text
NRC FORM 366 (4-95)
U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
APPROVED BY OMB NO. 31504104 EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORYINFORMATIONCOLLECTlON REQUEST:
60.0 HRS.
REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE UCENSING PROCESS AND FED BACK TO INDUSTRY. FORWARD COMMENTS REGARDING 8URDEN ESTIMATE TO THE INFORMATIONAND RECORDS MANAGEMENT BRANCH (TA F33).
U.S.
NUCLEAR REGULATORYCOMMISSION, WASHINGTON,DC2~ 1, FACILITYNAIIE II)
Browns Ferry Nuclear Plant (BFN) Unit 3 DOCKET NUllSER (I) 05000296 FACE P) 1 OF6 TITLE ie)
Loss of the Emergency Core Cooling Systems (ECCS) Division I Instrumentation Renders ECCS Equipment Inoperable.
EVENT DATE 5 LER NUMBER 6 REPORT DATE OTHER FACIUTIES INVOLVED 8 07 DAY YEAR 17 96 SEQUENTIAL REVISION NUM8ER NUMBER 96
004
00 08 DAY YEAR 16 96 FACIUTY N/A FACIUTYNAM N/A OPERATING MODE (9)
POWER LEVEL (10)
N 100 20.2201(b) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(v) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(i)(B) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(viii) 50.73(a)(2)(x) 73.71 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR: (Check one or moro) (11) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20,2203(a)(4) 50.36(c)(1) 50.36(c)(2)
UCENSEE CONTACT FOR THIS LER (12) 50.73(a)(2)(iv) 50.73(a)(2)(v)
X 50.73(a)(2)(vii)
OTHER Speci/y In Abstract below or in NRC Form 366A NAMF TELEPHONE NUMBER 0oervde Atee Code)
James E. Wallace, Compliance Licensing Engineer (205) 729-7874 COMPLETE ONE UNE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13
CAUSE
SYSTEM COMPONENT MANUFACTURER
' ','AUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS X
AD SCR H177 X
AD FU B569 AD INVT H177 SUPPLEMENTAL REPORT EXPECTED (14)
YES (Ifyes, complete EXPECTED SUBMISSION DATE).
NO EXPECTED SUBMISSION DATE (15)
MONTH DAY YEAR 10 30 96 ABSTRACT (Limitto 1400 spaces, l.e., approximately 15 single-spaced typewritten lines) (16)
On July 17, 1996, with Units 2 and 3 at approximately 100 percent power and Unit 1 shutdown and defueled, Unit 3 operators declared ECCS Division I instrumentation inoperable, in accordance with TS 3.2.B. This event was presumed to be caused by a failed control board in the ECCS Division I Analog Trip Unit Invefter, which resulted in the loss of the inverter output.
Unit 3 entered several limiting condition for operations (LCO) and prepared to shut the unit down.
Operators initiated troubleshooting that found a cleared fuse, a shorted silicon control rectifier, and the failed ATU Inverter control board.
The failed components were replaced, the ECCS instrumentation was declared operable, and the LCOs were exited.
On August 6, 1998, a second similar event occurred.
When TVA has determined the root causes and corrective actions for these events, TVAwill provide a supplemental report.
This report is being submitted in accordance with 10 CFR 50.73 (a)(2)(vii) as any event where a single cause or condition caused at least one independent train or channel to become inoperable in multiple systems.
Previous LERs on similar events were: 260/94001, 260/94006, and 260/94010.
9608220104 960816 PDR ADDCK 05000296 S
PDR
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NRC FORM ~MBA
. (4-95)
U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FAGILITX NAME DOCKET PAGE Browns Ferry Unit 3 05000296 NUMBER NUMBER 6 of 6 96 --
004 00 TEXT more space rs requrr, use rrrooa copes orm (17) failure.
- However, the root cause of the event was determined to be a failure of the ECCS ATU Inverter control board.
Since this event occurred on a different unit, the corrective actions taken in LER 260/94001 would not have precluded this event (296/96004).
LER 260/94006 described the failure of an ECCS Division I ATU
- Inverter, 250v DC reactor motor operator valve (RMOV) breaker trip.
This ECCS RMOV breaker tripped as a result of 'a shorted SCR.
Therefore,
corrective actions
taken for LER 260/94006 would not have precluded this event (296/96004).
LER 260/94010 addressed the failure of Cl capacitor in the Division II ATU Inverter capacitor bank.
This failed capacitor was a result of a manufacturing defect.
