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Category:Letter
MONTHYEARCNL-25-009, And Watts Bar Nuclear Plant, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A, Revision 262025-01-29029 January 2025 And Watts Bar Nuclear Plant, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A, Revision 26 ML25007A0782025-01-15015 January 2025 Rci/Rai Audit Letter 05000259/LER-2024-004, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2025-01-10010 January 2025 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints CNL-25-014, Response to Request for Additional Information, Set 22025-01-0808 January 2025 Response to Request for Additional Information, Set 2 ML25014A2072025-01-0808 January 2025 EPA Letter to the Mississippi Department of Environmental Quality on Browns Ferry SLR IR 05000259/20240112024-12-26026 December 2024 Biennial Problem Identification and Resolution Inspection Report 05000259/2024011, 05000260/2024011, and 05000296/2024011 ML24312A3222024-12-23023 December 2024 Issuance of Amendment Nos. 334, 357, & 317; 368 & 362; 172 & 77 Regarding Revision to TS 5.4 & 5.7.1 ML24311A1212024-12-19019 December 2024 Evaluation of Effects of Out-of-Limit Condition as Described in ASME Section XI, IWB-3720(a) ML24354A2092024-12-19019 December 2024 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inspection Service, System Procedure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear CNL-24-009, Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations2024-12-17017 December 2024 Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations CNL-24-081, Application for Subsequent Renewed Operating Licenses, Third Safety Supplement2024-12-17017 December 2024 Application for Subsequent Renewed Operating Licenses, Third Safety Supplement CNL-24-082, Central Emergency Control Center Emergency Plan Implementing Procedure Revision2024-12-17017 December 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML24347A0142024-12-12012 December 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-083, Alabama Department of Environmental Management Letter2024-12-10010 December 2024 Alabama Department of Environmental Management Letter CNL-24-049, Brows Ferry Nuclear Plant, Units 1, 2 and 3 - License Amendment Request for Adoption of TSTF-576 to Revise Safety/Relief Valve Requirements2024-12-0909 December 2024 Brows Ferry Nuclear Plant, Units 1, 2 and 3 - License Amendment Request for Adoption of TSTF-576 to Revise Safety/Relief Valve Requirements 05000296/LER-2024-004, Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping2024-12-0404 December 2024 Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping ML24332A0372024-11-27027 November 2024 Updated Report of a Deviation or Failure to Comply Associated with a Valve in the High Pressure Coolant Injection System 05000260/LER-2024-002-01, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-11-25025 November 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation IR 05000260/20240912024-11-21021 November 2024 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000260/2024091 ML24324A3332024-11-20020 November 2024 Notification of Licensed Operator Initial Examination 05000259/2025301, 05000260/2025301, 05000296/2025301 IR 05000259/20240102024-11-12012 November 2024 Design Basis Assurance Inspection Program Inspection Report 05000259/2024010 and 05000260/2024010 and 05000296/2024010 IR 05000259/20240032024-11-0404 November 2024 Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024 Application for Subsequent Renewed Operating Licenses, Second Safety Supplement ML24305A1692024-10-31031 October 2024 Site Emergency Plan Implementing Procedure Revision 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure ML24299A2632024-10-25025 October 2024 Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075 ML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24308A0042024-10-16016 October 2024 Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) 2025-01-08
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000259/LER-2024-004, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2025-01-10010 January 2025 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000296/LER-2024-004, Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping2024-12-0404 December 2024 Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping 05000260/LER-2024-002-01, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-11-25025 November 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation 05000296/LER-2024-002, Breaker Trip Automatically Started an Emergency Diesel Generator2024-04-24024 April 2024 Breaker Trip Automatically Started an Emergency Diesel Generator 05000296/LER-2024-001, Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup2024-04-22022 April 2024 Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup 05000260/LER-2024-001-01, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-04-17017 April 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure 