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Category:Letter
MONTHYEARML24353A1542024-12-20020 December 2024 Final Audit Summary Report in Support of Review of License Amendment Requests ML24352A2612024-12-18018 December 2024 Notification of Licensed Operator Initial Examination 05000250/2025302 and 05000251/2025302 ML24344A0772024-12-12012 December 2024 Authorized Alternative to Requirements of the American Society of Mechanical Engineers Operation and Maintenance Code L-2024-199, Special Report - Post Accident Monitoring Instrumentation2024-12-10010 December 2024 Special Report - Post Accident Monitoring Instrumentation L-2024-191, Reply to a Notice of Violation: NOV 05000250/2024003 and 05000251/20240032024-11-22022 November 2024 Reply to a Notice of Violation: NOV 05000250/2024003 and 05000251/2024003 IR 05000250/20240032024-11-13013 November 2024 Integrated Inspection Report - 05000250/2024003 & 05000251/2024003 & Notice of Violation L-2024-187, Supplement to the Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-11-12012 November 2024 Supplement to the Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-188, Supplement to License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-11-12012 November 2024 Supplement to License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24305A1482024-11-0606 November 2024 Westinghouse Topical Report - Request for Withholding Information from Public Disclosure L-2024-184, Radiological Emergency Plan Revision 772024-11-0505 November 2024 Radiological Emergency Plan Revision 77 ML24276A2162024-11-0101 November 2024 Request for Withholding Information from Public Disclosure L-2024-173, Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-31031 October 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-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 L-2024-175, Cycle 34 Core Operating Report2024-10-24024 October 2024 Cycle 34 Core Operating Report ML24291A2882024-10-24024 October 2024 Westinghouse Topical Report - Request for Withholding Information from Public Disclosure L-2024-177, Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-10-22022 October 2024 Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24276A2302024-10-16016 October 2024 Westinghouse Topical Report – Request for Withholding Information from Public Disclosure ML24289A2372024-10-15015 October 2024 Transmittal of Revision 1 Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles 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-2024-118, 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) IR 05000250/20243012024-10-0303 October 2024 NRC Operator License Examination Report 05000250/2024301 and 05000251/2024301 L-2024-157, Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-0303 October 2024 Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-147, Submission of Periodic Reports2024-10-0101 October 2024 Submission of Periodic Reports 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 ML24269A1292024-09-24024 September 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24262A2272024-09-18018 September 2024 Transmittal of Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles ML24260A2262024-09-18018 September 2024 NRC Examination Results Summary - Examination Reports: 05000250/2024301 and 05000251/2024301 ML24158A0052024-09-17017 September 2024 Completion of Subsequent License Renewal Site Specific Environmental Review and Modification to Subsequent Renewed Facility Operating Licenses 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 ML24256A1132024-09-13013 September 2024 Regulatory Audit Summary Related to the Review of Regarding the Updated Spent Fuel Pool Criticality Safety Analysis License Amendment Request ML24207A0342024-09-13013 September 2024 – Exemption from Certain Requirements of 10 CFR 50.46 for Use of Axiom Fuel Rod Cladding – Letter IR 05000250/20240052024-08-23023 August 2024 Updated Inspection Plan for Turkey Point Units 3 & 4 - Report 05000250/2024005 and 05000251/2024005 ML24234A0062024-08-22022 August 2024 Project Manager Assignment L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 