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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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NRV'FORM J5<2.7G)U.S.NUCLEAR REGULATORV Co SSION DOC~T NUMBER'SO~BM NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL FILE NUMBER INCIDENT REPORT TO:.Mr.Norman C.Moseley Florida Power 6 Light Company Miami, Florida A~D~Schmidt.DATE OF DOCUMENT 4/4/77 DATE RECEIVED 4/18/77 ETTER CRRIGINAL Ocopv ONOTORIZED PRONCLASSIFIED I PLANT NAME:)~!ISt.Lucie Unit No.1 RJL DESCRIPTION Ltr, trans the following:
PROP (1-P)INPUT FORM NUMBER OF COPIES RECEIVED ENCLOSURE sE<~~(2-P)<m@@BSI Ig Jiff hHBf..NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J, COLLINS Licensee Event Report (RO 50-335/77-16) on 3/5/77 concerning low steam gener'ator pressure trips being received on channel A RPS and channel A MSIS~~~~~~BRANCH CHIEF: 8 3 CYS FOR ACTION LICo ASST,: W CYS'CRS CYS S!%&INC S FOR ACTION/INFORMATION R iC~nrt NT EG RIL NRC PDR M6cE 2 MIPC SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES CASE BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SHAO VOLLMER/BUNCH KREGER/J COLLINS INTERNAL D R I BUTION IST LPDR0 TZC0 N E NAL DISTRIBUTION CONTROL NUMBER NRC FORM 196 (2 7GI PPJo go+5'f 4~Ivy 4 yg FLORIOA POWER&LIGHT COMPANY April 4, 1977-Px-77-PQ$
j;Mr.Norman C.Moseley, Director, Region Office of Inspection and Enforcement U.S.Nuclear Regulatory Commission 230 Peachtree Street, N.W., Suite 1217 Atlanta, Georgia 30303
Dear Mr.Moseley:
REPORTABLE OCCURRENCE 335-77-16 ST.LUCIE UNIT 1 DATE OF OCCURRENCE:
MARCH 5, 1977 STEAM GENERATOR PRESSURE TRANSMITTER The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide 30-day notification of the subject occurrence.
Very truly yours, D.c it Vice President Power Resources MAS/cpc Attachment cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (30)Director, Office of Management Information and Program Control (3)>7mb'dA Y$I PEOPLE...SERVING PEOPLE
~-.e.~>~P'I P CONTROL 8LOCK LICENSEE EVENT REPORT~(PLEASE PRINT ALL RECIUIREO INFORMATION)
UCENSEE NAME 01 F L S L S 1 0.7 89 14 15 REPORT AEPOAT CATEGORY TYPE SOURCE I001]coN'T~~L L 7 8 57 58 59 60 EVENT DESCRIPTION Qg Durin Power 0 eration UCENSE EVENT~UCENSE NUMSER TYPE TYPE 0-0 0 0 0 0-0 0 A 1 1 1 1 L0OO3~I 25 26 30 31 32 OOCKET NUh18EA EVENT OATE REPORT OATE 0 5 0-0 3 3 5 0 3 0 5 7 7 0 3 1 6 7 7 61 68 69 74 75 , 8O low steam enerator'essure tri s were received on channel A 89 t003j RPS and channel A MSIS.Action was taken in accordance with Technical S ecifications 7 89~4..1 ion 2.and..2.1 action'.The affected channel A tri s were 8O 80 7 8 9 Qog 7 8 9 Jog 80 d o service in 1.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.This was the fourth occurrence of an ino erable RPS 80 FAS channe.The revious occurrences were re orted as LER's 335-76-5 loss of 7 8 9 PAME SYSTEM CAUSE COMPONENT COOE COOE, COMPONENT COOE SUPPUER I007I~TA~E x x x x x x z 7 8 9 10 11 12 17 43 CAUSE OESCRIPTION I008 The fuse rotectin the DC ower su 1 for z 9 9 9 a7 N 48 steam enerator channel A ressure trans-80 7 8 9 Q~I mitter PT-8013A failed.The ower su 1 and'nstrument loo were checked for other 80 7 8 9 roblems and none were found.The fuse was re laced and the channel A tri 80 set oint was OTHER STATUS NA'7 89 LOSS OR OAMAGE TO FACIUTY TYPE OESCAIPTICN z 7 89 10 PUSLICITY 7 89 7 89 FACiUTY STATUS.1 POWER 0~g 0~O 7 8 9 10 12 13 FOAM OF ACTIVITY COATENT RELEASEO OF RELEASE AhIOUNT OF ACTIVITY KRI NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMSER TYPE OFSCAIPTION Q~~]~(~0 z 7 8 9 11 12 13 PERS'ONNEL
!N JURIES OESCAIPTION
~~4 0 0 0 7 8 9 11 12 PROBABLE CONSEQUENCES Qg METHOO OF OISCOVEAY OISCOVEAY OESCAIPTION A NA 44 45 46 LOCATION OF RELEASE NA 44 45 NA NA NA NA NA 8O 80 80 60 80 80~80 AOOITIONAL FACTORS Q~g See a e two for continuation of Event Descri tion and Cause Description.
,7 89 80 7 89 NAME M.A.Scho man PHONEI 305/552-3779 80 CPO IISI 6IIT LICENSEE EVENT REPORT REPORTABLE OCCURRENCE 335-77-16 PAGE TWO EVENT DESCRIPTION (Continued) power caused by loose electrical connections), 335-76-17 (ESFAS setpoint drift), and 335-76-26 (loss of power due to 1C inverter failure).This occurrence was not related to the previous occurrences.
(335-77-16).
CAUSE DESCRIPTION (Continued)
Verified.
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