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Category:Letter
MONTHYEARIR 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 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 1 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
[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
NII 0 I:ofIM-106 I2 70)'u.s.NucLEAn nrouI.ATonv cof sfoN Docllr T NUMoFB 50-335 NRC DISTRIBUTION ron PART 60 DOCI(ET MATI:-RIAL F ILc NUMOEfl INCIDI hIT HI'".VOHT TO: Lc TTcn QonfoINAI.
+copv DCSCfIII'TION QNOTOBIZED UN C LASS IF I E D Mr.Norman,C~Moseley pnop INPUT FoflM ENCLOSURE FROM: Florida Power&Light Company Miami, Florida-A.D.Schmi.dt DATC OF DOCUMCNT 8/5/76 DATE flCCCIVCD 8/12/76 NUMOEB OF COPIES BECFIVED One signed copy Ltr.'trans the following:
PLANT NAME;'St.Lucie 81 (1-P)Li.censee Event Report (RO 50-335/76-33) on 7/5/76 concerning'the Refueling Mater Tank overflowing while pumping water from the primary water tank to the spent fuel, pool~ACKNOWLEDGED
()DO NOT REMOVE NOTE: IFi PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGEH/J..COLLINS aHANCH CHIEF: M CYS i<OR ACTION TIC..ASST.:
W CYS ACHS CYS HOLDTNG SEN'm n Di s FOR ACTION/INFORMATION
'NTERNAL 0 IST Rl BUTION NHC PDR ICE 2 hIIPC SCHROEDEH IPPOLITO HOUSTON NOVAK CHECK GRIMES CASE HlTLEH'ANAUER TEDESCO hIACCARY EISENIIUT P~R SHAO VOLLhlEH ZmrCH KHEGER J.COLLINS LPDH.TIC: EXTERNAI.DISTRIBUTION CONTROL NUMBER r , r F Pt V f~.AO 4 E l~C 1
'/II//g l:-: FLORIO'OV'iR
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~August 5, 1976 PRN-LI-76-198 Mr.Norman C.Moseley, Director, Region II Office of Inspe'ction and Enforcement U.S.Nuclear Regulatory Commission 230 Peachtree Street, N.W., Suite 818 Atlanta, Georgia 30303
Dear Mr.Moseley:
~<NI': AUGl21976~"~~g P>~clthk NCQA'~X+-'ow~isso>i
'MJ/glow lp REPORTABLE OCCURRENCE 335-76-33 ST.LUCIE UNIT 1 DATE OF OCCURRENCE:
JULY 5,'1'976 REFUELING WATER TANK 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, chmidt ice President Power Resources MAS:pg cc: Jack R, Newman, Esquire Director, Office of Inspection and Enforcement (30)Director, Office of Management Information and Program Control (3)nL paCKETKa!Q$8KQ ggQ jg1S7Žg lg(g'c gyral'EAR RE~()g g peg QQC~g~~los LICENSEE EVENT REPORT CONTROL BLOCK: 1 L&cNSEE NAME 01-F L UCENSE NUM8ER 0 0 0 7 89 14'EPORT CATFGORY TYPE~os ccav~~z, 7 8 57 58 59 15 REPORT SOURCE'OCKET NUM8ER L 0 5 0-0 3 3 60 61 (P E PRINT ALL REQUIRED INFORMATION]
UCENSE CLIENT TYPE TYPE 4 25 26 30 31 32 6 80'EVENT OATS REPORT OATE 07057'608057 68 69 74 75 EVENT DESCRIPTION QOg W'm in water from the rimar water tank to the s ent fuel ool 7 8 9 Qpg operations personnel found that the Refueling Water Tank (RWT)was 80=7 89 80 tOgpj overflowing.