05000259/LER-2024-001, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-04-11011 April 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure 05000260/LER-2024-001, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-02-16016 February 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure 05000259/LER-2023-003, Standby Liquid Control Inoperable Due to Demineralized Water In-Leakage2024-01-29029 January 2024 Standby Liquid Control Inoperable Due to Demineralized Water In-Leakage 05000259/LER-2022-002-01, High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator2023-10-12012 October 2023 High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator 05000260/LER-2023-001-01, Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line Due to Fatigue Failure2023-09-18018 September 2023 Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line Due to Fatigue Failure 05000260/LER-2023-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2023-08-0404 August 2023 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000296/LER-2022-003-01, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line Due to Fatigue Failure2023-07-31031 July 2023 Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line Due to Fatigue Failure 05000259/LER-2023-002, Full Reactor Scram Due to an Oscillation Power Range Monitor (OPRM) Confirmation Density Algorithm (CDA) Trip2023-07-17017 July 2023 Full Reactor Scram Due to an Oscillation Power Range Monitor (OPRM) Confirmation Density Algorithm (CDA) Trip 05000259/LER-2023-001-01, High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm2023-06-13013 June 2023 High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm 05000260/LER-2023-001, Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line2023-04-19019 April 2023 Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line 05000259/LER-2023-001, High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm2023-03-27027 March 2023 High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm 05000259/LER-2022-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2023-02-0606 February 2023 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000296/LER-2022-003, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line2023-01-31031 January 2023 Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line 05000296/LER-2022-002, Both Standby Liquid Control Subsystems Inoperable Due to an Insufficient Boron Injection Rate2022-12-19019 December 2022 Both Standby Liquid Control Subsystems Inoperable Due to an Insufficient Boron Injection Rate 05000259/LER-2022-002, High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator2022-09-12012 September 2022 High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator 05000296/LER-2022-001, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2022-07-11011 July 2022 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2021-001-01, Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay2022-07-0606 July 2022 Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay 05000259/LER-2022-001, From Browns Ferry Nuclear Plant, Unit 1 Regarding Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line2022-03-16016 March 2022 From Browns Ferry Nuclear Plant, Unit 1 Regarding Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line 05000259/LER-2021-001, Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay2021-11-22022 November 2021 Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay 05000260/LER-2021-001-01, Inoperability of a TS-required Main Steam Isolation Valve2021-08-20020 August 2021 Inoperability of a TS-required Main Steam Isolation Valve 05000260/LER-2021-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2021-08-0202 August 2021 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000260/LER-2021-001, Inoperability of a TS-required Main Steam Isolation Valve2021-06-21021 June 2021 Inoperability of a TS-required Main Steam Isolation Valve 05000259/LER-2020-003-01, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2021-04-0202 April 2021 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2020-002-01, Standby Gas Treatment System Train B Inoperable Longer than Allowed by Technical Specifications2021-02-12012 February 2021 Standby Gas Treatment System Train B Inoperable Longer than Allowed by Technical Specifications 05000259/LER-2020-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2021-02-0202 February 2021 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2020-002, Standby Gas Treatment System Train B Inoperable Longer than Allowed by Technical Specifications2020-12-14014 December 2020 Standby Gas Treatment System Train B Inoperable Longer than Allowed by Technical Specifications 05000259/LER-2020-001-01, Manual Reactor Shutdown of Two Units on Decreasing Condenser Vacuum Due to Eel Grass Intrusion2020-11-17017 November 2020 Manual Reactor Shutdown of Two Units on Decreasing Condenser Vacuum Due to Eel Grass Intrusion 05000260/LER-2020-001, For Browns Ferry Nuclear Plant, Unit 2, Core Spray System Inoperable