Therefore, corrective actions for LER 260/94010 would not have precluded this event '(296/96004).
TVA has had previous similar events.
At this time, TVA believes that corrective actions taken to resolve those events would not have precluded this event.
- However, due to the aggzegate of these
- events, TVA is conducting a broader evaluation of inverter problems.
Consequently, TVA's current presumption that past
'inverter problems were separate and isolated may change.
This evaluation result will be addressed in the supplemental report.
VZZ.
CQbRCZQKENTS TVA expects to submit a supplemental report by October 30, 1996.
Energy Industry Identification System (EIIS) system and component, codes are identified in the text with brackets (e.g.,
[XX)).
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| 05000259/LER-1996-001-01, :on 960121,Unit 1/2 B DG Auto Started During Local Panel Testing.Caused by Failure of Blocking Diode in Start Failure Circuitry.Failed Diode Replaced & Panel Alarm Pushbutton Annuciation Circuitry Checked |
- on 960121,Unit 1/2 B DG Auto Started During Local Panel Testing.Caused by Failure of Blocking Diode in Start Failure Circuitry.Failed Diode Replaced & Panel Alarm Pushbutton Annuciation Circuitry Checked
| 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) | | 05000296/LER-1996-001-04, :on 960229,reactor Scrammed After APRM High Flux Scram Signal Because of Partial Closure of Turbine Control Valves Due to Faulty EHC Frequency/Voltage Converter Card.Main Turbine Manually Tripped & Faulty Card Replaced |
- on 960229,reactor Scrammed After APRM High Flux Scram Signal Because of Partial Closure of Turbine Control Valves Due to Faulty EHC Frequency/Voltage Converter Card.Main Turbine Manually Tripped & Faulty Card Replaced
| 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)(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 10 CFR 50.73(a)(2)(viii) | | 05000260/LER-1996-001-03, :on 960216,10CFR50 App R Noncompliance Resulted in Plant Being Outside Design Basis & Being in Condition Not Covered by Plant Operating Instructions.Initiated Problem Evaluation |
- on 960216,10CFR50 App R Noncompliance Resulted in Plant Being Outside Design Basis & Being in Condition Not Covered by Plant Operating Instructions.Initiated Problem Evaluation
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(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 10 CFR 50.73(a)(2)(viii) | | 05000260/LER-1996-001, :on 960216,discovered That 10CFR50 App R Noncompliance Condition Existed Due to Failures to Correctly Implement Design Criteria During Original Development of App R Programs.Fire Watches Established |
- on 960216,discovered That 10CFR50 App R Noncompliance Condition Existed Due to Failures to Correctly Implement Design Criteria During Original Development of App R Programs.Fire Watches Established
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(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 10 CFR 50.73(a)(2)(viii) | | 05000259/LER-1996-002-02, :on 960328,EDG auto-started Due to Undervoltage Condition as Result of Personnel Error.Functional Tests on Breakers Associated W/Shutdown Bus Stopped & EDG Shutdown & Placed in Standby Readiness |
- on 960328,EDG auto-started Due to Undervoltage Condition as Result of Personnel Error.Functional Tests on Breakers Associated W/Shutdown Bus Stopped & EDG Shutdown & Placed in Standby Readiness
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) | | 05000296/LER-1996-002-04, :on 960421,unit Scrammed Following Loss of Reactor Feed Pump 3C.Caused by Personnel Error.Personnel Stabilized Reactor,Reactor Feed Pump 3C Isolated & Reactor Feed Pump 3C Oil Tank Refilled |
- on 960421,unit Scrammed Following Loss of Reactor Feed Pump 3C.Caused by Personnel Error.Personnel Stabilized Reactor,Reactor Feed Pump 3C Isolated & Reactor Feed Pump 3C Oil Tank Refilled
| 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)(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 10 CFR 50.73(a)(2)(viii) | | 05000260/LER-1996-002-03, :on 960323 & 24,main Steam Isolation Valve Leak Rates Exceeded Acceptance Criteria.Caused by Excessive Leakage on a & C Inboard MSIV Line Valves.Leaking Valves Investigated |
- on 960323 & 24,main Steam Isolation Valve Leak Rates Exceeded Acceptance Criteria.Caused by Excessive Leakage on a & C Inboard MSIV Line Valves.Leaking Valves Investigated
| 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)(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 10 CFR 50.73(a)(2)(viii) | | 05000259/LER-1996-003-03, :on 960403,Unit 2 Received Unplanned ESF Actuation.Caused by Electrician Introduced Fault Into ECCS Logic While Preparing Wires for Termination in Panel 2-9-81. Problem Evaluation Rept Initiated |
