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| FLORIO'OV'iR < uGv> car.'.~;,~ ~ | | FLORIO'OV'iR < uGv> car.'.~;,~ ~ |
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| Very truly yours, chmidt ice President Power Resources MAS:pg cc: Jack R, Newman, Esquire Director, Office of Inspection and Enforcement (30) | | 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! | | Director, Office of Management Information and Program Control (3) nL paCKETKa! |
| Q$ 8KQ ggQ jg1S7 | | Q$ 8KQ ggQ jg1S7 g |
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| g QQC g () | | g QQC g () |
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| LICENSEE EVENT REPORT CONTRQL BLOCK: (PLEASE PRINT ALL REQOIRED INFORIVIATION). | | LICENSEE EVENT REPORT CONTRQL BLOCK: (PLEASE PRINT ALL REQOIRED INFORIVIATION). |
| UCENSEE UCENSE EVENT NAME LICENSE NUMBER TYPE TYPE 01 F L 0 0 0' 4 | | UCENSEE UCENSE EVENT NAME LICENSE NUMBER TYPE TYPE 01 F L 0 0 0' 4 |
| .7 89 14 15 25 26 30 31 32 | | .7 89 14 15 25 26 30 31 32 REPORT REPORT |
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| , CATEBORY TYPE SOURCE OOCKET NUMBER EVENT OATE REPORT OATE | | , CATEBORY TYPE SOURCE OOCKET NUMBER EVENT OATE REPORT OATE |
| [OD1]OON'T~ L ~L 0 5 0 .0 '3, 3ii3 0 7 0 3 '7 6 0 8 0 5 7 6 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION 7 | | [OD1]OON'T~ L ~L 0 5 0 .0 '3, 3ii3 0 7 0 3 '7 6 0 8 0 5 7 6 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION 7 |
| @02 8 9 W i um in water from the rimar water tank to the s ent fuel ool | | @02 8 9 W i um in water from the rimar water tank to the s ent fuel ool 80 top3] operations personnel found that the Refueling Water Tank (RWT) was 7 89 80 Qp~] overflowing. The valve lineup was checked and a crossover valve 7 8 9 80 |
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| 80 top3] operations personnel found that the Refueling Water Tank (RWT) was 7 89 80 Qp~] overflowing. The valve lineup was checked and a crossover valve 7 8 9 80 | |
| ~05 between the RWT and the spent fuel pool system was found open. The "7 89 80 tOOI valve was closed and the RWT was recirculated in order to get a; 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT COOE COO E COMPONENT COOE SUPPlKA MANUFACTURER VclATKlN | | ~05 between the RWT and the spent fuel pool system was found open. The "7 89 80 tOOI valve was closed and the RWT was recirculated in order to get a; 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT COOE COO E COMPONENT COOE SUPPlKA MANUFACTURER VclATKlN |
| [P] ~RB 7 8 9 | | [P] ~RB 7 8 9 |
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| REPORTABLE OCC -~/CD 335-. 76-33 LICENSEE EVENT @PORT PAGE TWO I | | REPORTABLE OCC -~/CD 335-. 76-33 LICENSEE EVENT @PORT PAGE TWO I |
| l; representative boron concentration sample. Sample analysis ind'zca e d a boron or 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 cond occurrence at St. Lucie Unit 1 affecting a borated secon t source I however,I the two occurrences were un related with respect to cause. The first occurrence (335-7 6-32 ) involved a leaking gasket on a relief valve in the boric acid makeup system. (335-76-33) . | | l; representative boron concentration sample. Sample analysis ind'zca e d a boron or 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 cond occurrence at St. Lucie Unit 1 affecting a borated secon t source I however,I the two occurrences were un related with respect to cause. The first occurrence (335-7 6-32 ) involved a leaking gasket on a relief valve in the boric acid makeup system. (335-76-33) . |
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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
NII0 I:ofIM-106 ' u.s. NucLEAn nrouI.ATonv cof sfoN Docllr T NUMoFB 50-335 I2 70)
F ILc NUMOEfl NRC DISTRIBUTION ron PART 60 DOCI(ET MATI:-RIAL INCIDI hIT HI'".VOHT TO: FROM: DATC OF DOCUMCNT Florida Power & Light Company 8/5/76 Mr. Norman,C ~ Moseley Miami, Florida- DATE flCCCIVCD A. D. Schmi.dt 8/12/76 Lc TTcn QNOTOBIZED pnop INPUT FoflM NUMOEB OF COPIES BECFIVED QonfoINAI. UN C LASS IF I E D
+copv One signed copy DCSCfIII'TION ENCLOSURE Ltr. 'trans the following: 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 (1-P) ( ) DO NOT REMOVE PLANT NAME; NOTE: IFi PERSONNEL EXPOSURE IS INVOLVED
'St. Lucie 81 SEND DIRECTLY TO KREGEH/J..COLLINS FOR ACTION/INFORMATION aHANCH CHIEF: n M CYS i<OR ACTION TIC..ASST.: Di s W CYS CYS HOLDTNG SEN'm ACHS
'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 EXTERNAI. DISTRIBUTION CONTROL NUMBER LPDH.