for Longer than Permitted by Technical Specifications2020-08-31031 August 2020 For Browns Ferry Nuclear Plant, Unit 2, Core Spray System Inoperable for Longer than Permitted by Technical Specifications 05000296/LER-2020-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2020-07-0707 July 2020 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints ML20160A0232020-06-0404 June 2020 SR 2020-001-00 for Browns Ferry Nuclear Plant (Bfn),Inoperable Oscillating Power Range Monitor (OPRM) Instrumentation 05000296/LER-2020-001, Automatic Actuation of Emergency Diesel Generators Due to an Offsite Lightning Strike2020-05-0404 May 2020 Automatic Actuation of Emergency Diesel Generators Due to an Offsite Lightning Strike 05000259/LER-2020-001, For Browns Ferry Nuclear Plant, Unit 1, Inoperable Oscillating Power Range Monitor (OPRM) Instrumentation2020-03-19019 March 2020 For Browns Ferry Nuclear Plant, Unit 1, Inoperable Oscillating Power Range Monitor (OPRM) Instrumentation 05000260/LER-2019-001-01, Traversing In-core Probe Purge Header Check Valve Leak Rate in Excess of Technical Specifications Limits2019-12-19019 December 2019 Traversing In-core Probe Purge Header Check Valve Leak Rate in Excess of Technical Specifications Limits 05000260/LER-2019-003, Automatic Reactor Scram During Startup Due to Intermediate Range Monitor Noise2019-12-0202 December 2019 Automatic Reactor Scram During Startup Due to Intermediate Range Monitor Noise 05000259/LER-2019-002, Unanalyzed Condition Due to Inoperable Security Doors Following a Liqhtninq Strike2019-11-12012 November 2019 Unanalyzed Condition Due to Inoperable Security Doors Following a Liqhtninq Strike 05000259/LER-2019-001-01, High Pressure Coolant Injection System Declared Inoperable Due to Steam Supply Isolation2019-11-0707 November 2019 High Pressure Coolant Injection System Declared Inoperable Due to Steam Supply Isolation 05000259/LER-2019-001, High Pressure Coolant Injection System Declared Inoperable Due to Steam Supply Isolation2019-09-0606 September 2019 High Pressure Coolant Injection System Declared Inoperable Due to Steam Supply Isolation 05000260/LER-2019-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2019-07-18018 July 2019 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 2025-01-10
[Table view] |
LER-2077-015, For Browns Ferry Nuclear Plant, Unit 3, HPCI Turbine Speed Controller Would Not Control Turbine During Surveillance Testing |
Event date: |
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2962077015R00 - NRC Website |
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text
0 REGULATORY INFORMATION DISTRIBUTION SYSTEM
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DISTRIBUTION FOR INCOMING MATERIAL 50-296 REC:
OREILLY J P
NRC ORG:
FOX H S TN VALLEY AUTH DOCDATE: 09/19/77 DATE RCVD: 02/22/78 DOCTYPE:
LETTER NOTARIZED:
NO COPIES RECEIVED
'UBJECT:
LTR 1
ENCL 1
LICENSEE EVENT REPT'O'0 296 CONCERNING THE HPCI TURBINE SPEED CONTROLLER WHICH WOULD NOT CONTROL THE TURBINE DURING SURVEILLANCE TESTING...
PLANT NAME:BROWNS FERRY UNIT 3 REVIEWER INITIAL:
XRL DISTRIBUTOR INITIAL;
.<<<<<<<<<<<<<<<<+
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS LER
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(DISTRIBUTION CODE FO INTERNAL:
EXTERNAL:
CL I 0 E~~~W/2 ENCL LPDR'S ATHENS'L<<W/ENCL TIC<<W/ENCL ACRS CAT B<<W/0 ENCL NRC PDR<<W/ENCL DISTRIBUTION:
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1P+1P+3P ENCL 6 CONTROL NBR:
780530225 THE END
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TENNESSEE VALLEYAUTHORiTY CHATTANOOGA. TENNESSEE 37401 Mr. James P.
O'R ly, Dire'ctor U~S ~ Nuclear RQ ulatory Commission Office of Ins ction and Enfox'cement Reg'ion XI 230 Peachtr e Street,;iU., Suite 3217 Atlanta
- - orgia 30303 Deax Mr 0'a illy:
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TENNESSEE VALLEY AUTHORITY BROLiNS FERRY NUCLEAR PLANT UNIT 3 DOCKET NO ~ 50-296 FACILITY OPERATINQ LICENSE DPR-68 REPORTABLE OCCURRENCE REPORT BFRO-50-296/77/5 The enclosed report provides details concerning the HPCI turbine
.speed controller which would not control 'the turbine dur'ing surveillance testing.
This report is submitted in accordance with
.Browns Ferry unit 3 Technical Specifications, Section 6.7.2.n(2)
~
Vex'y truly.yours, TENNESSEE 'VALLEYAUTHORITY
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Director (3)
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0 7
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TYPE OESCRIPTION Q1] ~8 '/A METHOO OF OISCOVERY B
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EUENT DESCRIPTION 4
During surveillance*thsting, the AtCE turoine speed controller would'not control the turbine.
The controller was repaired and returned to service prior to completing al'he backup system testing required by section 3.5.E.2 of the limiting conditions.~
of operation in the technical specifications; therefore, only the CSS and RHR (LPCI) tests were completed.
This is a repetitive occurrence.
