ML18127A6581978-07-0707 July 1978 LER 1978-020-00 for St. Lucie Unit 1, on 06/07/78 Concerning Pwer Ascension Physics Testing Following a Refueling Outage, CEA #65 Dropped ML18127A6601978-06-28028 June 1978 LER 1978-019-00 for St. Lucie Unit 1, on 05/30/78 Concerning During Special Low Pier Feedwater Control System Test a 15% Feedwater Bypass Control Valve Inadvertently Opened Fully Causing Excessive Cooling of 1A Steam Generator ML18127A6611978-06-26026 June 1978 LER 1978-018-00 for St. Lucie Unit 1, on 05/26/78 Concerning CEA #19 Dropped for No Apparent Reason ML18127A6621978-06-13013 June 1978 LER 1978-017-00 for St. Lucie Unit 1, on 05/14/78 Concerning Improper Switching at Pratt & Whitney Substation Combined with Incorrect Wiring of Protective Relays at Midway Substation Led to Deenergization of Midway Substation Resulting in L ML18127A6641978-06-0909 June 1978 LER 1978-016-00 for St. Lucie Unit 1, on 05/26/78 Concerning Containment Pressure-High Trip Setpoint (Table 2.2-1) Appeared to Be in Error During the Refueling Outage ML18127A6651978-05-23023 May 1978 LER 1978-015-00 for St. Lucie Unit 1, on 04/23/78 Concerning Operator Blew Down 1B Bamt Level Instrument to Prevent Sensing Line Blockage, Causing Instrument to Fail High ML18127A6681978-04-28028 April 1978 LER 1978-012-00 for St. Lucie Unit 1, on 04/16/78 Concerning Eddy Current Testing Performed on Fuel Assembly CEA Guide Tubes at Unit 1 Showed Near in Guide Tubes Where Tips of Fully Withdrawn CEAs Were Located ML18127A6691978-04-28028 April 1978 LER 1978-011-00 for St. Lucie Unit 1, When Upper Guide Structure Was Removed (Refueling Shutdown), 3 (of 45) Incore Instrument Thimbles Remained in the Core ML18127A6701978-04-27027 April 1978 LER 1978-013-00 for St. Lucie Unit 1, on 03/28/78 Concerning During Shutdown for Refueling, Dose Equivalent Iodine Exceeded Technical Specification 3.4.8 ML18127A6711978-04-25025 April 1978 LER 1978-010-00 for St. Lucie Unit 1, One Channel of Steam Generator Low Pressure Measurement for the Main Steam Isolation Signal Failed Requiring Action in Accordance with Technical Specification 3.3.2.1.B ML18127A6731978-03-30030 March 1978 LER 1978-009-00 for St. Lucie Unit 1, During PWR Operation Digital Data Processing System Malfunctioned. Apparent Momentary Memory Failure Caused Ddps to Halt ML18127A6741978-03-24024 March 1978 LER 1978-008-00 for St. Lucie Unit 1, Due to an Administrative Error During a Procedure Revision Instructions for Documenting Surveillance of Volume in Diesel Generator Engine Mounted Fuel Tanks Were Omitted ML18127A6791978-02-17017 February 1978 LER 1978-007-00 for St. Lucie Unit 1, Technical Specification 4.3.1.1.3 RTD Response Time ML18127A6781978-02-17017 February 1978 LER 1978-007-00 for St. Lucie Unit 1, Technical Specification 4.3.1.1.3 RTD Response Time ML18144A8051977-12-15015 December 1977 12/15/1977 Memo Reportable Occurrence 335-77-50 ML18110A8681977-10-24024 October 1977 LER 1977-335-39 for St. Lucie, Unit 1 on Refueling Water Tank Piping ML18110A8691977-09-26026 September 1977 LER 1977-335-35 for St. Lucie, Unit 1 on Intake Cooling Water Pump ML18110A8711977-09-15015 September 1977 LER 1977-335-34 for St. Lucie, Unit 1 on Containment Spray Header Valve ML18110A8731977-09-13013 September 1977 LER 1977-335-31 for St. Lucie, Unit 1 on Repair of Leaking Shaft Mechanical Seal of Component Cooling Water Pump ML18110A8741977-09-0909 September 1977 LER 1977-335-33 for St. Lucie, Unit 1 on Steam Driven Auxiliary Feedwater Pump ML18110A8751977-08-31031 August 1977 LER 1977-335-32 for St. Lucie, Unit 1 on Refueling Water Tank Level Setpoint Drift ML18110A8761977-07-14014 July 1977 LER 1977-335-30 for St. Lucie, Unit 1 on Detector Calibration ML18110A8771977-07-0808 July 1977 LER 1977-335-03 for St. Lucie, Unit 1 on Diesel Generator 1A, Update Report No. 1 ML18110A8781977-07-0808 July 1977 LER 1977-335-28 for St. Lucie, Unit 1 on Containment Isolation Valve ML18110A8791977-06-27027 June 1977 LER 1977-335-27 for St. Lucie, Unit 1 on Dropped Control Element Assembly No. 39 Initiating a Turbine Runback ML18110A8801977-06-16016 June 1977 LER 1977-335-26 for St. Lucie, Unit 1 on Off-Site Power ML18110A8821977-06-0303 June 1977 LER 1977-335-25 for St. Lucie, Unit 1 Setpoint of Bistable Trip Unit for Steam Generator Pressure Found Inadequately Conservative 2024-09-25