IR 05000250/20240112024-08-0606 August 2024 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000250/2024011 and 05000251/2024011 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections 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-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal 05000250/LER-2024-002-01, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project 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 IR 05000250/20244012024-06-0505 June 2024 – Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401 L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 2024-09-25
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000250/LER-2024-002-01, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications 05000250/LER-2024-002, 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications2024-04-11011 April 2024 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications 05000250/LER-2023-004, Unplanned Automatic Scram During RPS Testing2023-12-13013 December 2023 Unplanned Automatic Scram During RPS Testing 05000250/LER-2023-003, Grid Disturbance in Switchyard Causes Automatic Reactor Trip2023-11-20020 November 2023 Grid Disturbance in Switchyard Causes Automatic Reactor Trip ML23318A1782023-11-13013 November 2023 FAQ 23-03- Turkey Point IE01 05000250/LER-2023-002, Manual Reactor Trip Due to Steam Generator Feedwater Regulating Valve Positioner Failure2023-10-0202 October 2023 Manual Reactor Trip Due to Steam Generator Feedwater Regulating Valve Positioner Failure 05000250/LER-2023-001, RCS Pressure Boundary Degraded2023-06-14014 June 2023 RCS Pressure Boundary Degraded 05000250/LER-2021-003, Regarding Auxiliary Feedwater Actuation Due to Feedwater Isolation During Plant Shutdown2021-12-0202 December 2021 Regarding Auxiliary Feedwater Actuation Due to Feedwater Isolation During Plant Shutdown 05000250/LER-2021-002, Unrecognized Technical Specification Surveillance Requirement Non-Compliance2021-06-0303 June 2021 Unrecognized Technical Specification Surveillance Requirement Non-Compliance 05000250/LER-2021-001, Automatic Reactor Trip Due to Reactor Trip Breaker Cell Switch Malfunction2021-04-29029 April 2021 Automatic Reactor Trip Due to Reactor Trip Breaker Cell Switch Malfunction 05000250/LER-2020-005-01, Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel (Rev 1)2021-03-0505 March 2021 Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel (Rev 1) 05000250/LER-2020-002-01, Manual Reactor Trip in Response to High Steam Generator Level Following Inadve1ient Opening of Feedwater Heater Bypass Valve (Rev 1)2021-03-0505 March 2021 Manual Reactor Trip in Response to High Steam Generator Level Following Inadve1ient Opening of Feedwater Heater Bypass Valve (Rev 1) 05000250/LER-2020-005, Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel2020-10-14014 October 2020 Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel 05000250/LER-2020-004, Re Manual Reactor Trip in Response to Automatic Trip of the 3B Steam Generator Feedwater Pump2020-10-0707 October 2020 Re Manual Reactor Trip in Response to Automatic Trip of the 3B Steam Generator Feedwater Pump 05000250/LER-2020-003, Automatic Reactor Trip Due to High Source Range Flux During Reactor Startup2020-09-29029 September 2020 Automatic Reactor Trip Due to High Source Range Flux During Reactor Startup 05000250/LER-2020-002, Re Manual Reactor Trip in Response to High Steam Generator Level Following Inadvertent Opening of Feedwater Heater Bypass Valve2020-09-23023 September 2020 Re Manual Reactor Trip in Response to High Steam Generator Level Following Inadvertent Opening of Feedwater Heater Bypass Valve 05000251/LER-2020-001, Automatic Reactor Trip Caused by Main Generator Lockout Due to Exciter Fault2020-08-28028 August 2020 Automatic Reactor Trip Caused by Main Generator Lockout Due to Exciter Fault 05000250/LER-2020-001, Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection System (RPS) and Engineered Safety Feature Actuation System (ESFAS) Instrument Channel Functional Units2020-06-24024 June 2020 Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection