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| [ODg The cause of this occurrence was PRME COMPONENT SUPPUER COMPONENT MANUFACTURER I 0 7 5 A N 44 47 that more than 15 minutes was needed to verif that a 7 8 9 80~0 3 ressurizer. | | [ODg The cause of this occurrence was PRME COMPONENT SUPPUER COMPONENT MANUFACTURER I 0 7 5 A N 44 47 that more than 15 minutes was needed to verif that a 7 8 9 80~0 3 ressurizer. |
| When reactor coolant s stem ressure was about 268 sia the Low-Pressure 7 8 9 tOOI ressurizer bubble had been drawn and that RC Le erature and 80 7 8 9 80 a ro riate limits before ener izin RCP's.15 minutes is considered insufficient time 7 89 FACIUTY STATUS 96 POWER[Z]uo~00 o 7 8 9 10 12 13 FORM OF p ACTIVITY COATENT RELEASEO OF RELEASE Qg Lzl~z 7 8 9 10 11 PERSONNEL EXPOSURES C<03~IJII lZJ 7 89 11 12 13 PERSONNEL IN JURIES NUMBER OESCRPTION Qg~0.o o 7 89'1 12 OTHER STATUS NA AMOUNT OF ACTIVITY NA PROBABLE CONSEQUENCES Qg 7 89 7 8 9 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION | | When reactor coolant s stem ressure was about 268 sia the Low-Pressure 7 8 9 tOOI ressurizer bubble had been drawn and that RC Le erature and 80 7 8 9 80 a ro riate limits before ener izin RCP's.15 minutes is considered insufficient time 7 89 FACIUTY STATUS 96 POWER[Z]uo~00 o 7 8 9 10 12 13 FORM OF p ACTIVITY COATENT RELEASEO OF RELEASE Qg Lzl~z 7 8 9 10 11 PERSONNEL EXPOSURES C<03~IJII lZJ 7 89 11 12 13 PERSONNEL IN JURIES NUMBER OESCRPTION Qg~0.o o 7 89'1 12 OTHER STATUS NA AMOUNT OF ACTIVITY NA PROBABLE CONSEQUENCES Qg 7 89 7 8 9 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION |
| ~16 Z 7 89 10 PUBLICITY METHOO OF OSCOVERY a 44 45 46 44 45 NA NA NA 80 OISCOVERY OESCRIPTION NA 80 LOCATION OF RELEASE NA 80 80 80 80 80.80 ADDITIONAL FACTORS'~I See Pa e Two for continuation of Event and Cause descri tion.7 8 9 80 7 89 NAME.M.A.Schoppman 305/552-3779 80 GPO Gent GGT 4 r Reportable Occurrence 3 76-6 Licensee Event Report Page Two Event Descri tion (continued) 3.4.1 permits operation in Modes 3, 4, and 5 for a maximum of 15 minutes with no shutdown cooling (LPSI)pump or RCP in operation. | | ~16 Z 7 89 10 PUBLICITY METHOO OF OSCOVERY a 44 45 46 44 45 NA NA NA 80 OISCOVERY OESCRIPTION NA 80 LOCATION OF RELEASE NA 80 80 80 80 80.80 ADDITIONAL FACTORS'~I See Pa e Two for continuation of Event and Cause descri tion.7 8 9 80 7 89 NAME.M.A.Schoppman 305/552-3779 80 GPO Gent GGT 4 r Reportable Occurrence 3 76-6 Licensee Event Report Page Two Event Descri tion (continued) |
| | |
| | ====3.4.1 permits==== |
| | operation in Modes 3, 4, and 5 for a maximum of 15 minutes with no shutdown cooling (LPSI)pump or RCP in operation. |
| This was the first occurrence of this type.(335-76-6). | | This was the first occurrence of this type.(335-76-6). |
| Cause Descri tion continued) to perform the transition from SDC 3 operation to RCP operation. | | Cause Descri tion continued) to perform the transition from SDC 3 operation to RCP operation. |
| Followup action will be to submit a request to amend the Technical Specifications to extend the time limit for transition from SDC operation to RCP operation in Modes 3, 4, and 5.}} | | Followup action will be to submit a request to amend the Technical Specifications to extend the time limit for transition from SDC operation to RCP operation in Modes 3, 4, and 5.}} |
|
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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
[Table view] |
Text
'f I C'r onM 194~I7.7!II~~'.s.I~UCLL'An ncGULATonv co ssioN OOCKGT NUM(IL'n 50-335'TO: 'MR, NORMAN C~MOSELEY F IIOM: FLORIDA POWER&LIGHT COMPANY MIAMI~FLORIDA AD H GHHIDIIIO~~~'".7
'.NLL=TTEB I QfonIGINAL Qcopv 0 NOTofli7 C 0 QkUNC LASSII'IEO pnop INPUT FORM NRC DISTRIBUTION ron PABT 50 DQCICET MATERIAL IiILF.NUM!I!In XNCXDEIIT REPORT OATC OF OOCUIAFNT 4/26/76 OATF.RECDIVL'O 5/4/76 NUMOFB or.cor IES ReccivFO~ONE'SIGNED I OSSCBIPTION LTD TRANS THE FOLLOWING:, LNCI.OSU BC I', LICENSEE EIJENTJgT.(RO 50'-335/1976-6')
ON.3/26/76'CONCERl43,"NG 3~4PERMITS OPERATION IN MODES', 4&5 FOR A MAXIMUM OF 15 MINUTES WITH NO SHUTDOWN.QOOLXNG (LPSI)PUMP OR.RCP,~XN OPERATIONS
.,~'~~~h~ACKNOWLEI)BED DP gOT PEMQVE PLANT NAME: ST.LUCIE 81~I NOTE': XF'PERSONNEL EXPOSURE XS INVOLVED'END DXRECTLY TO IDZGER/J.COLLXNS SAFETY 13RANCH CIIXEF: w 3 cYS FoR AcTIoN PARR FOR ACT IOiNiiI'J FO RMAT ION ENVIRO LXC, ASST: W/CYS ACRS CYS HOLDXNG/GOULBOURNE ENT TO LA:.G I NRC PDR I&E 2 J I)XS~SCI!ROEDI:R/XPPOLITO JNLII)IIOV~V.Cl>>:.CI(-C!!,-""'~.-"~il i": Ch.Sj'~iXAMS Dk I~h U~'8 TL'l)l'SCO Hh(l('Al'KBMLUI 13AI R S1IAO VOI.I.HI'.