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FFPL.March 10, 2014L-2012-066 10 CFR 50.73U. S. Nuclear Regulatory Commission Attn: Document Control DeskWashington, D.C. 20555Re: St. Lucie Unit 1Docket No. 50-335Reportable Event: 2014-001Date of Event: January 9, 2014Internal RAB Flooding During Heavy Rain Due to Degraded Conduits Lacking InternalFlood BarriersThe attached Licensee Event Report 2014-001 is being submitted pursuant to the requirements of10 CFR 50.73 to provide notification of the subject event.Respectfully, Site Vice President St. Lucie PlantJJ/KWFAttachment Florida Power & Light Company6501 S. Ocean Drive, Jensen Beach, FL 34957 NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES:
01/31/2017 (02-2014)
Estimated burden per response to comply with this mandatory collection request:
80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />... Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information CollectionsLICENSEE EVENT REPORT (LER) Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or byLI E E T Rinternet e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and(See Page 2 for required number of Regulatory
- Affairs, NEOB-10202, (3150-0104),
Office of Management and Budget, Washington, DCfor each block) 20503. It a means used to impose an information collection does not display a cun-ently valid OMBdigits/characters control number, the NRC may not conduct or sponsor, and a person is not required to respond to,the intormation collechon.
- 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGESt. Lucie Unit 1 05000335 1 OF4. TITLEInternal RAB Flooding During Heavy Rain Due to Degraded Conduits Lacking Internal Flood Barriers5. EVENT DATE 6. LER NUMBER 7. REPORT DATE 8. OTHER FACILITIES INVOLVEDFACILITY NAME DOCKET NUMBERMONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR 05000FACILITY NAME DOCKET NUMBER1 9 2014 2014- 001 -0 3 10 2014 050009. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)D1 20.2201(b)
F1 20.2203(a)(3)(i)
D 50.73(a)(2)(i)(C)
D 50.73(a)(2)(vii)
[] 20.2201(d)
F] 20.2203(a)(3)(ii)
[] 50.73(a)(2)(ii)(A)
[] 50.73(a)(2)(viii)(A)
D 20.2203(a)(1)
[ 20.2203(a)(4)
" 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
_ _ 20.2203(a)(2)(i)
[ 50.36(c)(1)(i)(A)
[ 50.73(a)(2)(iii)
[ 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL F1 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
[] 50.73(a)(2)(iv)(A)
F1 50.73(a)(2)(x)
ED 20.2203(a)(2)(iii)
[ 50.36(c)(2)
[] 50.73(a)(2)(v)(A)
D 73.71(a)(4)
El 20.2203(a)(2)(iv)
[ 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(B)
D 73.71(a)(5) 100E] 20.2203(a)(2)(v)
[ 50.73(a)(2)(i)(A)
[ 50.73(a)(2)(v)(C)
[ OTHERr5 5Specify in Abstract below or in______________
20.2203(a)(2)(vi) 50.73(a)(2)(t)(B)
- 5) _ NRC Form 366A12. LICENSEE CONTACT FOR THIS LERLICENSEE CONTACT TELEPHONE NUMBER (include Area Code)K. W. Frehafer, Licensing Engineer 1 (772) 467-774813. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORTCAUSE SYSTEM COMPONENT MANU- REPORTABLE CAUSE SYSTEM OPNN FACTURE R TEPORTBLFACTURER TO EP[X 1 FACTURER TO EPIXB N/A N/A N/A N/A14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEARSUBMISSION 5] YES (Ifyes complete
- 15. EXPECTED SUBMISSION DAT"E) [ NO DATE 5 2014ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)On January 9, 2014, the St. Lucie site was experiencing heavy rainfall.