System (RPS) and Engineered Safety Feature Actuation System (ESFAS) Instrument Channel Functional Units L-2019-127, Manual Reactor Trip Following Grid Disturbance2019-06-27027 June 2019 Manual Reactor Trip Following Grid Disturbance 05000250/LER-2018-001, Inoperable Containment Purge Exhaust Penetration2018-11-21021 November 2018 Inoperable Containment Purge Exhaust Penetration 05000250/LER-2018-002, As-Found Cycle 29 Main Steam Safety Valve Setpoints Outside Technical Specification Limits2018-11-21021 November 2018 As-Found Cycle 29 Main Steam Safety Valve Setpoints Outside Technical Specification Limits 05000251/LER-2018-001, Inoperable Auxiliary Feedwater Steam Supply Flowpath2018-06-27027 June 2018 Inoperable Auxiliary Feedwater Steam Supply Flowpath 05000251/LER-1917-001, Regarding Manual Reactor Trip Due to Lowering Steam Generator Level Caused by Loss of Flow Regulating Valve Positioner Control2017-11-0707 November 2017 Regarding Manual Reactor Trip Due to Lowering Steam Generator Level Caused by Loss of Flow Regulating Valve Positioner Control 05000250/LER-1917-001, Regarding Loss of 3A 4kV Vital Bus Results in Reactor Trip, Safety System Actuations, and Loss of Safety Injection Function2017-05-16016 May 2017 Regarding Loss of 3A 4kV Vital Bus Results in Reactor Trip, Safety System Actuations, and Loss of Safety Injection Function L-2017-090, LER Special Report Regarding Accident Monitoring Instrumentation2017-05-11011 May 2017 LER Special Report Regarding Accident Monitoring Instrumentation 05000251/LER-2016-001, Regarding Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection Instrument Channel2016-06-30030 June 2016 Regarding Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection Instrument Channel 05000250/LER-2016-001, Regarding Loose Breaker Control Power Fuse Caused the 3B Emergency Containment Cooler to Be Inoperable Longer than Allowed2016-04-0707 April 2016 Regarding Loose Breaker Control Power Fuse Caused the 3B Emergency Containment Cooler to Be Inoperable Longer than Allowed 05000250/LER-2015-001, Regarding Diesel Generator Start Resulting from Switchyard Protective Relay Actuation2016-01-19019 January 2016 Regarding Diesel Generator Start Resulting from Switchyard Protective Relay Actuation L-2015-217, Turkey, Unit 3 - Special Report Regarding Accident Monitoring Instrumentation2015-08-27027 August 2015 Turkey, Unit 3 - Special Report Regarding Accident Monitoring Instrumentation 05000251/LER-2015-002, Regarding Reactor Trip Resulting from Generator Differential Lockout2015-07-13013 July 2015 Regarding Reactor Trip Resulting from Generator Differential Lockout 05000251/LER-2015-001, Regarding Automatic Auxiliary Feedwater System Actuation During a Planned Reactor Trip2015-01-29029 January 2015 Regarding Automatic Auxiliary Feedwater System Actuation During a Planned Reactor Trip 05000251/LER-2014-003, Regarding Emergency Containment Cooler Safety Function Impacted During Breaker Replacement2014-11-10010 November 2014 Regarding Emergency Containment Cooler Safety Function Impacted During Breaker Replacement 05000250/LER-2014-004, Regarding Ultimate Heat Sink Temperature Limit Exceeded Due to Environmental Conditions2014-09-18018 September 2014 Regarding Ultimate Heat Sink Temperature Limit Exceeded Due to Environmental Conditions 05000251/LER-2014-001, Regarding Incorrect Feedwater Flow Transmitter Calibration Caused RPS Channels to Be Inoperable2014-06-24024 June 2014 Regarding Incorrect Feedwater Flow Transmitter Calibration Caused RPS Channels to Be Inoperable 05000250/LER-2014-003, Regarding Manual Actuation of the Reactor Protection System Due to Failure of Group Step Counter2014-06-18018 June 2014 Regarding Manual Actuation of the Reactor Protection System Due to Failure of Group Step Counter 05000250/LER-2014-002, Regarding Reactor Coolant System Pressure Boundary Leakage at Pressurizer Heater Sleeve Attachment Weld2014-05-15015 May 2014 Regarding Reactor Coolant System Pressure Boundary Leakage at Pressurizer Heater Sleeve Attachment Weld L-2014-139, Special Report Regarding Accident Monitoring