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August 5, 1976 PRN-LI-76-198 Mr. Norman C. Moseley, Director, Region II ~<NI':
Office of Inspe'ction and Enforcement U. S. Nuclear Regulatory Commission 230 Peachtree Street, N.W., Suite 818 AUGl21976 ~ "~~
Atlanta, Georgia 30303 g P> ~clthk NCQA'~X
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Dear Mr. Moseley:
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!
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LICENSEE EVENT REPORT CONTROL BLOCK: (P E PRINT ALL REQUIRED INFORMATION]
1 L&cNSEE UCENSE CLIENT NAME UCENSE NUM8ER TYPE TYPE 01- F L 0 0 0 4
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7 89 14 15 25 26 30 31 32
'EPORT REPORT 7
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CATFGORY 57 58 TYPE
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60 61 0
'OCKET 5 0 NUM8ER 0 3 3 68 69 07057'608057 EVENT OATS 74 75 REPORT OATE 6
80 '
QOg 7 8 9 W 'm EVENT DESCRIPTION in water from the rimar water tank to the s ent fuel ool operations personnel found that the Refueling Water Tank (RWT) was 80 =
Qpg 7 89 80 tOgpj overflowing. The valve lineup was checked and a crossover valve 7 8 9 ~
eo between the RWT 'and the spent fuel pool system was found open. The
~
[os]
7 8 9 80 Qo g valve was closed and'he RWT was recirculated'n order to get a es PAME 80 e SYSTEM CAUSE COMPONENT COMPONENT Q077 7 8 9 10 COOE
~RB COOE
~A 11 12 A C COMPONENT COOE C U M U 17 SUPPLER
~A 43 44 C 3 l MANUFACTURER 0
47 VC CAUSE DESCRIPTION Qo 8 A crossover valve between the RWT and the s ent fuel ool s stem was 7 8 9 80 tocm inadvertently left open causing the RWT boron concentration to be 7 8 9 80 Q~O diluted below 1720 m.
7 89 METHOO OF 80 OTHER STATUS OISCOVERY OISCOVERY OESCRIPTION Q~g N A N A a 9 10 12 13 44 45 46 80 FORM OF ACTMTY CO@TENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Hl 7 8 9 LzJ IzJ 10 11 44 45 N A 80 PERSONNEL EXPOSURES NUMSER TYPE OESCRIPTION
[~$ 3 [gJgi JJJ [zJ N A as 11 12 13 PERSONNEL INJURIES OESCRIPTION
~4 oo o N/A 7 8 9 11 12 80 PROBABLE CONSEQUENCES
~15 N/A 7 8 9 80 LOSS OR DAMAGE TO FACIUTY TYPE OESCRIPTION
. z N/A 7 89 ~ 10 80 PUBLICITY N/A 7 89 ~ 80 ADDITIONAL'ACTORS
+18 See Pa e 2 for continuation of Event Description 7 8 9 80 7 89 80 NAME: N- A. Scho oman PHONE: 305 552 3779 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).
UCENSEE UCENSE EVENT NAME LICENSE NUMBER TYPE TYPE 01 F L 0 0 0' 4
.7 89 14 15 25 26 30 31 32 REPORT REPORT
, CATEBORY TYPE SOURCE OOCKET NUMBER EVENT OATE REPORT OATE
[OD1]OON'T~ L ~L 0 5 0 .0 '3, 3ii3 0 7 0 3 '7 6 0 8 0 5 7 6 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION 7
@02 8 9 W i um in water from the rimar water tank to the s ent fuel ool 80 top3] operations personnel found that the Refueling Water Tank (RWT) was 7 89 80 Qp~] overflowing. The valve lineup was checked and a crossover valve 7 8 9 80
~05 between the RWT and the spent fuel pool system was found open. The "7 89 80 tOOI valve was closed and the RWT was recirculated in order to get a; 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT COOE COO E COMPONENT COOE SUPPlKA MANUFACTURER VclATKlN
[P] ~RB 7 8 9
~A A C C U M U ~A C 3 3 0: N 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 7 8 9 80
~09 inadvextently left open causing the RWT boron concentration to be 7 8 9 80
, Q~O diluted below .1'720 m.
7 89 80 FACIUTY METHOO OF 7 8 STATUS 9
[rJ FORM OF
~B 10 POWER 12 13 OTHER STATUS N A 44 OISCOVERY Ll 45 46 OISCOVERY OESCRIPTION N A 80 ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE KRI N A 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION 7
[~@3 8 9
~IJJJ 11
~z 12 13 N A 80 PERSONNEL INJURIES NUMBER OESCRIPTION
~4 ~oo 0 N A 7 89 11 12 80 PROBABLE CONSEQUENCES QS] N/A 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION z N/A 7 89 10 80 PUBLICITY
[is~] N/A 7 8 9 ~ 80 ADDITIONAL for continuation of FACTORS'18]
See Pa e 2 Event Description 7 8 9 80 7 89 80 NAME M. A. scho man PHONE.305 552 3779 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 ind'zca e d a boron or 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 cond occurrence at St. Lucie Unit 1 affecting a borated secon t source I however,I the two occurrences were un related with respect to cause. The first occurrence (335-7 6-32 ) involved a leaking gasket on a relief valve in the boric acid makeup system. (335-76-33) .
A t 1