Storm drain blockage caused water to backupwithin the emergency core cooling system (ECCS) pipe tunnel. Water entered the reactor auxiliary building (RAB)through two degraded conduits that lacked internal flood barriers.
At 1803 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.860415e-4 months <br /> St. Lucie declared an Unusual Event.(UE) due to storm drain capacity degradation.
The UE was terminated at 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> on January 10, 2014, when thestorm had passed and the drains had been cleared.The extent of condition identified four additional conduits that lacked the required internal flood barriers.
All the affectedconduits subsequently had qualified internal water seals installed.
During this event there was no loss of any safety related accident mitigation or safe shutdown equipment.
The safetysignificance of this event is being evaluated by FPL. This LER will be revised to reflect the results.NRC FORM 366 (02-2014)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES:
01/31/2017 (02-2014)
Estimated burden per response to comply with this mandatory collection request:
80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.... " 'Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections
",j .Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or byLICENSEE EVENT REPORT (LER) intemet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of nformation and Regulatory
- Affairs, NEOB-10202, (3150-0104),
Office of Management and Budget,CONTINUATION SHEET Washington, DC 20503. If a means used to impose an information collection does not display acurrently valid OMB control number, the NRC may not conduct or sponsor, and a person is notrequired to respond to, the information collection.
- 1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGEYEAR SEQUENTIAL REVIYEAR NUMBER NO.St. Lucie Unit 1 05000335 j 2 OF 32014 001 -0NARRATIVE Description of the EventOn January 9, 2014, St. Lucie Unit 1 was in Mode 1 operation at 100 percent reactor power. The St. Lucie sitewas experiencing heavy rainfall.
In the early afternoon the site storm drain system was challenged as the stormwater basins started to back up.At -1610 hours, operators reported that water was backing up through the -0.5 feet elevation floor drains in thereactor auxiliary building (RAB) and into the emergency core cooling system (ECCS) pump room sumps atthe -10.0 feet elevation.
The water was observed entering the RAB through an electrical junction box which wasbelow the elevation for which the RAB flood protection was designed.
At -1620 hours, the control room received the B Safeguards Pump Room Sump Level High/High-High alarms.At -1628 hours the operators entered procedure 1-AOP-24.01, "RAB Flooding,"
and immediately closed theECCS sump isolation valves to preclude flooding of the ECCS pump room. However, the water level in the RAB-0.5 feet elevation continued to rise.At -1635 hours, after deliberation between the field operators and the Control Room, the operators decided tocontrol the RAB flooding by cycling the ECCS sump isolation valves to allow batch removal of RAB water via theECCS sump pumps.At -1732 hours, a higher capacity temporary pump at the yard sump was used to reduce the rate of water entryinto the RAB.At -1803 hours, an Unusual Event (UE) was declared as the significant rainfall exceeded the site's storm drainsystem capacity.
The UE was terminated at -0001 hours on January 10, 2014, after the significant rains subsided and the stormdrain were observed draining site water accumulation.
All safety related accident mitigation and safe shutdown equipment remained operable prior to, during, and afterthe event.Cause of the EventThe cause of the RAB flooding was due to' legacy installation issues with two non-safety electrical conduits[EIIS:CND]
in the ECCS pipe tunnel that lacked the required internal flood barriers.