Instrumentation2014-05-14014 May 2014 Special Report Regarding Accident Monitoring Instrumentation 05000251/LER-2014-002, Regarding Automatic Actuation of the Reactor Protection System Due to Low Main Condenser Vacuum2014-04-24024 April 2014 Regarding Automatic Actuation of the Reactor Protection System Due to Low Main Condenser Vacuum 05000250/LER-2014-001, Regarding Missed Surveillance Test Resulted in a SG Pressure Instrument Channel to Be Inoperable Longer than AOT2014-03-0404 March 2014 Regarding Missed Surveillance Test Resulted in a SG Pressure Instrument Channel to Be Inoperable Longer than AOT 05000250/LER-2013-009, Regarding Loose Breaker Control Power Fuse Holder Caused 3B Jcw Pump to Be Inoperable Longer than AOT2013-11-27027 November 2013 Regarding Loose Breaker Control Power Fuse Holder Caused 3B Jcw Pump to Be Inoperable Longer than AOT 05000250/LER-2013-008, Regarding Through-Wall Leak in 3A CCW Pump Threaded Fitting Caused Pump to Be Inoperable Longer than AOT2013-08-19019 August 2013 Regarding Through-Wall Leak in 3A CCW Pump Threaded Fitting Caused Pump to Be Inoperable Longer than AOT 05000250/LER-2013-007, Regarding Manual Reactor Trip Due to Generator Load Drop2013-07-0808 July 2013 Regarding Manual Reactor Trip Due to Generator Load Drop 05000251/LER-2013-002, Reactor Trip Due to Loss of Offsite Power Resulting from Generator Testing2013-06-18018 June 2013 Reactor Trip Due to Loss of Offsite Power Resulting from Generator Testing 05000251/LER-2013-001, Regarding Power Operated Relief Valve Inoperable for Greater than Allowed Outage Time Due to Lifted Leads2013-05-22022 May 2013 Regarding Power Operated Relief Valve Inoperable for Greater than Allowed Outage Time Due to Lifted Leads 05000250/LER-2013-006, Regarding Reactor Protection and Auxiliary Feed Water System Actuations Due to Trip of Operating Feed Water Pumps2013-05-13013 May 2013 Regarding Reactor Protection and Auxiliary Feed Water System Actuations Due to Trip of Operating Feed Water Pumps 05000250/LER-2013-005, Reactor Trip Due to Turbine Header Pressure Spike While Testing Turbine Control Valves2013-05-10010 May 2013 Reactor Trip Due to Turbine Header Pressure Spike While Testing Turbine Control Valves 05000250/LER-2013-004, Safety Injection Flow Path Not Isolated Due to Manual Valve Out of Position2013-04-29029 April 2013 Safety Injection Flow Path Not Isolated Due to Manual Valve Out of Position 05000250/LER-2013-003, Regarding Manual Reactor Trip Due to Increasing Reactor Coolant Pump Seal Leakage2013-04-19019 April 2013 Regarding Manual Reactor Trip Due to Increasing Reactor Coolant Pump Seal Leakage 05000250/LER-2013-002, Regarding Automatic Reactor Trip Due to Low Condenser Vacuum2013-04-11011 April 2013 Regarding Automatic Reactor Trip Due to Low Condenser Vacuum 05000250/LER-2013-001, Regarding Procedure Noncompliance Causes Incorrect Instrument Setting and Condition Prohibited by Technical Specifications2013-03-0101 March 2013 Regarding Procedure Noncompliance Causes Incorrect Instrument Setting and Condition Prohibited by Technical Specifications 2024-07-10
[Table view] |
Text
N)+C FORM 195 I2.7SI DOCKFT NUMBER wO-FILE NUMBER INCIDENT REPORT Florida Pwr & Light Co Miami, Fla A D Schmidt Mr Moseley DATE OF DOCUMENT0--
DATE RECEIVED 10 18 76 ONOTORIZED XUNCLASSIFIF D HLETTER OORIGINAL 2fcor v PROP INPUT FORM NUMBER OF COPIES RECEIVED DESCRIPTION ENCLOSURE CORRECTION TO:
a Licensee Evnet Report (R($76-6) on 7-26-76 MIXCH zecgear6edntripping of g4 generator lockout action......
Ltr trans the following:
NOTE; IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J..COLLINS Turkey Point 8'4 FOR ACTION/INFORMATION r)m~7,H Cn~~:
W CYS FOR ACTION LIC..ASST.:
W CYS ACRS CYS ISTRI BUTION INTERNAL D REG FIXE NR~DR IREE 2
MIPC i SCHROEDER IPPOLITO HOUSK)N NOVAK CIIECK GRIMES CASE TEDESCO MACCARY EISENHUT BAER SHAO VOLLMER 8JNCH KI EGER J.COLLINS CONTROL NUMBER EXTERNALDISTRIBUTION QXQ~
U.S. NUCLEAR REGULATORY MISSION NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL
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FLORIO'O'4V R & LIGH" COMPANY October 6,
