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Category:Letter
MONTHYEARL-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums IR 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-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes 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 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 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-2024-064, 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 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 05000389/LER-2024-002, Safety Injection Tank Vent Through Wall Leakage2024-02-29029 February 2024 Safety Injection Tank Vent Through Wall Leakage 05000389/LER-2024-001, Safety Injection Tank Vent Through Wall Leakage2024-02-13013 February 2024 Safety Injection Tank Vent Through Wall Leakage 05000335/LER-2022-003, Manual Reactor Trip Due to Loss of Feedwater Pump2022-10-28028 October 2022 Manual Reactor Trip Due to Loss of Feedwater Pump 05000389/LER-2022-001, Reactor Shutdown Required by Technical Specifications Due to a Misaligned Control Element Assembly2022-03-0404 March 2022 Reactor Shutdown Required by Technical Specifications Due to a Misaligned Control Element Assembly 05000335/LER-2021-001, Manual Reactor Trip Due to Insufficient Feed Flow to Steam Generators2022-02-0404 February 2022 Manual Reactor Trip Due to Insufficient Feed Flow to Steam Generators 05000389/LER-2021-002, Foreign Material Exclusion Device Found in Containment Spray System2021-11-10010 November 2021 Foreign Material Exclusion Device Found in Containment Spray System 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 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 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-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 2024-09-25
[Table view] |
Text
NIIC FOflM 195 U.S. NUCLGAA flGOULATOIIVCOMMIS ION DOCKET NUMOEf1 I 2-701 50-336
~t FILE NUMOL'll NBC DISTBIOUTION Fol I ART 50 DOCKET MATERIAL INCIDI',NT REPORT N.C. Mgs'eley FRoM:Flordia Power. 8'ight Co. DATE OF DOCUMENT Miami, Flordia 6-10-76 A.D. Schmidt DATE RECEIVED 6-17-.76 QLCTTEA ONOTOAIZGD PROP INPUT FOAM NUMOGA OF COPIES AGCEIVFD QOAIGINAL
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@UNCLASSIFIED EICOPV DESCRIPTION ENCLOSURE Ltr.. trans the Licensee Event Report (R.O. 76-9) on.,3-31-76
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Concerning Mechanical Pipe Restraints Supplementary Report 81 .......
(30 Carbon Signed Cys. Received)
(4 Page's)
ACKNOWLEDGED, .
D>>OT aZMOVz PLANT NAME: St. Lucie 8 1 NOTE: IF PERSONNEL EfiPOSURE XS 'INVOLVED.,
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Dear Mr. Moseley:
REPORTABLE OCCURRENCE 335-76-9 ST. LUCIE UNIT 1 DATE OF OCCURRENCE: MARCH 31'976 MECHANICAL PIPE RESTRAINTS SUPPLEMENTARY REPORT NO. 1 The attached Licensee Event Report is being submitted to supplement our initial report of April 12, 1976.