- on 960403,Unit 2 Received Unplanned ESF Actuation.Caused by Electrician Introduced Fault Into ECCS Logic While Preparing Wires for Termination in Panel 2-9-81. Problem Evaluation Rept Initiated
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) | | 05000296/LER-1996-003-04, :on 960501,unit 3 Scrammed on Low Reactor Water Level.Caused by Failure of Steam Packing Exhauster by Pass Flow Control Valve.Valve Replaced |
- on 960501,unit 3 Scrammed on Low Reactor Water Level.Caused by Failure of Steam Packing Exhauster by Pass Flow Control Valve.Valve Replaced
| 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)(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 10 CFR 50.73(a)(2) | | 05000260/LER-1996-003-02, :on 960328,determined That Fuel Movement Performed W/Inoperable Refueling Interlock.Caused by Misinterpretation of TS Requirements.Fuel Movement Activities Discontinued |
- on 960328,determined That Fuel Movement Performed W/Inoperable Refueling Interlock.Caused by Misinterpretation of TS Requirements.Fuel Movement Activities Discontinued
| 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000296/LER-1996-004, :on 960717,loss of ECCS Division I & Division II Instrumentation Renders ECCS Equipment Inoperable.Caused by Loss of Inverter Output.Failed Components Replaced in Atu Inverter Circuitry & Instrumentation Logic Restored |
- on 960717,loss of ECCS Division I & Division II Instrumentation Renders ECCS Equipment Inoperable.Caused by Loss of Inverter Output.Failed Components Replaced in Atu Inverter Circuitry & Instrumentation Logic Restored
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000296/LER-1996-004-01, Forwards LER 96-004-01,clarifying Analysis of Event Section Which Div I & II ECCS Equipment Remained Operable for Automatic Initiation | Forwards LER 96-004-01,clarifying Analysis of Event Section Which Div I & II ECCS Equipment Remained Operable for Automatic Initiation | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000296/LER-1996-004-03, :on 960717,ECCS Division I Instrumentation Rendered ECCS Equipment Inoperable.Caused by Loss of Inverter Output.Cleared Fuse,Shorted SCR & Failed Inverter Control Board Was Replaced in ECCS Division I Atu Inverter |
- on 960717,ECCS Division I Instrumentation Rendered ECCS Equipment Inoperable.Caused by Loss of Inverter Output.Cleared Fuse,Shorted SCR & Failed Inverter Control Board Was Replaced in ECCS Division I Atu Inverter
| 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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 10 CFR 50.73(a)(2)(viii) | | 05000260/LER-1996-004-01, :on 960425,Unit 2 SRV Pilot Cartridges Failed Setpoint Acceptance Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints Deviating.Valves Currently Being Retested & Recertified |
- on 960425,Unit 2 SRV Pilot Cartridges Failed Setpoint Acceptance Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints Deviating.Valves Currently Being Retested & Recertified
| 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)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) 10 CFR 50.73(e)(2)(x) | | 05000296/LER-1996-004-02, Forwards LER 96-004-02,providing Root Causes for Four Failures of ECCS Inverters.Revision Bars Identify Where Changes Made | Forwards LER 96-004-02,providing Root Causes for Four Failures of ECCS Inverters.Revision Bars Identify Where Changes Made | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000260/LER-1996-005-01, :on 960510,unit Automatically Scrammed on Low Reactor Water Level Due to Runback of Reactor Feed Pumps. Caused by Inadequate Design of Digital Feedwater Control Sys Software.Design Change Implemented |
- on 960510,unit Automatically Scrammed on Low Reactor Water Level Due to Runback of Reactor Feed Pumps. Caused by Inadequate Design of Digital Feedwater Control Sys Software.Design Change Implemented
| 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000296/LER-1996-005-03, :on 960915,reactor Scrammed as Required by TSs Due to Trip of Reactor Recirculation Motor Generator Set 3A. Caused by Bus Bar in Generator Armature Circuit Failing. Collector Rings Were Replaced |
- on 960915,reactor Scrammed as Required by TSs Due to Trip of Reactor Recirculation Motor Generator Set 3A. Caused by Bus Bar in Generator Armature Circuit Failing. Collector Rings Were Replaced
