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Category:Letter
MONTHYEARIR 05000335/20240052024-08-22022 August 2024 Updated Inspection Plan for St. Lucie, Units 1 & 2 - Report 05000335/2024005 and 05000389/2024005 IR 05000335/20240022024-08-13013 August 2024 Integrated Inspection Report 05000335-2024002 and 05000389-2024002 L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis 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 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 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-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 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 L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes ML24078A2622024-03-26026 March 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML24058A1572024-03-19019 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-023, Unusual or Important Environmental Event - Turtle Mortality2024-03-0606 March 2024 Unusual or Important Environmental Event - Turtle Mortality L-2024-015, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report IR 05000335/20230062024-02-28028 February 2024 Annual Assessment Letter for St Lucie Units 1 & 2 - Report 05000335/2023006 and 05000389/2023006 L-2024-029, 2023 Annual Operating Report2024-02-28028 February 2024 2023 Annual Operating Report L-2024-026, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-02-27027 February 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules IR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) IR 05000335/20230042024-01-24024 January 2024 – Integrated Inspection Report 05000335/2023004 and 05000389/2023004 L-2024-004, 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 to 20 Years2024-01-18018 January 2024 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 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 2024-08-07
[Table view] 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
[Table view] |
Text
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$ 0-'3 ARC DISTRIBUTION Q PART "0 DOC!(ET MATERIAL FILE NUM(II:n XNCXDEIIT.REPORT Mr Moseley FROlorida Pwr 6 Light Co DATE OF DOCUMENT Miami, 'Fla. 7-8-76 A D SCSmidt . DATE RECEIVED 7-le-76 l'6Bi:E TTE n QNOTORIZED':- ~ PROP INPUT FORM NUMSER OF COPtEP gECFIVED I QORIGINAL',,
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Ltr trans the, following: Licensee Event Report '(R0876-29) on I6-8-76 concerning failure to perform surveilance-of seismic inst'ruments.....
PLANT NAME:
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FLORIDA POYY.R R LIGHI'OP IPARY July 8, 1976 PRN-LI-76-175 I ~
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Mr. Norman C. Moseley, Director, Region II Office of Inspection and Enforcement.
U. S. Nuclear Regulatory Commission 230 Peachtree Street, N.N., Suite 818 Atlanta, Georgia 30303 Dear Mr. Moseley." ~8OR I e<~
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REPORTABLE OCCURRENCE 335-76-29 ST. LUCIE UNIT 1 DATE OF OCCURRENCE: JUNE 8, 1976 SEISMIC INSTRUMENT SURVEILLANCE 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, lg
~saic
-'JUL, *g g-.;
D. c idt , 9 u.s.
3 Vice President JNGII S Power Resources MAS/ms Attachment cc: Jack R. Newman, Esquire Director, Office of Inspection and Enforcement (30)
Director, Office of Management Information and Program Control (3)
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CONTROL 8LOCK: ASE PRINT ALL REQIjIRED INFORMATION) 1 4
UCENSEE UCENSE EVENT
'AMC LCKNSE NUMSEA TYPE TYPE
[oaf F L S L S 1 0 0 0 0 0 0 0 0 4 1 1 1 1 ~03
~
7 89 14 15 25 26 30 31 32 REPORT. REPORT CATEGORY TYPE SOURCE ~
OOCXET NUMSEA EVENT OATE REPORT OATS
~01 CON'T 0 6 0 8 7 6 0 7 0 8 7 6 7 8 57 58 59 60 61 68 69 74 75 60 EVENT OESCRIPTION '
Qp g 'Contrary to Technical Specification 4.3 .3.3.1, the required channel 7 8 9 80
[QQ3]
check of two triaxia 1 ace e 1 erographs was not performed wit:hin the 7 8 9 80 Qo4 required time frame. A containment entry was procedurally required as 60 0 5 to perform this check but, because the reactor was operating.,at 50 '
as percent power, t
it was decided not to make the. entry.
The required 60
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~0 6 The surveillance procedure as originally written required a containment 7 8 9 60 Iocms entry in order to perform the instrum'entation check. Following this FACILITY occurrence, the procedure was r'evised to permit the instrument. ation 7 89 METHOO OF STATUS % FOWER OTHER STATUS OISCOVEAY OISCOVEAY OESCALPTION Jig ~s ~os o N/A N/A 7 8 9 10 12 13 44 45 46 80 FOAM OF ACTIVITY CQATKNT
~ RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATIOQgg RELEASE O'H LJ LJ N/A 7 s s 10 11 44 ..45 80 PERSONNEL FXPOSURES EH as LLLJ Zl 12 13 N/A 60 PERSONNEL INJURIES N/A 7 8 9 11 12 80 PROBABLE CONSEQUENCES Q~g N/A 7 89 LOSS OR DAMAGE 'TO FACILITY TYPE OESCAIPTIQN 2 N/A 7 89 10 PU8LICITY N/A 7 89 AOOITIONAL FACTORS See page 2 for continuation of Event Description and Cause Description.
