LER-1998-001, Forwards LER 98-001-00 Providing Details Re Automatic Turbine & Reactor Trip Due to Failure of Sudden Pressure Relay on B Phase Main Transformer |
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10 CFR 50.73(a)(2)(iv), System Actuation |
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| 3281998001R00 - NRC Website |
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, Termoseee VaNey Authority Post Offee Box 2000, Soddy Dasy, Tennessee 37379 2000 I
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' Masoud Bajestani
. Site Vee President '.
Sequoyah Nudear Plant I.p 1998
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l September 28, i
f U.S. Nuclear Regulatory Commission 10~CFR 50.73 ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
i
- - TENNESSEE VALLEY AUTHORITY - - SEQUOYAH NUCLEAR PLANT- (SON) i UNIT.2
- - DOCKET NO. 50-328 - FACILITY OPERATING LICENSES
'DPR-79-- LICENSEE EVENTJREPORT (LER) 50-328/1998001.
L The enclosed -report provides' details concerning an automatic
- turbine and reactor trip,.resulting from a failure of the M
isudden. pressure relay on the
'B' phase main transformer.
l This eventLis being reported in accordance with 10iCFR 50.73 (a) (2) (iv) as an event that resulted'in a
. automatic' actuation of engineered safety features, including the reactor protection system.
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Sincerely,
&'s;tanip i
e Masoud B i
- Encloa I
cc:
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9810070097 990928 f
. PDR ADOCK 05000328 e
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l-13. S. Nuclear Regulatory Commission Page 2 September 28, 1998 Enclosure cc (Enclosure) :
INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, Georgia 30339-5957 Mr.
R.
W.
Hernan, Project Manager U.S.
Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike "V ~'
Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah' Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624
)
Regional Administrator U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 I
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| 05000327/LER-1998-001-04, :on 980519,automatic Reactor Trip Occurred. Caused by Failure of Alternate Feedwater to 1A1-A 480-volt Shutdown Board.Normal Feedwater Breaker Placed in Svc & 480- Volt Shutdown Board Returned to Operation |
- on 980519,automatic Reactor Trip Occurred. Caused by Failure of Alternate Feedwater to 1A1-A 480-volt Shutdown Board.Normal Feedwater Breaker Placed in Svc & 480- Volt Shutdown Board Returned to Operation
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) | | 05000327/LER-1998-001, Forwards LER 98-001-00 Re Unit 1 Reactor Trip Resulting from Breaker Failure.Rept Submitted IAW 10CFR50.73(a)(2)(iv) as Event or Condition,Resulted in Automatic Actuation of Esfs, Including Reactor Protection Sys | Forwards LER 98-001-00 Re Unit 1 Reactor Trip Resulting from Breaker Failure.Rept Submitted IAW 10CFR50.73(a)(2)(iv) as Event or Condition,Resulted in Automatic Actuation of Esfs, Including Reactor Protection Sys | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000328/LER-1998-001, Forwards LER 98-001-00 Providing Details Re Automatic Turbine & Reactor Trip Due to Failure of Sudden Pressure Relay on B Phase Main Transformer | Forwards LER 98-001-00 Providing Details Re Automatic Turbine & Reactor Trip Due to Failure of Sudden Pressure Relay on B Phase Main Transformer | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000328/LER-1998-001-05, :on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays |
- on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000327/LER-1998-002-03, :on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance |
- on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) | | 05000327/LER-1998-002, Forwards LER 98-002-00,providing Details Concerning Inadequate Surveillance Testing of Gas Treatment Ventilation Sys | Forwards LER 98-002-00,providing Details Concerning Inadequate Surveillance Testing of Gas Treatment Ventilation Sys | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000328/LER-1998-002, Forwards LER 98-002-00 Re Automatic Turbine & Reactor Trip, Resulting from Failure of Sudden Pressure Relay on B Phase Main Transformer | Forwards LER 98-002-00 Re Automatic Turbine & Reactor Trip, Resulting from Failure of Sudden Pressure Relay on B Phase Main Transformer | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000328/LER-1998-002-05, :on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure |
- on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000327/LER-1998-003-04, :on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced |
- on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) | | 05000327/LER-1998-003-01, :on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status |
- on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) | | 05000327/LER-1998-004-02, :on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check |
- on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000327/LER-1998-004, Forwards LER 98-004-00,providing Details Concerning Inability to Complete Surveillance within Required Time Interval | Forwards LER 98-004-00,providing Details Concerning Inability to Complete Surveillance within Required Time Interval | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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