LER-1994-010, Forwards LER 94-010-01,clarifying Analysis of Event Section Which Division I & Division II ECCS Equipment Remained Operable for Automatic Initiation |
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| Reporting criterion: |
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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| 2601994010R01 - NRC Website |
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text
CATEGORY REGULA RY INFORMATION DISTRIBUTIO SYSTEM'RIDS)
ACCESSION'-NBR:9610090099 DOC.DATE: 96/09/30 NOTARIZED:
NO FACIL:50-260 Browns Ferry, Nuclear Power Station, Unit 2, Tennessee AUTH.NAME AUTHOR AFFILIATION MACHONgR.D.
Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards LER 94-010-01.Clarify in analysis of event section which Division I 6 'Division II ECCS equipment remained operable for automatic initiation.
'DZSTRZBUTZON CODE:
ZE22T COPZES RECEZVED:LTR L ENCL /
SZZE:
TITLE: 50.73/50..9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
DOCKET 05000260 A
RECIPIENT ID CODE/NAME PD2-3-PD INTERNAL: ACRS R
JOE/EE NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB'RR/DSSA/SRXB RGN2 FILE 01 COPIES LTTR ENCL 1
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'WILLIAMS,J.
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0 EXTERNAL: L ST LOBBY WARD NOAC MURPHY,G.A NRC PDR 1
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NOAC POORE,W.
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N NOTE TO ALL "RIDS." RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU'OR'YOUR ORGANIZATION, CONTACT THE'DOCUMENT CONTROL DESK (DCD)
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Tennessee tj'atey Authonty, Post Offce Box 2000. Deca'ur. Ataoarna 35609 20CO September 30, 1996 R. D,(Rick) Machon Vice Presioent. Browns Feny Nuctear Pant U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
10 CFR 50.73 BROWNS PERRY NUCLEAR PLANT (BFN) - UNITS 1~
2q AND 3 - DOCKET NOS 50-259'0-260'ND 296 - FACZLTTY OPERATING LZCENSE DPR-33~
52~
AND 68 - LZCENSEE EVENT REPORT 50-260/94010'EVZSION 1
This revision to LER 50-260/94010 i.s to clarify in the Analysis of the Event section which Divison I and Division II ECCS equipment remained operable for automatic initiation, and which Division II ECCS equipment would be required to be manually initiated.
The initial report also provided details concerning a loss of instrumentation input logic for the plant's Division II Emergency Core Cooling Systems (ECCS).
The event was caused by a blown fuse to the ECCS Division II, Analog Trip Unit (AT rter.
The blown fuse resulted from a failed capacz or xn the ATU Inverter capacitor bank.
Section VII of the report provided a description of TVA's commitment regarding this event.
Finally, the initial report was submitted pursuant to 10 CFR 50.73(a)(2)(vii),
and 50.73(a)(2) (i)(B).
Sincerely, R.
D.
on Enclosure cc:
See page 2
96l0090099 960930 PDR ADOCK OS000260 PDR 1 L>0
U.S. Nuclear Regulatory'ommission Page 2
September 30, 1996 Enclosure cc (Enclosure):
INPO, Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339 Paul Krippner American Nuclear Insurers Town Center, Suite 300S 29 South Main Street West Hartford, Connecticut 06107 NRC Resident Inspector Browns Ferry Nuclear Plant 10833
.Shaw Road
- Athens, Alabama 35611 Regional Administrator U.S.,Nuclear Regulatory Commission
'Region II 101 Marietta Street, NW, Suite '2900 Atlanta,,Georgia 30323 Mr,. J., F. Williams, Project Manager U..S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike
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| 05000260/LER-1994-001-02, :on 940214,loss of Unit 2,Division II ECCS Instrumentation Due to Blown Fuse.Caused by Failure of Atu Inverter Control Card.Blown Fuse & Control Card in ECCS Division II Atu Inverter Replaced |
- on 940214,loss of Unit 2,Division II ECCS Instrumentation Due to Blown Fuse.Caused by Failure of Atu Inverter Control Card.Blown Fuse & Control Card in ECCS Division II Atu Inverter 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)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(1)
10 CFR 50.73(a)(1)(B) | | 05000259/LER-1994-001-01, :on 940304,EECW Pump A3 Inadvertently Auto Started During Performance of SI O-SI-4.2.B.-67.Caused by Personnel Error.Electrical Maint Procedures Will Be Revised. Walkdown of 4 Kv Shutdown Will Be Performed |
- on 940304,EECW Pump A3 Inadvertently Auto Started During Performance of SI O-SI-4.2.B.-67.Caused by Personnel Error.Electrical Maint Procedures Will Be Revised. Walkdown of 4 Kv Shutdown Will Be 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)(i)
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)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000296/LER-1994-001-04, :on 941018,unexpected auto-start of Unit 3 DGs Occurred During Performance of SI Due to Personnel Error. Electrical Maint Personnel Briefed on Event |