Very truly yours, Vice President Power Resources MAS/cpc At tachment cc: Jack R. Newman, Esquire
-Director, Office of. Inspection and Enforcement (40)
Director,.- Office of Management Information and Program Control (3)
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LICENSEE EVENT REPORT CONTROL BLOCK: Sf PRINT ALL RfQUIRE 0 INFORMATION) 1 6
. UCENSEE UCENSE EVENT
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~01 FLSLZ1 0 0 00000 UCENSE NUMBER 00 41 TYPE 1 11L000~1I TYPE
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7 89 14 15 25 26 30 31 32 REPOAT, REPORT CATEOORY TYPE SOURCE OOCKET NUMBER ~ EVENT OATC AEPORT OATE
[001j coN'r T ~L 0 5 0 0 3 3 5 0 3 3 1 7 6 0 6 1 0 7 6 7 8 57 58 59 60 61 68 69 74 75 80 EVENT OESCRIPTION Qg8 7 9 P o rational testin of i in restraints snubbers was bein er-80 Qg'ormed durin the heatu for Post Core Hot Functional testin . At the 7 89 80
[GD4] 260'F heatu lateau five INC mechanical snubbers were found to be 7 8 9 80 Qo 5 locked u . The immediate action was to replace the defective snubbers 7 8 9 toad with o erable snubbers. All of the INC snubbers have since been replace 80 7 8 9 PRME 60 SYSTEM CAUSE COMPOI4ENT COMPONENT COOE COOE COMPONENT COOE SUPPUER MANUFACTURER
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~zz ~z A N G E R ~A 'B 2 1 0 'N 11 12 17 43 44 47 CAUSE OESCFIIPTION Qg8 7 9 As reviousl re orted it was determined that oxidation of internal 80 to09 corn onents was the cause of the occurrence. Subse uent factory labora-7 8 9 80 tor testin and anal sis showed the followin 7 89 FACVPf METHOO OF 80 STATUS 9fi POWER OTHER STATUS 06COVERY OISCOVEAY OESCRIPTION Q~g 0 Loaoo J N A Preo erational Test Procedure 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE 'AMOUNT OF ACTIVITY LOCATION OF RELEASE t11g ~Z Z N/A N/A 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 7 8 9 11 12 13 80 PERSONNEL INJURIES 7
~4 8 9 0'0 11 0ESCRIPTION 12 N A 80 P>QQ~LE CONSEQUENCES N A 7 8 9 80 LOSS OR OAMAGE TO FACILITY TYPE OESCAIPTION EE L~l 7 89 10 N A 80 PUBLICITY N/A 7 8 9 80 AOOITIONAL FACTORS See Pa es 2
'18 and 3 for continuation of Event & Cause Descriptions.
7 89 80 7 89 80 NAMEI M. A. Schop man PHONE 305/552-3779 GPO IIAI~ 6/7
REPORTABLE OCCURRENCE 335-7 6-9 SUPPLEMENTARY LER NO.
PAGE TWO l
Event Descri tion (Continued) by Pacific Scientific snubbers.
C Cause. Descri tion (Continued)
S/N 000377 The front. and rear caps of the snubber were removed. A thin layer of oxidation was found on the inside of both caps, and there was water inside the rear cap. The ball screw was opera-tional, and clearances between'internal components were normal. However, there was a large amount of rust sludge and water inside the center section which, caused rotational binding.
The rotational binding resulted in resistance to thermal move-
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ment.
Also, the thrust bearing was installed incorrectly at .the factory, but this did not cause the snubber malfunction.
S/N 000343 This snubber was found to have an improper end fitting (i.e.,
no ball bushing), and its indicator bar was slightly bent.
With the correct- end fitting, the snubber was opeiational, therefore, it was not disassembled.
S/N 000525 The front and rear caps were removed and the snubber interior was found to be clean. .The ball screw was operational, and the clearances between internal components were normal.
slight, rotational binding in the center section.
However,'here was When the adaptor assembly was rotated one revolution, the. snubber began to operate,. but with a higher .than normal resistance to movement. The adaptor assembly was removed and a small amount of oxidation was found on the thrust bearing. The amount of oxidation was considered large enough to have caused the snubber malfunction.
S/N 000695 Same description as for 000525.
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REPORTABLE OCCURRENCE 335-76-9 SUPPLEMENTARY LER NO.. 1 PAGE THREE Cause'escri tion (Continued)
S/N 000632
": The'ront and rear caps were'removed.and'he snubber -interior
- was found to be clean. 'The ball screw. was operational, and the clearances between internal components were normal; However,
- there -was rotational binding in the center section. The adaptor assembly was removed and a large amoun't of oxidation was found on
~
the thrust bearing.. The oxidation caused the snubber malfunction.
FLORIDA POWER 8, LIGHT COMPANY June 10, 1976 PRN-LI-76-143 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:
REPORTABLE OCCURRENCE 335-76-9 ST. LUCXE UNIT 1 DATE OF OCCURRENCE: MARCH 31, 1976 MECHANICAL PIPE RESTRAXNTS SUPPLEMENTARY REPORT NO. 1 The attached Licensee Event. Report is being submitted to supplement our initial report of April 12, 1976.