R/>>>>INC I I.lslll'gIMI.
1.e (cOI J!XNS INTERNAL D R I I3UTI ON EARc~~Ž~TXr iNS I.C EXTEIIf'Jhf.
I)ISTR IIIUl ION CON'I f I OL NUMIII'.l l r I 1 4~IC T/'I t I t 0 t f 4 I i 9 d e~la~eJRRe
~~8 FLORIDA POWER 5 LIGHT COMPANY April 26, 1976 PRN-LI-76-98 Mr.Norman C.Moseley, Director, Region II Office of Inspection and Enforcement U.S.Nuclear Regulatory Commission
.230 Peachtree Street, N.W., Suite 818 Atlanta, Georgia 30303
Dear Mr.Moseley:
~l:y,ETE0 6 1I)11IIQ 8 IIIg P IS7S 9 QQVLA1 REPORTABLE OCCURRENCE 335-76-6'ST.LUCIE UNIT 1 DATE OF OCCURRENCE:
MARCH 26, 1976 TECHNICAL SPECIFICATION TIME LIMIT EXCEEDED DURING TRANSITION FROM SHUTDONN COOLING PUMPS TO REACTOR COOLANT PUMPS 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, A.D.Schmidt Vice President Power Resources MAS/cpc Attachment gg1 q8~cc: Jack R.Newman, Esquire Director, Office of Inspection and Enforcement (30)Director, Office of Management Information and Program Control (3)HELPING BUILD FLORIDA LICENSEE EVENT REPORT~CONTROL BLOCK: 1 UCFNSEE NAME F L S L S 1.7 89 14 15 UCENSE NUMBER LICENSE TYPE 4 1 1 25 26 30 EVENT TYPE LoOJ 31 32 (PLEASE PRINT AI.L REQUIRED INFORMATION)
REPORT REPORT CATEGORY TYPE SOURCE~OOCKET NUMBER I001]CON'7~~L~L 0 5 0 0 7 8 57 58 59 60 61 EVENT DESCRIPTION
[oO~]68 69 EVENT OATE 2 74 75 REPORT DATE 80 89~, 80 f74 Safet In ection LPSI um s were sto ed because the maximum re u o utd 7 8 9 80~0 5 coolin (SDC)o eration is 268 sia.The transition from SDC o eration to reactor 7 8 9 80 Qp g coolant pump (RCP)operation took a roximatel 35 minutes.Technical S ecification (cont.d')7 8 9 SYSTEM CAUSE COOE COOE COMPONENT COOS~07~CF~F P'M P 7t 7 8 9 10 11 12 17 CAUSE DESCRIPTION
[ODg The cause of this occurrence was PRME COMPONENT SUPPUER COMPONENT MANUFACTURER I 0 7 5 A N 44 47 that more than 15 minutes was needed to verif that a 7 8 9 80~0 3 ressurizer.
When reactor coolant s stem ressure was about 268 sia the Low-Pressure 7 8 9 tOOI ressurizer bubble had been drawn and that RC Le erature and 80 7 8 9 80 a ro riate limits before ener izin RCP's.15 minutes is considered insufficient time 7 89 FACIUTY STATUS 96 POWER[Z]uo~00 o 7 8 9 10 12 13 FORM OF p ACTIVITY COATENT RELEASEO OF RELEASE Qg Lzl~z 7 8 9 10 11 PERSONNEL EXPOSURES C<03~IJII lZJ 7 89 11 12 13 PERSONNEL IN JURIES NUMBER OESCRPTION Qg~0.o o 7 89'1 12 OTHER STATUS NA AMOUNT OF ACTIVITY NA PROBABLE CONSEQUENCES Qg 7 89 7 8 9 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION
~16 Z 7 89 10 PUBLICITY METHOO OF OSCOVERY a 44 45 46 44 45 NA NA NA 80 OISCOVERY OESCRIPTION NA 80 LOCATION OF RELEASE NA 80 80 80 80 80.80 ADDITIONAL FACTORS'~I See Pa e Two for continuation of Event and Cause descri tion.7 8 9 80 7 89 NAME.M.A.Schoppman 305/552-3779 80 GPO Gent GGT 4 r Reportable Occurrence 3 76-6 Licensee Event Report Page Two Event Descri tion (continued)
3.4.1 permits
operation in Modes 3, 4, and 5 for a maximum of 15 minutes with no shutdown cooling (LPSI)pump or RCP in operation.
This was the first occurrence of this type.(335-76-6).
Cause Descri tion continued) to perform the transition from SDC 3 operation to RCP operation.
Followup action will be to submit a request to amend the Technical Specifications to extend the time limit for transition from SDC operation to RCP operation in Modes 3, 4, and 5.
