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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
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
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'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
~os ccav 8
CATFGORY 57 58 TYPE
~z, 59 SOURCE L
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
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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
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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.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
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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