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Category:Licensee Event Report (LER)
MONTHYEAR05000335/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 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 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 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 ML18127A6781978-02-17017 February 1978 LER 1978-007-00 for St. Lucie Unit 1, Technical Specification 4.3.1.1.3 RTD Response Time ML18127A6791978-02-17017 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 ML18110A8781977-07-0808 July 1977 LER 1977-335-28 for St. Lucie, Unit 1 on Containment Isolation Valve ML18110A8771977-07-0808 July 1977 LER 1977-335-03 for St. Lucie, Unit 1 on Diesel Generator 1A, Update Report No. 1 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 ML18110A8831977-05-24024 May 1977 LER 1977-335-29 for St. Lucie, Unit 1 Safety Injection Line Weld ML18110A8841977-05-19019 May 1977 LER 1977-335-29 for St. Lucie, Unit 1 Pressure Boundary Leakage ML18110A8851977-05-15015 May 1977 LER 1977-335-20 for St. Lucie, Unit 1 Ginca Code ML18110A8811977-05-13013 May 1977 LER 1977-335-23 for St. Lucie, Unit 1 on RCS Flow 2017-08-15
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U.S. NUCI.EAB REGULATORY COMMISSION DOCKET NUMOFB N RC"FORM 196
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!J I'ILE NUMOCB NlgC DISTRIBUTION roR PART ES DOCKET MATERIAL I INCXDENT REPORT TO: N.C.MOSELEY,. "ROM: FLORDIA PWR & LIGHT CO. DATE OF DOCUMENT MIAMI, FL. 3/24/77
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A.D . SCHMIDT DATE RECEIVED 4/6/77 g&LETTE R QNOTORIZED PROP INPUT FORM NUMOER OF COPIES RECEIVED
~B G IN*LI l@J NC LASS IF I E D 0 COPY DESCRIPTION ENCLOSURE LTR. TRANS THE FOLLOWXNG'...... LICENSEE EVENT REPORT FOR R.O. "/3 77-12, ON 2/24/77 CONCERNING THE DIGITAL DATA PROCESSIN SYSTEM MALFUNCTIONING...'...
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PLANT NAIVE: ST LUCIE f/ 1 SAB NOTE: XF PERSONNEL EXPOSURE IS INVOLVED SEND DXRECTLY TO KREGER/J, COLLXNS FOR ACTION/INFORMATION BRANCH CHIEF:
01 3 CYS FOR ACTIONJ LXC, ASST,:
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..~S INTERNAL D IST RIBUTION N C PDR I & E 2 MXPC SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRXMES CASE BUTLER HANAUER TEDESCO/MACCARY FXSENHUT'AER SHAD VOLLMER/BUNCH KREGER/J COLLINS EXTERNAL DISTR I BUTION CONTROL NUMBER LPDR:
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P.O. BOX 013100, MIAMI, FL 33101 FLORIDA POWER & LIGHT COMPANY March 24, 1977 PRN-LI-77-83 Mr. Norman C. Moseley, Director, Region II oy.
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Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 230 Peachtree Street, N. N., Suite 1217 Atlanta, Georgia 30303
Dear Mr. Moseley:
REPORTABLE OCCURRENCE 335-77-12 ST. LUCIE UNIT 1 DATE OF OCCURRENCE: FEBRUARY 24, 1977 DIGITAL DATA PROCESSING SYSTEM 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. Sc 3.
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)
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PEOPLE... SERVING PEOPLE
i' LICENSEE EVENT REPORT
~ ~, I CSNTROL BLOCK: (PLEASE PAINT ALL AEOUIAEO INFORMATION) 1 UCENSEE UCENSE EVENT NAME UCENSE NUMBER TYPE TYPE Ioa~] 0 0 0 0 0 1 1 1 1 ~p 7 89
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14 15 25 26 30 31 32 REPORT AEPOAT CATEGORY TYPE SOURCE OOCKET NUMBER EVENT OATE REPORT OATE I001]CON'r 1, p p p 0 2 2 7 7 0 3 1 8 7 7 7 8 57 58 59 60 61 68 69 74 75 80 I
EVENT OESCRIPTION Qg Durin ower o eration the Di ital Data Processi S stem malfunctioned resulting in a 7 8 9 80 loss of CEA backu osition indication and the incore flux detector s stem used to I 7 89 80
~0 4 monitor incore flux distribution. Action required by Specification 3.1.3.3 and 4.2.1.3 7 8 9 80 Qg was initiated but the DDPS was restored to o eration before ower was reduced signifi-7 a9 80
~0 6 cantl and all CEA's were alread full withdrawn with all reed switch osition 7 8 9 80 SYSTEM CAUSE COMPONENT COOE
'2 COOE COMPONENT COOE MANUFACTURER
~XX ~E X X X X A F 1 2 0 7 8 9 10 11 17 43 44 47 48 CAUSE OESCRIPTION Qgaa Durin routine transfer of a ro ram from disc stora e to active memor the DDPS 80 Qg momentaril lost its reference oint. The resultin incorrect transfer caused the 7 8 9 80
. Qg co uter to al .;- No cause could be found for the s stem malfunction however F
7 89 80 FAClUTY METHOD OF STATUS =
% POWER OTHER STATUS
~ZP OISCOVEAY OISCOVERY OESCAIPTION Q~g E NA NA 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT AELEASEO OF RELEASE AMOUNT OF ACTNITY LOCATION OF RELEASE EH L~J Lzl NA NA 7 8 9 10 11 45 80 PERSONNEL EXPOSURES NUMBER TYPE OESCAIPTION
~s ~o o 0 z NA 7 8 9 11 12 13 PERSONNEL INJURIES NUMSEA OESCRIPTION 7
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~oo o 11 12 NA 80 PROBABLE CONSEQUENCES 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCAIPTION z NA 7 89 10 80 PUBLICITY NA 7 89 .80 AOOITIONAL FACTORS t11I w for continuation of Event Descri tion and Cause Descri tion.
7 89 80 7 89 80 M. A. Scho man PHONE 305/552-3779 CFO IIII5 ~ 1IIT
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Licensee Event Report Reportable Occurrence 335-77-12 Page 2 of 2 EVENT DESCRIPTION (Continued) indication channels operable. This is the sixth reportable occurrence involving loss of the DDPS (335-76-19, 335-76-27, 335-76-38, 335-76-48, 335-77-9), but the first occurrence due to this cause (335-77-12).
CAUSE DESCRIPTION (Continued) computer anomalies of this sort are not uncommon. Auto-restart of the unit functioned properly (after cause of halt was discovered) and the DDPS was back in service 18 minutes after the halt.
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