(BFRO-50-296/7715)
MAR:SSN 9/15/77
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DESCRIPTION
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~a N/A 7
89 10 PUBLICITY N/A 7
89 METHOD OF OTHER STATUS DISCOVERY A
B 44 45 46 44 45 7
89 Qg to the Woodward overnor failed due to an opened resistor.
DISCOVERY DESCRIPTION N A LOCATION OF RELEASE N/A 80 80 80 80 80 80 80 80 80 80 ADDITIONAL FACTORS [i(s) 7 89 N/A 80 7, 89 NAME:
PHONE'0 S>0 IIII Odt
ENT DESCRIPTION During surv'eillance testing, the HPCI turbine. speed controller would not control the turbine.
The controller was repaired and returned to service prior to completing all the backup system testing required by section 3.5.E.2 of the limiting conditions of operation in the technical specifications; therefore, only the CSS and RHR (LPCI) tests were completed.
This is a repetiti've occurrence.
(BFRO-50-296/7715)
MAR:SSN 9/15/77
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05000296/LER-2077-001, For Browns Ferry Nuclear Plant, Unit 3, Relief Valve on Pump Discharge Opened at Lower than Set Pressure During Performance of Surveillance Instruction 4.4.A.1 on Standby Liquid Control Pump 3A | For Browns Ferry Nuclear Plant, Unit 3, Relief Valve on Pump Discharge Opened at Lower than Set Pressure During Performance of Surveillance Instruction 4.4.A.1 on Standby Liquid Control Pump 3A | | 05000259/LER-2077-001, Relief Valve on Pump Discharge Opened at Lower than Set Pressure During Performance of Surveillance Instruction 4.4.A.1 on Standby Liquid Control Pump 3A | Relief Valve on Pump Discharge Opened at Lower than Set Pressure During Performance of Surveillance Instruction 4.4.A.1 on Standby Liquid Control Pump 3A | | 05000260/LER-2077-001, For Browns Ferry Nuclear Plant, Unit 2, False Alarm Would Not Clear That Was Received from Smoke Detector in Reactor Building, Elevation 565, During Normal Operation | For Browns Ferry Nuclear Plant, Unit 2, False Alarm Would Not Clear That Was Received from Smoke Detector in Reactor Building, Elevation 565, During Normal Operation | | 05000259/LER-2077-002, HPCI Restraints R-24 & R-35 on Pump Discharge Line Were Discovered with Loose Bolts & Broken Cinch Anchors Upon Completion of Operation of HPCI System During Reactor Scram on 1/26/1977 | HPCI Restraints R-24 & R-35 on Pump Discharge Line Were Discovered with Loose Bolts & Broken Cinch Anchors Upon Completion of Operation of HPCI System During Reactor Scram on 1/26/1977 | | 05000259/LER-2077-003, Reactor Low Water Level Scram Switch LIS-3-203D Failed to Operate During Routine Surveillance Testing | Reactor Low Water Level Scram Switch LIS-3-203D Failed to Operate During Routine Surveillance Testing | | 05000259/LER-2077-004, Cmflpd Exceeded Limit on 1/15 & 1/18/1977, & MAPRAT Exceeded Limit on 1/18 & 1/24/1977 | Cmflpd Exceeded Limit on 1/15 & 1/18/1977, & MAPRAT Exceeded Limit on 1/18 & 1/24/1977 | | 05000260/LER-2077-004, For Browns Ferry Nuclear Plant, Unit 2, Two Heat Detectors in the Fire Protection System for the Recirculation MG Sets Which, Would Not Alarm | For Browns Ferry Nuclear Plant, Unit 2, Two Heat Detectors in the Fire Protection System for the Recirculation MG Sets Which, Would Not Alarm | | 05000296/LER-2077-005, For Browns Ferry Nuclear Plant, Unit 3, RPS MG Set a Which Continued Running & MG Set B Output Breaker Which Did Not Trip During Startup Test STI-31, Which Is Supplementing Previous Letter of 3/24/1977 | For Browns Ferry Nuclear Plant, Unit 3, RPS MG Set a Which Continued Running & MG Set B Output Breaker Which Did Not Trip During Startup Test STI-31, Which Is Supplementing Previous Letter of 3/24/1977 | | 05000260/LER-2077-005, For Browns Ferry Nuclear Plant, Unit 2, Drywall Oxygen Sensor 02M-76-43 Became Erratic During Normal Operation & Read Erroneously High