Degradation of the conduitsprovided a water entry path into the R.AB. The extent of condition identified four more conduits with the samelegacy installation issue, for a total of six conduits without internal flood seals. Qualified flood seals have nowbeen installed where these conduits terminate in the building in order to restore the RAB to a waterproofed condition.
The Organizational and Programmatic portion of the root cause evaluation is on-going at the time theLER was submitted.
This LER will be supplemented once the evaluation is completed, approximately 60 daysfrom the date of this LER.The direct cause of the storm water basin back up that allowed the ECCS pipe tunnel to flood was blockage ofthe piping that connects east storm water basin to the overflow basin. The blockage that contributed to thestorm drain system flow restriction has been removed.NRC FORM 366A (02-2014)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (02-2014)
LICENSEE EVENT REPORT (LER)CONTINUATION SHEET1. FACILITY NAME 2. DOCKET 6. LER NUMBER 3. PAGEY SEQUENTIAL REVA NUMBER NO.St. Lucie Unit 1 05000335 YA3 OF 32014 -001 0NARRATIVE Analysis of the EventThis condition is reportable in accordance with 10 CFR 50.73(a)(2)(ii)(B) as an event or condition that resultedin the nuclear power plant being in an unanalyzed condition that significantly degraded plant safety. Althoughthis event did not result in any loss of function, postulated external flooding events could result in RAB waterlevels exceeding the analyzed RAB internal flooding event, as a result of the discovery of these missing conduitseals. This is contrary to design as it is assumed that design features seal the RAB below the +17.2 feetelevation from water sources external to the RAB.The site is comprised of an east and a west drainage system that outflows to the east and west storm waterbasins, which in turn flow to the southwest overflow basin and to the southeast overflow basin through a 36-inchinterconnection.
The southeast overflow basin has a high level outflow valve that can be opened duringexcessive rainfall events. Due to flow blockage from the east storm water basin to the overflow basins, thesevere rainfall caused the water level of the east storm water basin to rise above its banks and flood the plantarea west of the G1 and G2 warehouses.
Once the water level exceeded the elevation of the Unit 1 component cooling water (CCW) building floor (elevation
+12 feet) the building no longer drained and allowed the backflowto flood the adjacent ECCS pipe tunnel and yard sump. The degraded conduit within the ECCS pipe tunnel,along with the lack of internal conduit flood barriers in the RAB side, provided a direct path for water to enter theRAB.The water intrusion into the RAB continued until the storm drain blockage was corrected and the remaining volume of water in the ECCS pipe tunnel drained into the building.
Operators took action to remove the floodwater, by cycling the ECCS room sump isolation valves in order to utilize the installed sump pumps.As previously noted, during this event there was no loss of safety related accident mitigation or safe shutdownequipment.
Florida Power & Light (FPL) is currently evaluating various external flooding scenarios to determine if any postulated conditions could have resulted in, the loss of safety related accident mitigation or safeshutdown equipment.
Once this evaluation is complete, FPL will provide a supplement to this LER.Safety Significance The safety significance of the RAB flood protection bypass provided by the degraded conduits is currently beingassessed by FPL, and will be provided in a supplement to this LER.Corrective Actions1. All conduits identified as lacking internal flood barriers during the extent of condition reviews were providedwith qualified seals.Failed Component(s)
Various non-safety conduitsSimilar EventsOn December 27, 2012, FPL reported degraded penetration seals within electrical manways that bypassed St.Lucie Unit 1 RAB external flood protection features in LER 50-335/2012-010.
This original construction legacyissue was discovered during the Fukushima 50.54(f) flooding walkdowns that were performed as part of theNRC-approved NEI walkdown scope. Unit 2 was also identified to have unsealed conduit penetrations, but wasnot included in that LER as a flooding evaluation performed at the time concluded Unit 2 was bounded by itsinternal flooding analysis.
Once complete, the insights developed from the detailed St. Lucie flooding modelsbeing developed for the recent event will be applied to the 2012 LER condition.
If any conditions are identified that exceed previous analysis
- results, those conditions will be reevaluated for impact on equipment operability and reportability.