| 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)(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 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(s)(2)(viii) | | 05000260/LER-1996-005, Forwards LER 96-005-00 Re Unit 2 Automatic Scram on Low Reactor Water Level Occurred | Forwards LER 96-005-00 Re Unit 2 Automatic Scram on Low Reactor Water Level Occurred | 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000296/LER-1996-006-03, :on 961106,loss of ECCS Div 1 Instrumentation Rendered ECCS Equipment Inoperable.Caused by Cleared Fuse in ECCS Div.Fuse Replaced & Addl Testing to Challenge Replacement Fuse Performed |
- on 961106,loss of ECCS Div 1 Instrumentation Rendered ECCS Equipment Inoperable.Caused by Cleared Fuse in ECCS Div.Fuse Replaced & Addl Testing to Challenge Replacement Fuse Performed
| 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)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(s)(2)(ii) 10 CFR 50.73(s)(2) 10 CFR 50.73(s)(2)(iii) | | 05000260/LER-1996-006-01, :on 960402,process for Determination of Generic SLMCPR Values Might Not Always Give Most Conservative Result.Administrative Controls Instituted,Colr Revised & Amend Request Submitted |
- on 960402,process for Determination of Generic SLMCPR Values Might Not Always Give Most Conservative Result.Administrative Controls Instituted,Colr Revised & Amend Request Submitted
| 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)(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 10 CFR 50.73(a)(2)(viii) | | 05000260/LER-1996-007-02, :on 961029,Unit 2 Scram on Turbine Control Valve Fast Closure Occurred Due to Loss of Excitation to Main Generator.Exciter Brushes Inspected & Replaced & Procedures Revised |
- on 961029,Unit 2 Scram on Turbine Control Valve Fast Closure Occurred Due to Loss of Excitation to Main Generator.Exciter Brushes Inspected & Replaced & Procedures Revised
| 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)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(s)(2)(v) 10 CFR 50.73(s)(2)(viii) 10 CFR 50.73(s)(2)(iii) | | 05000296/LER-1996-007, Forwards LER 96-007-00 Re Unplanned Esf.Caused by Inadequate Planning of step-text Work Order That Did Not Fully Isolate Circuit Prior to Adding External Power Supply | Forwards LER 96-007-00 Re Unplanned Esf.Caused by Inadequate Planning of step-text Work Order That Did Not Fully Isolate Circuit Prior to Adding External Power Supply | | | 05000296/LER-1996-007-04, On 961213,engineered Safety Feature Actuations Resulting from Inadequate Planning of step-text Work Order Occurred.Tripped Breaker Reset & LCO Condition Exited | On 961213,engineered Safety Feature Actuations Resulting from Inadequate Planning of step-text Work Order Occurred.Tripped Breaker Reset & LCO Condition Exited | 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(b)(2)(ii) | | 05000260/LER-1996-008-02, :on 961101,MS SR Valves Exceeded TS Required Setpoint Limit as Result of Disc/Seat Bonding.Caused by Corrosion Bonding of SRV Pilot Interface.Replaced All Thirteen Ms SR Valve Pilot Cartridges |
- on 961101,MS SR Valves Exceeded TS Required Setpoint Limit as Result of Disc/Seat Bonding.Caused by Corrosion Bonding of SRV Pilot Interface.Replaced All Thirteen Ms SR Valve Pilot Cartridges
| 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)(B), Prohibited by Technical Specifications 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 10 CFR 50.73(a)(2)(viii) | | 05000260/LER-1996-008, :on 961101,Unit 2 Main Steam SRV Pilot Cartridges Failed Setpoint Tolerence Bench Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints.Srv Pilot Cartridges Replaced |
- on 961101,Unit 2 Main Steam SRV Pilot Cartridges Failed Setpoint Tolerence Bench Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints.Srv Pilot Cartridges Replaced
| 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)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000296/LER-1996-008-03, :on 961217,loss of ECCS Division II Instrumentation Caused ECCS Equipment to Be Inoperable. Replaced Cleared Fuse & Shorted SCR |
- on 961217,loss of ECCS Division II Instrumentation Caused ECCS Equipment to Be Inoperable. Replaced Cleared Fuse & Shorted SCR
| 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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 10 CFR 50.73(a)(2)(viii) | | 05000296/LER-1996-008, Forwards LER 96-008,providing Details Concerning Loss of Instrumentation Input Logic for Plants Division II ECCS Due to Cleared Fuse & Shorted Silicon Controlled Rectifier in Atu Inverter | Forwards LER 96-008,providing Details Concerning Loss of Instrumentation Input Logic for Plants Division II ECCS Due to Cleared Fuse & Shorted Silicon Controlled Rectifier in Atu Inverter | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
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