1976 PRN-LI-76-250 Nr. Norman C. lioseley, Director, Region II Office of Inspection and Enforcement U.
S. Nuclear Regulatory Commission 230 Peachtree
- Street, N. N., Suite 818 Atlanta, Georgia 30303
Dear Nr. Hoseley:
REPORTABLE OCCURRENCE 251-76-6 TURKEY POINT UNI' DATE OF OCCURRENCE:
JULY 26, 1976 eKEVEs
OCT1B I97BL p Sq I;., 'E
<<REGVihroRy JP C ghII~ION hIeN ~I CORRECT ION A Licensee Event Report for the subject occurrence was sent to you on August 25, 1976.
The last sentence of the Cause Description stated that a followup investigation was being conducted as ment'oned in previous Reportable Occurrence Report 250-72-2.
Tne referenced report numbe is incorrect and should be changed to 250-76-2.
A corrected Licensee Event Report is attached.
Very truly yours, Vice President Power Resources.
OOCKETE0 VSNRQ OCT 181
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'< ~ is hiell.
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Jack R.
- Newman, Esquire Director, Office of Inspection and Enforcement (40)
Director, Office of llanagement In ormation and Program Control (3)
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Lqenerator lockout action.
The startu transformer breaker (4B 4l60 7
8 0 Jog LVolt Bus >>o.
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Reportable Occurrence 251-76-6 Licensee Event Report Papa Two Event Description (continued) making full contact which prevented the breaker from closing.
Previous occurrences involving this.,type breaker have been described in Reports 3-72-3, 3-72-'4, 250-74-2, 250-75-4, 250-75-5, 250-75-6, 251-75-8 and 250-76-2.
(25l-76-6).
Cause Description (continued) being conducted by the Off-Site Support Staff as mentioned in Report 250-76-2 will include the operation of tn=s switch.
FLORIDA POWER 5 LIGHT COMPANY October 6,
1976 PRN-LI-76-250 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:
ggfy~
'+1 REPORTABLE OCCURRENCE 251-76-6
~/
v, TURKEY POINT UNIT 4 DATE OF OCCURRENCE:
JULY 26, 1976 CORRECTION A Licensee Event Report for the subject occurrence was sent to you on August 25, 1976.
The last sentence of the Cause Description stated that a followup investigation was being conducted as mentioned in previous Reportable Occurrence Report 250-72-2.
The referenced report number is incorrect and should be changed to 250-76-2.
A corrected Licensee Event Report is attached.
Very truly yours, Vice President Power Resources MAS/cpc Attachment CC Jack R.
- Newman, Esc(uire Director, Office of Inspection and Enforcement (40)
Director, Office of Management Information and Program Control (3)
HELPING BUILD FLORIDA
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L!CENSEE EVENT con"soL BLoe'(:~gjJ REPORT As'= ~rnl."iT ALLREGUIP.=-a)
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EV=i'4T OESCPIPTION t002 Durin normal stead state o eration, the No.
4 Generator was tripped by a9I qenexator lockout acti.on.
The startuo transformer breaker (48 4l60 7
89 Q0J Volt 80 Bus No.
4N26456) failed to close durinq the automatic transfer J
Kl tnlj6 deener ized Xns ecti.on of the breaker showed that the FFFF svFitch was not J
80 7
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8 9 80 05 se uence from the auxi3.iar transformer.
This left the 4B 4160 Volt Bus CAUSE OESCRIPT!Oi'4 zz Lx='.~-'
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Abraham PHONE 305/552-3779 r ~ ~
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Reportable Occurrence 251-76-6 Licensee Event Report
. Page Two Event Description (continued) making full contact which prevented the breaker from closing.
Previous occurrences involving this, type breaker have been described in Reports 3-72-3, 3-72-4, 250-74-2, 250-75-4, 250-75-5, 250-75-6, 251-75-8 and 250-76'-2.
(251-76-6)
Cause Description (continued) being conducted by the Off-Site Support Staff as mentioned in Report 250-76-2 Iwill include the operation of th-s switch.
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