The valve lineup was checked and a crossover valve 7 8 9~~eo[os]between the RWT'and the spent fuel pool system was found open.The 7 8 9 Qo g valve was closed and'he RWT was recirculated'n order to get a 80 47 es PAME SYSTEM CAUSE COMPONENT COMPONENT COOE COOE COMPONENT COOE SUPPLER MANUFACTURER VC Q077~RB~A A C C U M U~A C 3 l 0 7 8 9 10 11 12 17 43 44 CAUSE DESCRIPTION Qo 8 A crossover valve between the RWT and the s ent fuel ool s stem was 80 e 7 8 9 tocm inadvertently left open causing the RWT boron concentration to be 7 8 9 Q~O diluted below 1720 m.80 80 OTHER STATUS N A 7 8 9 LOSS OR DAMAGE TO FACIUTY TYPE OESCRIPTION
.z 7 89~10 PUBLICITY 7 89 Q~g a 9 10 12 13 FORM OF ACTMTY CO@TENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY Hl LzJ IzJ 7 8 9 10 11 PERSONNEL EXPOSURES NUMSER TYPE OESCRIPTION
[~$3[gJgi JJJ[zJ as 11 12 13 PERSONNEL IN JURIES OESCRIPTION
~4 oo o 7 8 9 11 12 PROBABLE CONSEQUENCES
~15 METHOO OF OISCOVERY 44 45 46 44 45 N A N/A N/A N/A N/A OISCOVERY OESCRIPTION N A LOCATION OF RELEASE N A 80 80 80 80 80 80 7 89 ADDITIONAL'ACTORS
+18 See Pa e 2 for continuation of Event Description 7 8 9~80 80 7 89 NAME: N-A.Scho oman PHONE: 305 552 3779 80 CPO 88I~gCT REPORTABLE OCCUR CE 335-76-33 L~CQNSEE EVENT REPORT PAGE TWO representative boron concentration sample.Sample analysis indicated a boron concentration of 1653 ppm which was below-the minimum boron concentration of 1720 ppm specified in Technical Specification 3.5.4.Concentrated boric acid was added and a'ample taken one hour later indicated a boron concentration greater that 1720 ppm.This was the second occurrence at St.Lucie Unit 1 affecting a borated water source, however, the two occurrences were unrelated with respect to cause.The first occurrence (335-76-32) involved a leaking gasket on a relief valve in the boric acid makeup system.(335-76-33).
'a P.O.BOX 3100 MIAMI, FLORIDA 33101 FLORIDA POWER 5 LIGIIT COMPANY August 5, 1976 PRN-LI-76-198 (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 76-33 ST.LUCXE UNXT 1 DATE OF OCCURRENCE:
'ULY 5,1'976 REFUELXNG WATER TANK 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, chai,dt Vice President Power Resources MAS pg cc: Jack R, Newman, Esquire Director, Office of Xnspection and Enforcement (30)Director, Office of Management Xnformation and Program Control (3)HELPING BUILD FLORIDA LICENSEE EVENT REPORT CONTRQL BLOCK: (PLEASE PRINT ALL REQOIRED INFORIVIATION).
01 F L.7 89 UCENSEE NAME LICENSE NUMBER 0 0 0'14 15 4 25 26 UCENSE TYPE EVENT TYPE 30 31 32" REPORT REPORT , CATEBORY TYPE SOURCE OOCKET NUMBER EVENT OATE[OD1]OON'T~
L~L 0 5 0-.0'3, 3ii3 0 7 0 3'7 7 8 57 58 59 60 61 68 69 REPORT OATE 6 0 8 0 5 7 6 74 75 80 EVENT DESCRIPTION
@02 W i um in water from the.rimar water tank to the s ent fuel ool 7 8 9 top3]operations personnel found that the Refueling Water Tank (RWT)was 7 89 Qp~]overflowing.
The valve lineup was checked and a crossover valve 7 8 9~05 between the RWT and the spent fuel pool system was found open.The"7 89 tOOI valve was closed and the RWT was recirculated in order to get a;N 7 8 9~09 inadvextently left open causing the RWT boron concentration to be 7 8 9 PRME SYSTEM CAUSE COMPONENT COMPONENT COOE COO E COMPONENT COOE SUPPlKA MANUFACTURER VclATKlN[P]~RB~A A C C U M U~A C 3 3 0: 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION A crossover valve between the RWT and the s ent fuel ool s stem was 80 80 80 80 80 80 OTHER STATUS N A 7 8 9 , Q~O diluted below.1'720 m.7 89 FACIUTY STATUS POWER[rJ~B 7 8 9 10 12 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY KRI 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION
[~@3~IJJJ~z 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER OESCRIPTION
~4~oo 0 7 89 11 12 PROBABLE CONSEQUENCES QS]7 8 9 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION z 7 89 10 PUBLICITY[is~]7 8 9 METHOO OF OISCOVERY Ll 44 45 46 44 45 N A N A N/A N/A N/A OISCOVERY OESCRIPTION N A LOCATION OF RELEASE N A 80 80 80 80 80 80 80 80~80 ADDITIONAL FACTORS'18]
See Pa e 2 for continuation of Event Description 7 8 9 80 7 89 NAME M.A.scho man PHONE.305 552 3779 80 GPO Gbl dGT v-I i, REPORTABLE OCC-~/CD 335-.76-33 LICENSEE EVENT@PORT PAGE TWO'I l;representative boron concentration sample.Sample analysis in zca e a or d'd a boron concentration of 1653 ppm, which was below s ecified in the minimum boron concentration of 1720 ppm speci Technical Specification 3.5.4.Concentrated boric a'cid was added and a sample taken one hour later indicated a boron concentration greater that 1720 ppm.This was the secon cond occurrence at St.Lucie Unit 1 affecting a borated related with t source however, the two occurrences were un respect to cause.The first occurrence (335-7-)I I 6-32 involved a leaking gasket on a relief valve in the boric acid makeup system.(335-76-33)
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