Because of Grounded Shields | For Browns Ferry Nuclear Plant, Unit 2, Drywall Oxygen Sensor 02M-76-43 Became Erratic During Normal Operation & Read Erroneously High Because of Grounded Shields | | 05000259/LER-2077-005, A & B RPS MG Sets Failed to Trip During Startup Test, ST1 31, Loss of T-G, and Off Site Power Test | A & B RPS MG Sets Failed to Trip During Startup Test, ST1 31, Loss of T-G, and Off Site Power Test | | 05000260/LER-2077-006, For Browns Ferry Nuclear Plant, Unit 2, Unit Being Shut Down as Specified by Technical Specification 3.6.F.3 Due to the 2B Reactor Recirculation Motor-Generator Set Being Out of Service Greater than 24 Hours | For Browns Ferry Nuclear Plant, Unit 2, Unit Being Shut Down as Specified by Technical Specification 3.6.F.3 Due to the 2B Reactor Recirculation Motor-Generator Set Being Out of Service Greater than 24 Hours | | 05000259/LER-2077-006, Drywell High Pressure Switch PS-64-56A Exceeded Technical Specification Limit of 2.00 Psig by 0.04 Psi 6 During Normal Operation | Drywell High Pressure Switch PS-64-56A Exceeded Technical Specification Limit of 2.00 Psig by 0.04 Psi 6 During Normal Operation | | 05000296/LER-2077-007, For Browns Ferry Nuclear Plant, Unit 3, Torus Oxygen Sensor O2M-76-42 Failed to Calibrate to 2-Percent Oxygen Calibration Gas During Normal Operation | For Browns Ferry Nuclear Plant, Unit 3, Torus Oxygen Sensor O2M-76-42 Failed to Calibrate to 2-Percent Oxygen Calibration Gas During Normal Operation | | 05000259/LER-2077-007, Torus Oxygen Sensor O2M-76-42 Failed to Calibrate to 2-percent Oxygen Calibration Gas During Normal Operation | Torus Oxygen Sensor O2M-76-42 Failed to Calibrate to 2-percent Oxygen Calibration Gas During Normal Operation | | 05000260/LER-2077-007, For Browns Ferry Nuclear Plant, Unit 2, Limiting Critical Power Ratio-Ratio (Cprrat) Changed from .988 to 1.009 After Local Power Range Monitors (Lprms) Were Calibrated During Steady-State Operation at 97-Percent Power | For Browns Ferry Nuclear Plant, Unit 2, Limiting Critical Power Ratio-Ratio (Cprrat) Changed from .988 to 1.009 After Local Power Range Monitors (Lprms) Were Calibrated During Steady-State Operation at 97-Percent Power | | 05000296/LER-2077-008, For Browns Ferry Nuclear Plant, Unit 3, Relief Valve on Discharge of Standby Liquid Control Pump 3A Was Observed to Open at 1300 Psig Instead of Designed Setting of 1400 Psig & Stuck in Partially Open Position During Performanc | For Browns Ferry Nuclear Plant, Unit 3, Relief Valve on Discharge of Standby Liquid Control Pump 3A Was Observed to Open at 1300 Psig Instead of Designed Setting of 1400 Psig & Stuck in Partially Open Position During Performance of . | | 05000260/LER-2077-008, For Browns Ferry Nuclear Plant, Unit 2, Random Failure of Two Isolation Valves in One Traversing Incore Probe (Txp) Tube Could Not Have Been Closed If Required Between 2045 Hours on 3/16/1977, & 0100 Hours on 3/17/1977 | For Browns Ferry Nuclear Plant, Unit 2, Random Failure of Two Isolation Valves in One Traversing Incore Probe (Txp) Tube Could Not Have Been Closed If Required Between 2045 Hours on 3/16/1977, & 0100 Hours on 3/17/1977 | | 05000260/LER-2077-009, For Browns Ferry Nuclear Plant, Unit 2, Notification by NSSS Vendor, Minimum Critical Power Ratio Limit, as Determined by Analysis of Turbine Trip Without Bypass, Should Be 1.29 for Power Operation with Core Average Exposure | For Browns Ferry Nuclear Plant, Unit 2, Notification by NSSS Vendor, Minimum Critical Power Ratio Limit, as Determined by Analysis of Turbine Trip Without Bypass, Should Be 1.29 for Power Operation with Core Average Exposure . | | 05000259/LER-2077-009, Smoke Detector in Reactor Building Gave a False Alarm for Fire Protection Zone Due to Increased Detector Sensitivity During Normal Operation | Smoke