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| | LER year = 2024 | | | LER year = 2024 |
| | LER number = 3 | | | LER number = 3 |
| | LER revision = | | | LER revision = 0 |
| | Event date = | | | Event date = |
| | Report date = | | | Report date = |
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| {{#Wiki_filter:August 5, 2024 L-2024-115 10 CFR 50.73 | | {{#Wiki_filter:August 5, 2024 L-2024-115 10 CFR 50.73 |
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| U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 | | U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 |
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| Re: St. Lucie Unit 2 Docket No. 50-389 Reportable Event: 2024-03-00 Date of Event: June 4, 2024 | | Re: St. Lucie Unit 2 Docket No. 50-389 Reportable Event: 2024-03-00 Date of Event: June 4, 2024 |
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| Unplanned Reactor Scram | | Unplanned Reactor Scram |
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| The attached Licensee Event Report, 2024-03, is being submitted pursuant to the requirements of 10 CFR 50 .73 to provide notification of the subject event. | | The attached Licensee Event Report, 2024-03, is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event. |
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| Should you have any questions regarding this submission, please contact Mr. Kenneth Mack, Senior Manager Licensing and Reg Compliance - Nuclear Fleet, at 561-904-3635. | | Should you have any questions regarding this submission, please contact Mr. Kenneth Mack, Senior Manager Licensing and Reg Compliance - Nuclear Fleet, at 561-904-3635. |
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| This letter contains no new or modified regulatory commitments. | | This letter contains no new or modified regulatory commitments. |
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| Sincerely, | | Sincerely, |
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| Paul Rasmus General Manager - Regulatory Affairs - Nuclear Fleet Florida Power & Light Company | | Paul Rasmus General Manager - Regulatory Affairs - Nuclear Fleet Florida Power & Light Company |
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| Attachment | | Attachment |
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| cc: St. Lucie NRC Senior Resident Inspector St. Lucie Station NRC Program Manager | | cc: St. Lucie NRC Senior Resident Inspector St. Lucie Station NRC Program Manager |
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| Florida Power & Light Company | | Florida Power & Light Company |
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| 6501 S. Oc ea n Driv e, Jen se n Be ac h, FL 34957 NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 04/30/2027 (04-02-2024) Estimated burden per re sponse to comply with this mand atory collection reque st 80 hours . Reported lessons | | 6501 S. Oc ea n Driv e, Jen se n Be ac h, FL 34957 |
| | =Abstract= |
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| c,V'all.lf '°(., learned are in cOl])orated into the fi cens ing process an d fed back to industry. Se nd comments regarding burden
| | On June 4, 2024, at 1352 EDT, while in Mode 1 with Unit 2 at 92 percent power, the reactor was manually tripped due to a loss of condenser vacuum resulting from a circulating water pump (CWP) trip. The circulating water pump (282) trip was caused by the inability of the interlock circuit to provide the inhibiting function from the condenser outlet motor operated valve limit switch auxiliary contact. There were no Systems, Structures, or Components that were inoperable at the start of the event that contributed to the event. This event is being reported pursuant of 10 CFR 50.73(a)(2)(iv)(A), System Actuation. |
| .. 'i\\ LICENSEE EVENT REPORT (LER) estimate to th e FOIA, Library, and lnfonnation Collections Branch {T-6 A 101'1), U. S. Nucl ea" Regulatory
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| !~ j \\. / ..... (See NUREG-1022, (See Page 2 for required number of digits/characters for each block) Commission, Washington, DC 20555-0001, or by email to lnfocollects.Re source@nrc.gov, and the 0MB reviewer at 0MB Office or lnfonnation and Regulatory Affai rs, (3150-0104), Attn: Desk Office r for th e Nudear Reg ul atory R.3 for instruction and guidance for completing this form Commission, 725 17th Stree t NW, Washington, DC 20503. The NRC may not conduct or spo ns or, and a perso n is b!ti;r11www me gold~adiag-[rn/doc-collec!ioas/au[egs/s!a~[1 Q22l[JQ not required to respond to , a collection of infonnation unless the doc ument requesting or requiring the collection displays a currently va id 0MB control number.