Very truly yours, Vice President Power Resources MAS/cpc Attachment cc: Jack R. Newman, Esquire Director, Office of Inspection and Enforcement (40)
Director, Office of Management Xnformation and Program Control (3)
HELPING BUILD FLORIDA
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EVENT OESCRIPTION erational testin of i in restraints snubbers was bein er-1 Q58 Prep 7 9 80
. foimed durin the heatu for Post Core Hot Functional testin . At the 7 89 80
~04 260'F heatu lateau, five INC mechanical snubbers were found to be 7 8 9 80 .
Qo g .locked u . The immediate action was to replace the defective snubbers 7 8.9 80 Qo 6 with operable snubbers. All of the .INC snubbers have since been replace 7 8 9 WPAE 80 SYSTEM CAUSE COMPONENT COMPONENT 7
[oa'] ~ZZ 8 9 10 COBE COOE
~S 11 12 ANGERA COMPONENT COOE 17 SUPPUER 43 B
MANUFACTUAER 2 1 0 47 N
48 CAUSE OESCRIPTION 7 8 9 As reviousl re orted it was determined that oxidation of internal 80 Qg8 corn onents was the cause of the occurrence. Subse uent. factory labora-7 9 80 Qg tor testin and anal sis showed the followin 7 89 80 FAC~ METHOO OF STATUS % POWER OTHER STATUS OISCOVEAY OISCOVEAY OESCAIPTION Em L~l . N A C Preo erational Test, Procedure 7 8 9 '10 12 13 44 45 46 80 FORM OF ACTIVITY CONTENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE t11I ~Z
. Z N/A N/A 7 8 9 10 11 44 45 80 P
PERSONNEL EXPOSURES N A 7 89 11 12 13 , 80 PERSONNEL INJURIES NUMBER, OESCRIPTION 7 8'9
~00 0 12
'~4 N A 11 80 PROBABLE CONSEQUENCES N A 7 89 80 LOSS OR OAMAGE TO FACILITY TYPE OESCRIPTION Z N A
- 7. '8 9 '10 80 PU8LICITY N/A 7 8 9 "80 AOOITIONAL FACTORS
[]is] See Pa es 2 and 3 for continuation of Event & Cause Descriptions.
7 8 9 80 7 89 M. A. Schop man'HONE, 3 05/552 377 9 eFO 80 eeS- eeT
v, ~
REPORTABLE OCCURRENCE 335-76-9 SUPPLEMENTARY LER NO. l PAGE TWO Event Descri tion (Continued) by Pacific Scientific snubbers.
Cause Descri tion (Continued)
S/N 000377 The front and rear caps of the snubber were removed. A thin layer of oxidation was found on the inside of both caps, and there was water inside the rear cap. The ball screw was opera-tional, and clearances between internal components were normal. However, there was a large amount of rust. sludge and water inside the center section which caused rotational binding.
The rotational binding resulted in resistance to thermal move-ment.
Also, the thrust bearing was installed incorrectly at the factory, but this did not cause the snubber malfunction.
S/N 000343 This snubber was found to have an improper end fitting (i.e.,
no ball bushing), and its indicator bar was slightly bent.
With the correct end fitting, the snubber was operational, therefore, it was not disassembled.
S/N 000525 The front and rear caps were removed and the snubber interior was found to be clean. The ball screw was operational, and the clearances between internal components were normal. However, there was slight rotational binding in the center section.
When the adaptor assembly was rotated one revolution, the snubber began to operate, but with a higher than normal resistance to movement. The adaptor assembly was removed and a small amount of oxidation was found on the thrust bearing. The amount of oxidation was considered large enough to have caused the snubber malfunction.
S/N 000695 Same description as for 000525.
REPORTABLE OCCURRENCE 335-76-9 SUPPLEMENTARY LER NO. 1 PAGE THREE Cause Descri tion (Continued)
S/N 000632 The front and rear caps were removed and the snubber interior was found to be clean. The ball screw was operational, and the clearances between internal components were normal. However, there was rotational binding in the center section. The adaptor assembly was removed and a large amount, of oxidation was found on the thrust bearing. The oxidation caused the snubber malfunction.
At I