- on 941018,unexpected auto-start of Unit 3 DGs Occurred During Performance of SI Due to Personnel Error. Electrical Maint Personnel Briefed on Event
| 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)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000259/LER-1994-002-03, :on 940428,GE Akr Circuit Breakers Failed Trip Time Tests Due to Different Testing Equipment Used by TVA & GE for Breaker Testing.Akr Breakers Returned to GE for Addl Rework & Retest |
- on 940428,GE Akr Circuit Breakers Failed Trip Time Tests Due to Different Testing Equipment Used by TVA & GE for Breaker Testing.Akr Breakers Returned to GE for Addl Rework & Retest
| 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)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(1) | | 05000260/LER-1994-002-02, :on 940412,noncompliance w/10CFR50,App R Resulted in Plant Being Outside Design Basis.Caused by Personnel Error.C/As:Engineering Dept Personnel Will Review Circumstances That Led to Events |
- on 940412,noncompliance w/10CFR50,App R Resulted in Plant Being Outside Design Basis.Caused by Personnel Error.C/As:Engineering Dept Personnel Will Review Circumstances That Led to Events
| 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)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000296/LER-1994-002-04, :on 941031,discovered Deficiency Re Raychem Tubing Used for Environ Qualification Applications.Condition Occurred When Tubing Could Not Be Shrunk Enough to Provide Proper Seal Per Vendor Specs |
- on 941031,discovered Deficiency Re Raychem Tubing Used for Environ Qualification Applications.Condition Occurred When Tubing Could Not Be Shrunk Enough to Provide Proper Seal Per Vendor Specs
| 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)(B) | | 05000260/LER-1994-003-02, :on 940104,standby Gas Treatment Trains Declared Inoperable as Result of Inoperable Edgs.Caused by Fuel Oil Leak.Tripping Time Relay Replaced & Testing Ongoing |
- on 940104,standby Gas Treatment Trains Declared Inoperable as Result of Inoperable Edgs.Caused by Fuel Oil Leak.Tripping Time Relay Replaced & Testing Ongoing
| 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)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000259/LER-1994-003-03, :on 940713,defect Discovered in Pressure Rating for Air Conditioning Units (Acu) Supplied by Ellis & Watts. on 940823,determination Made That Event Reportable Per 10CFR21.All Acus Will Be Reworked |
- on 940713,defect Discovered in Pressure Rating for Air Conditioning Units (Acu) Supplied by Ellis & Watts. on 940823,determination Made That Event Reportable Per 10CFR21.All Acus Will Be Reworked
| 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)(x)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(1)
10 CFR 21.21(c)(3)(ii)
10 CFR 21.21(c)(3)(i) | | 05000260/LER-1994-004-02, :on 940415,Unit 2 Received a Full Scram from Full Power Due to RPS Trip Signal Generated by Low Scram Pilot Air Header Pressure Signal.Failed Module in Temp Detection Loop |
- on 940415,Unit 2 Received a Full Scram from Full Power Due to RPS Trip Signal Generated by Low Scram Pilot Air Header Pressure Signal.Failed Module in Temp Detection Loop
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
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)
10 CFR 50.73(s)(2)(viii)(B)
10 CFR 50.73(s)(2)(viii)(A) | | 05000260/LER-1994-005-01, :on 940418,unit 2 Reactor Automatically Scrammed from 15 Percent When MSIVs Unexpectedly Closed. Caused by Low Main Steam Pressure.Corrective Action:Ehc Setpoint Potentiometer Was Replaced |
- on 940418,unit 2 Reactor Automatically Scrammed from 15 Percent When MSIVs Unexpectedly Closed. Caused by Low Main Steam Pressure.Corrective Action:Ehc Setpoint Potentiometer Was Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000260/LER-1994-006-03, :on 940831,received Alarms That Indicated Loss of Unit 2 ECCS Instrumentation.Caused by Random Failure of ECCS Division I,Atu Inverter.Atu Inverter Was Replaced by Replacing Shorted SCR |
- on 940831,received Alarms That Indicated Loss of Unit 2 ECCS Instrumentation.Caused by Random Failure of ECCS Division I,Atu Inverter.Atu Inverter Was Replaced by Replacing Shorted SCR
| 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)(A) | | 05000260/LER-1994-007, :on 940929,discovered That Condition Involving Noncompliance w/10CFR50 App R,Criterion III.L.2.d Existed. Caused by Failures to Correctly Interpret/Implement Requirements of Calculations.Rept Initiated |
- on 940929,discovered That Condition Involving Noncompliance w/10CFR50 App R,Criterion III.L.2.d Existed. Caused by Failures to Correctly Interpret/Implement Requirements of Calculations.Rept Initiated
| 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)(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)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000260/LER-1994-008-01, :on 941002,primary Containment Penetrations & Main Steam Isolation Valves Leak Rates Exceeding TS Limits Occurred.Cause of Leakage Initially Investigated.Valves Will Be Repaired |