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| : 1. Facility Name ~ 050 2. Docket Number 3. Page
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| St. Lucie Unit 2 D 052 00389 1 OF 2
| | ==Description of Event== |
| : 4. Title
| | On June 4, 2024, at 1352 EDT, while in Mode 1 with Unit 2 at 92 percent power, the reactor was manually tripped d ue to a loss of condenser vacuum resulting from a circulating wate r pump (CWP) trip. There were no Systems, Structures, or Components that were inoperable at the start of the event that contributed to the event. This event is being reported pu rsuant of 10 CFR 50. 73(a)(2)(iv)(A), System Actuation. * |
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| Unplanned Reactor Scram
| | ==Cause of Event== |
| : 5. Event Date 6. LER Number 7. Report Date 8. Other Facilities Involved
| | On June4, 2024, at 1345 EDT, St. Lucie Uni t 2 expe rienced a malfu nct ion of the condense r outlet valve (MV-21-5A2) limit sw itch. The ma lfunction resul ted in a trip of the 282 CWP that requ ired a manual reactor trip due to low condenser vacuum. |
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| Month Day Year Year Sequential Revision Month Day Year Facility Name D Docket Number Number No. 050
| | The 282 CWP trip was caused by the inability of the interlock circui t to prov ide the inh i bit ing fu nctio n f rom the condenser outlet motor operated valve limit switch auxiliary contac t. The lim it switch for the valves a re aux iliary contacts that do not provide indicat ion to the Control Room. |
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| 06 04 2024 2024 - 03 - 00 8 5 2024 Faciilty Name D 052 Docket Number
| | Safety Sign ificance : |
| : 9. Operating Mode rO. Power Level 1 92 | |
| : 11. This Report is Sub,nitted Pursuant to the Requirements of 10 CFR §: (Check all that apply)
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| 10 CFR Part 20 D 20.2203(a)(2)(vi) 10 CFR Part 50 D 50. 73(a)(2)(ii)(A) D 50.73(a)(2)(viii)(A) D 73.1200(a)
| | This event did not prevent any safety systems from performing the i r safety related functions based on the m i ni mal amount of leakage identified. |
| D 20.2201(b) D 20.2203(a)(3)(i) D 50.36(c)(1 )(i)(A) D 50.73(a)(2)(ii)(B) D 50. 73(a)(2)(viii)(B) D 73.1200(b)
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| D 20.2201(d) D 20.2203(a)(3)(ii) D 50.36(c)(1 )(ii)(A) D 50.73(a)(2)(iii) D 50. 73(a)(2)(ix)(A) D 73.1200(c)
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| D 20.2203(a)(1) D 20.2203(a)(4) D 50.36(c)(2) [l] 50.73(a)(2)(iv)(A) D 50. 73(a)(2)(x) D 73.1200(d)
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| D 20.2203(a)(2)(i) 1 O CFR Part 21 D 50.46(a)(3)(11) D 50.73(a)(2)(v)(A) 10 CFR Part 73 D 73.1200(e)
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| D 20.2203(a)(2)(ii) D 21.2(c) D 50.69(g) D 50. 73(a)(2)(v)(B) D 73.77(a)(1) D 73.1200(f)
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| D 20.2203(a)(2)(iii) D 50. 73(a)(2)(i)(A) D 50. 73(a)(2)(v)(C) D 73.77(a)(2)(i) D 73.1200(9)
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| D 20.2203(a)(2)(iv) D 50. 73(a)(2)(i)(B) D 50. 73(a)(2)(v)(D) D 73.77(a)(2)(11) D 73.1200(h)
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| D 20.2203(a)(2)(v) D 50. 73(a)(2)(i)(C) D 50. 73(a)(2)(vii)
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| D OTHER (Specify here, in abstract, or NRC 366A).