7 8 9 80 7 89 NAME. M. A. Scho man PHONE: 305/552-3779 CPO S ~ I~ S ~T
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0 REPORTABLE OCCURRENCE 335-76-29 LICENSEE EVENT REPORT PAGE TWO Event Descri tion.(continued) surveillance was performed satisfactorily during a scheduled plant shutdown 3 days after the due date. This was the first occurrence of this type at St. Lucie Unit l. (335-76-29).
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Cause Descri tion (continued) check .to be performed without requiring containment entry.
".-"'-The"manufactur'e'r .'con'cur'reB 'wi;th"the-revis'ion""'.":".'".'~ "".:::" "~-""'""".-".:"-'-~':
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P.O. BOX 013100, MIAMI, FLORIDA 3310I Vlf'+
FLORIDA POWER 8; LIGHT COMPANY July 8, 1976 PRN-LI-76-175 Mr. Norman C. Moseley, Director, Region II Office of Inspection and,Enforcement U. S. Nuclear Regulatory Commission 230 Peachtree Street, N.Ã., Suite 818 Atlanta, Georgia 30303
Dear Mr. Moseley:
REPORTABLE OCCURRENCE 335-76-29 ST.. LUCIE,UNIT 1 DATE OF OCCURRENCE: JUNE 8, 1976 SEISMIC INSTRUMENT SURVEILLANCE 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
~Y idt Vice President Power Resources MAS/ms Attachment cc Jack R. Newman, Esquire Director, Office of Inspection and Enforcement (30)
Director, Office of Management Information and Program Control (3)
HELPING BUILD FLORIDA
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40 1 7 LICENSEE EVENT REPO ~"
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CONTROL BLOCK: (PLEA88 PRINT ALL REQUIRED INFORMATION7 1
UCENSEE UCENSE EVENT NAME LICENSE NUMBEA TYPE TYPE
[oa~] F L S L S 1 0 p p 0 0 0 0 0 4 1 1 1 1 ~03 7 89 14 15 25 26 30 31 32 REPORT REPORT OOCKET NUMBER EVENT DATE REPORT OATE 0 5 0 0 3 3 5 0 6 0 8 7 6 0 7 0 8 7 6 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION Q~ 2 Contrary to Technical Specification 4.3.3.3.1, the required channel 7 8 9 80
[QQ3]
check of two triaxial accelerographs was not perf ormed within the 7 89 80 tOO~j required time frame. A containment entry was procedurally required 7 8 9 80 m to perform this check but, beca'use'he;:reactor"was~operating..at;50 7 8 9 percent .power, it was decided not to make the. entry. The required 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT SUPPUEA MANUFACTUREA A K 1 3 0 N 7 8 9 10 11 12 17 44 47 48 CAUSE DESCRIPTION
[oOeJ The surveillance procedure as originally written required a containment 7 8 9 80
+0 9 entry in order to perform the instrumentation check. Following this 7 8 9
/ 0 occurrence, the procedure was revised to permit the xnstrumentat son 80 7 89 80 FACILITY METHOO OF STATUS 5 POWER OTHER STATUS OISCOVEAY OISCOVEAY OESCAIPTION s ~os o N/A b N/A 7 8 9 10 12 13 44 45 46 80 FOAM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATIOglg RELEASE z z N/A 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES N/A 7 8 9 11 12 13 80 PERSONNEL INJURIES OESCAIPTION N/A 7 89 11 12 80 PROBABLE CONSEQUENCES N/A 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION
~Z N/A 7 89 10 80 PUBLICITY N/A 7 8 9 80 ADDITIONAL for continuation of Event Description Description.
FACTORS'ee page 2 and Cause 7 89 80 7 89 80 M. A. Scho man PHONE 305/552 3779 CPO IIdl ~ 0(IT
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REPORTABLE OCCURRENCE 335-76-29 LICENSEE EVENT REPORT PAGE TWO Event Descri 'tion (continued) surveillance was performed satisfactorily during a scheduled plant shutdown 3 days after the due date.'his was the first occurrence of this type at St. Lucie Unit l. (335-.76-29).
Cause Descri tion (continued) check to be performed without requiring containment entry.
The manufacturer concurred with the revision.
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