- on 941002,primary Containment Penetrations & Main Steam Isolation Valves Leak Rates Exceeding TS Limits Occurred.Cause of Leakage Initially Investigated.Valves Will Be Repaired
| 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(s)(2)(v)
10 CFR 50.73(s)(2)(vii)
10 CFR 50.73(s)(2)(viii)(B) | | 05000260/LER-1994-008, :on 941002,containment Penetration & MSIV Leak Rates Exceeded TS Limits.Caused by Abnormal Rib Guide Wear. MSIVs Repaired & Retested.Maint Instructions Will Be Written for Valves to Address Proper Shimming Requirements |
- on 941002,containment Penetration & MSIV Leak Rates Exceeded TS Limits.Caused by Abnormal Rib Guide Wear. MSIVs Repaired & Retested.Maint Instructions Will Be Written for Valves to Address Proper Shimming Requirements
| 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000260/LER-1994-009-01, :on 940420,missed TS Surveillance Before Reactor Startup as Result of Misunderstanding of Ts.Util Will Submit TS Change to Clarify Frequency for IRM & APRM Instrumentation Funtional Tests |
- on 940420,missed TS Surveillance Before Reactor Startup as Result of Misunderstanding of Ts.Util Will Submit TS Change to Clarify Frequency for IRM & APRM Instrumentation Funtional Tests
| 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A) | | 05000260/LER-1994-010-01, Forwards LER 94-010-01,clarifying Analysis of Event Section Which Division I & Division II ECCS Equipment Remained Operable for Automatic Initiation | Forwards LER 94-010-01,clarifying Analysis of Event Section Which Division I & Division II ECCS Equipment Remained Operable for Automatic Initiation | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000260/LER-1994-010, :on 941005,loss of ECCS Division II Instrumentation Resulting from Blown Fuse in Atu Inverter. Caused by a Failed Capacitor.Blown DC Input Fuse Was Replaced |
- on 941005,loss of ECCS Division II Instrumentation Resulting from Blown Fuse in Atu Inverter. Caused by a Failed Capacitor.Blown DC Input Fuse Was Replaced
| 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)(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)
10 CFR 50.73(e)(2)(v) | | 05000260/LER-1994-011-01, :on 941001,magnesium Alloy Rotor Motor on Reactor Water Recirculation Sys Pump Discharge Isolation Valve Failed,Placing Facility in Lco.New Operator Motor Installed & Associated Breaker Replaced |
- on 941001,magnesium Alloy Rotor Motor on Reactor Water Recirculation Sys Pump Discharge Isolation Valve Failed,Placing Facility in Lco.New Operator Motor Installed & Associated Breaker Replaced
| | | 05000260/LER-1994-011, Forwards Voluntary LER 94-011 Re Failure of Magnesium Alloy Rotor Motor on Reactor Water Recirculation Sys Pump Discharge Valve.Rept Submitted Because of Potential Generic Applicability of Issues Surrounding Event to Other Util | Forwards Voluntary LER 94-011 Re Failure of Magnesium Alloy Rotor Motor on Reactor Water Recirculation Sys Pump Discharge Valve.Rept Submitted Because of Potential Generic Applicability of Issues Surrounding Event to Other Utils | | | 05000260/LER-1994-012-01, :on 941113,RHR Shutdown Cooling Valve Inadvertently Closed.Caused by Personnel Failure to Follow Procedure During Surveillance Instruction.Personnel Involved in Event Counseled |
- on 941113,RHR Shutdown Cooling Valve Inadvertently Closed.Caused by Personnel Failure to Follow Procedure During Surveillance Instruction.Personnel Involved in Event Counseled
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
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)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000260/LER-1994-013, :on 941202,Unit 2 Received Full Automatic Scram from 54% Reactor Power.Caused by Mechanical Degradation of Stator Cooling Water Temp Switch.Affected Systems Restored to Operable Status & Temp Switch Replaced Before Restart |
- on 941202,Unit 2 Received Full Automatic Scram from 54% Reactor Power.Caused by Mechanical Degradation of Stator Cooling Water Temp Switch.Affected Systems Restored to Operable Status & Temp Switch Replaced Before Restart
| 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)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000260/LER-1994-013-01, :on 941202,Unit 2 Scrammed from 54% Power Due to Balance of Plant Equipment Failure.Caused by Mechanical Degradation of Stator Cooling Water Temp Switch. Affected Sys Restored to Operable Status |
- on 941202,Unit 2 Scrammed from 54% Power Due to Balance of Plant Equipment Failure.Caused by Mechanical Degradation of Stator Cooling Water Temp Switch. Affected Sys Restored to Operable Status
| 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)
10 CFR 50.73(a)(2)(viii)(A) |
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