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| : 12. Licensee Contact for this LER
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| Licensee Contact Phone Number (Include area code) | | Th is Licensee Event Report is being reported pursuant of 10 CFR 50.73(a)(2)(iv)(A), System Actuation. |
| Bob Murrell 319-651-9496
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| : 13. Complete One Line for each Component Failure Described in this Report
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| Cause System Component Manufacturer Reportable to IRIS Cause System Component Manufacturer Reportable to IRIS B NN IEF N/A y
| | Th is event did not result in a Safety System Functional Failure. |
| : 14. Supplemental Report Expected Month Day Year
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| : 15. Expected Submission Date
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| [l] No Yes (If yes, complete 15. Expected Submission Date) D
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| : 16. Abstract (Limit to 1326 spaces, i.e., approximately 13 single-spaced typewritten lines)
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| On June 4, 2024, at 1352 EDT, while in Mode 1 with Unit 2 at 92 percent power, the reactor was manually tripped due to a loss of condenser vacuum resulting from a circulating water pump (CWP) trip. The circulating water pump (282) trip was caused by the inability of the interlock circuit to provide the inhibiting function from the condenser outlet motor operated valve limit switch auxiliary contact. There were no Systems, Structures, or Components that were inoperable at the start of the event that contributed to the event. This event is being reported pursuant of 10 CFR 50.73(a)(2)(iv)(A), System Actuation.
| | Correct ive Actions : |
| NRC FORM 366A U.S. NUCLEAR REGU LATORY COMMISSION APPROVED BY 0MB : NO . 3150 -0104 EXPIRES: 04/30/2027 (04-02-2024) Estimated burden per re spon se to comply with this mandatory collection request: 80 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry . Send comments LIC E NSEE EV ENT REPORT (L ER ) regarding burden estimate to the FOIA, Li brary, and Information Co ll ections Branch (T-6 A1 0M) , U.S .
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| Nuclear Regulatory Commiss ion, Washington, DC 20555-0001, or by email to CONTINUATION SH EE T lnfocollects.Resource@nrc.go v, and the 0MB reviewer at: 0MB Office of Information and Reg ulatory Affairs, (3150-0104), Attn: Desk Officer for the Nuclear Regulatory Com miss ion, 725 17th Street NW, (See NUREG - 1022, R.3 for instructi on and gu idance for completing th is form Was hi ng ton , DC 20503. The NRG may not conduct or sponsor, and a pe rson is not req uired to http ://www nrc gov/reading -rm/doc-collections/nuregs/ staff/sr1022/r3D respond to, a co ll ecti on of in fo rm ation unless th e document req uesting or requiring th e collection displays a cu rrently valid 0MB co ntrol number.
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| : 1. FACILITY NAME 050 2. DOCKET NUMBER 3. LER NUMBER YEAR SEQUENTIAL REV 1st. L ucie Unit 2 I 00389 D NUMBER NO.
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| I~ 052 I ~ - , 03 1-0
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| NARRATIVE
| | Operating procedu res we re revised to requ i re the re m oval of control fuses from the CWP breaker. |
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| Description of Event:
| | Simila r Events : |
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| On June 4, 2024 , at 1352 EDT, while in Mode 1 with Unit 2 at 92 percent power , the reactor was manually tripped d ue to a loss of condenser vacuum resulting from a circulating wate r pump (CWP) trip. There were no Systems, Structures, or Components that were inoperable at the start of the event that contributed to the event. This event is being reported pu rsuant of 10 CFR 50 . 73(a)(2)(iv)(A) , System Actuation.
| | A rev iew of events over the past 5 years did not identify any unplanned reactor scrams as a result of a CWP trip. |
| * Cause of Event:
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| On June4 , 2024 , at 1345 EDT , St. Lucie Uni t 2 expe rienced a malfu nct ion of the condense r outlet valve (MV-21-5A2) limit sw itch. The ma lfunction resul ted in a trip of the 282 CWP that requ ired a manual reactor trip due to low condenser vacuum .
| | N RC FORM 366 A (04-02-202 4) Page 2 of 2 |
| | |
| The 282 CWP trip was caused by the inability of the interlock circui t to prov ide the inh i bit ing fu nctio n f rom the condenser outlet motor operated valve limit switch auxiliary contac t. The lim it switch for the valves a re aux iliary contacts that do not provide indicat ion to the Control Room .
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| Safety Sign ificance :
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| This event did not prevent any safety systems from performing the i r safety related functions based on the m i ni mal amount of leakage identified.
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| Th is Licensee Event Report is being reported pursuant of 10 CFR 50 .73(a)(2)(iv)(A), System Actuation.
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| Th is event did not result in a Safety System Functional Failure .
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| Correct ive Actions :
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| Operating procedu res we re revised to requ i re the re m oval of control fuses from the CWP breaker.
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| Simila r Events :
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| A rev iew of events over the past 5 years did not identify any unplanned reactor scrams as a result of a CWP trip.