Detector in Reactor Building Gave a False Alarm for Fire Protection Zone Due to Increased Detector Sensitivity During Normal Operation | | 05000260/LER-2077-010, For Browns Ferry Nuclear Plant, Unit 2, Drywell Oxygen Sensor 202M-76-43 Became Erratic During Normal Operation | For Browns Ferry Nuclear Plant, Unit 2, Drywell Oxygen Sensor 202M-76-43 Became Erratic During Normal Operation | | 05000296/LER-2077-010, For Browns Ferry Nuclear Plant, Unit 3, HPCI Turbine Steam Supply Valve 3-FCV-73-16 Failed to Open During Performance of an Operability Surveillance Instruction | For Browns Ferry Nuclear Plant, Unit 3, HPCI Turbine Steam Supply Valve 3-FCV-73-16 Failed to Open During Performance of an Operability Surveillance Instruction | | 05000259/LER-2077-011, Reactor Water Column B Reference Leg Was Low, Producing a +20-inch Error in Two Reactor Water low-level Scram Switches During Startup from Cold Shutdown | Reactor Water Column B Reference Leg Was Low, Producing a +20-inch Error in Two Reactor Water low-level Scram Switches During Startup from Cold Shutdown | | 05000296/LER-2077-011, For Browns Ferry Nuclear Plant, Unit 3, Smoke Detector in Spreading Room B Gave False Alarm Due to Increased Detector Sensitivity During Routine Startup Operation | For Browns Ferry Nuclear Plant, Unit 3, Smoke Detector in Spreading Room B Gave False Alarm Due to Increased Detector Sensitivity During Routine Startup Operation | | 05000260/LER-2077-012, For Browns Ferry Nuclear Plant, Unit 2, Two Hydraulic Snubbers Were Found Inoperable During the Performance of Surveillance Instruction 4.6.H | For Browns Ferry Nuclear Plant, Unit 2, Two Hydraulic Snubbers Were Found Inoperable During the Performance of Surveillance Instruction 4.6.H | | 05000296/LER-2077-012, For Browns Ferry Nuclear Plant, Unit 3, Problems with Offgas System Occurred Between July 7 and July 15, 1977 | For Browns Ferry Nuclear Plant, Unit 3, Problems with Offgas System Occurred Between July 7 and July 15, 1977 | | 05000296/LER-2077-013, For Browns Ferry Nuclear Plant, Unit 3, SLC Pump 3A Discharge Relief Valve Lifted at 1275 Psig During Surveillance Testing When Pump Was Started Against Throttled Test Valve Set at That Pressure | For Browns Ferry Nuclear Plant, Unit 3, SLC Pump 3A Discharge Relief Valve Lifted at 1275 Psig During Surveillance Testing When Pump Was Started Against Throttled Test Valve Set at That Pressure | | 05000296/LER-2077-014, For Browns Ferry Nuclear Plant, Unit 3, Unidentified Leakage Inside the Drywell Had Exceeded 5 Gpm During Routine Monitoring of Control Room Meters | For Browns Ferry Nuclear Plant, Unit 3, Unidentified Leakage Inside the Drywell Had Exceeded 5 Gpm During Routine Monitoring of Control Room Meters | | 05000296/LER-2077-015, For Browns Ferry Nuclear Plant, Unit 3, HPCI Turbine Speed Controller Would Not Control Turbine During Surveillance Testing | For Browns Ferry Nuclear Plant, Unit 3, HPCI Turbine Speed Controller Would Not Control Turbine During Surveillance Testing | | 05000296/LER-2077-016, For Browns Ferry Nuclear Plant, Unit 3, Torus Oxygen Sensor O2M-76-42 Failed to Operate Properly During Normal Operation | For Browns Ferry Nuclear Plant, Unit 3, Torus Oxygen Sensor O2M-76-42 Failed to Operate Properly During Normal Operation | | 05000296/LER-2077-017, For Browns Ferry Nuclear Plant, Unit 3, Primary Containment Isolation Valve 3-FCV-77-2A on Drywell Floor Drain Sump Pump Discharge Line Would Not Operate as Required by Tech Spec 3.7.D.L During Routine Operability Checks | For Browns Ferry Nuclear Plant, Unit 3, Primary Containment Isolation Valve 3-FCV-77-2A on Drywell Floor Drain Sump Pump Discharge Line Would Not Operate as Required by Tech Spec 3.7.D.L During Routine Operability Checks | |
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