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| N RC FORM 366 A (04-02-202 4) Page 2 of 2 | |
| }} | | }} |
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| {{LER-Nav}} | | {{LER-Nav}} |
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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
ML24227A9702024-10-18018 October 2024
Letter to Kenneth Mack Dir, License and Reg Compliance, NextEra Energy, Inc Response to Request Re Engagement Re Sub License Renewal Environmental Review - St Lucie Nuclear Plant 1 and 2
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
L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024
2024 Population Update Analysis
IR 05000335/20240022024-08-13013 August 2024
Integrated Inspection Report 05000335-2024002 and 05000389-2024002
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
05000389/LER-2024-003, Unplanned Reactor Scram2024-08-0505 August 2024
Unplanned Reactor Scram
ML24163A0012024-08-0505 August 2024
LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review
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
05000389/LER-2024-002-01, 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-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024
Cycle 32 Core Operating Limits Report
L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024
Cycle 27 Core Operating Limits Report
ML24108A0632024-04-18018 April 2024
– Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024
Annual Radiological Environmental Operating Report for Calendar Year 2023
L-2024-064, 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-2024-054, 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
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
05000389/LER-2024-002-01, 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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LER-2024-003, Unplanned Reactor Scram |
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text
August 5, 2024 L-2024-115 10 CFR 50.73
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Re: St. Lucie Unit 2 Docket No. 50-389 Reportable Event: 2024-03-00 Date of Event: June 4, 2024
Unplanned Reactor Scram
The attached Licensee Event Report, 2024-03, is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.
Should you have any questions regarding this submission, please contact Mr. Kenneth Mack, Senior Manager Licensing and Reg Compliance - Nuclear Fleet, at 561-904-3635.
This letter contains no new or modified regulatory commitments.
Sincerely,
Paul Rasmus General Manager - Regulatory Affairs - Nuclear Fleet Florida Power & Light Company
Attachment
cc: St. Lucie NRC Senior Resident Inspector St. Lucie Station NRC Program Manager
Florida Power & Light Company
6501 S. Oc ea n Driv e, Jen se n Be ac h, FL 34957
Abstract
On June 4, 2024, at 1352 EDT, while in Mode 1 with Unit 2 at 92 percent power, the reactor was manually tripped due to a loss of condenser vacuum resulting from a circulating water pump (CWP) trip. The circulating water pump (282) trip was caused by the inability of the interlock circuit to provide the inhibiting function from the condenser outlet motor operated valve limit switch auxiliary contact. There were no Systems, Structures, or Components that were inoperable at the start of the event that contributed to the event. This event is being reported pursuant of 10 CFR 50.73(a)(2)(iv)(A), System Actuation.
Description of Event
On June 4, 2024, at 1352 EDT, while in Mode 1 with Unit 2 at 92 percent power, the reactor was manually tripped d ue to a loss of condenser vacuum resulting from a circulating wate r pump (CWP) trip. There were no Systems, Structures, or Components that were inoperable at the start of the event that contributed to the event. This event is being reported pu rsuant of 10 CFR 50. 73(a)(2)(iv)(A), System Actuation. *
Cause of Event
On June4, 2024, at 1345 EDT, St. Lucie Uni t 2 expe rienced a malfu nct ion of the condense r outlet valve (MV-21-5A2) limit sw itch. The ma lfunction resul ted in a trip of the 282 CWP that requ ired a manual reactor trip due to low condenser vacuum.
The 282 CWP trip was caused by the inability of the interlock circui t to prov ide the inh i bit ing fu nctio n f rom the condenser outlet motor operated valve limit switch auxiliary contac t. The lim it switch for the valves a re aux iliary contacts that do not provide indicat ion to the Control Room.
Safety Sign ificance :
This event did not prevent any safety systems from performing the i r safety related functions based on the m i ni mal amount of leakage identified.
Th is Licensee Event Report is being reported pursuant of 10 CFR 50.73(a)(2)(iv)(A), System Actuation.
Th is event did not result in a Safety System Functional Failure.
Correct ive Actions :
Operating procedu res we re revised to requ i re the re m oval of control fuses from the CWP breaker.
Simila r Events :
A rev iew of events over the past 5 years did not identify any unplanned reactor scrams as a result of a CWP trip.
N RC FORM 366 A (04-02-202 4) Page 2 of 2
