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 Utils |
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text
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(ACCELERATED RIDS PROCESSIi~
REGULATORY INFORMATION DISTRIBUTION.SYSTEM (RIDS)
ACCESSION NBR: 9503140132 DOC'. DATE: 95/03'/09:
NOTARIZED: NO FACIL:50-260 Browns Ferry Nuclear.Power Station, Unit 2, Tennessee AUTH.NAME AUTHOR AFFILIATION MACHON,R.D.
'Tennessee Valley Authority RECIP.'NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
- SUBJECT:
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.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR J ENCL J SIZE:
TITLE: 50.73/50.9 Licensee, Event Report (LER),, Incident Rpt, etc.
NOTES:
DOCKET N
05000260 RECIPIENT ID CODE/NAME PD2-4-PD COPIES
,RECIPIENT LTTR ENCL ID CODE/NAME 1
1 WILLIAMS,J.
COPIES LTTR ENCL 1
1 INTERNAL: ACRS AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DOPS/OECB NRR/DRCH/HICB NRR/DRSS/PRPB NRR/DSSA/SRXB'GN2 FILE 01 EXTERNAL: L ST LOBBY WARD NOAC MURPHY,G'.A NRC PDR 1
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NRR/DSSA/SPLB RES/DSIR/EIB LITCO BRYCE,J H
NOAC POORE,W.
NUDOCS FULL TXT' 1
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EMOTE TOALL"RIDS" RECIPIENTS:
PLEASE'HELP US TO REDUCE O'ASTE!'CONTACT'IHE DOCLi!EiTCOi"IROL DESK, ROOM PI -37 (EX"E 304-2083
) TO EL I X!IRATE YOUR iAifE F ROTI DISTR I8 U I IOi.LISTS I:OR,DOC(.'iIL'i'I'S 'YOI.'!Mi "I i'I:I'.D!
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER 'OF COPIES REQUIRED:
LTTR 27'NCL 27
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Terressee va ey A '.ew:y. >cs: ~"ce acx 2ÃC. "ew: r. Aa~a a"cc9.2XC R. D, {Rick)Machon Vce >'esther:. B.c:."sre.g N".cea ~a":
March 9, 1995 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555
Dear Sir:
BROWNS-FERRY NUCLEAR PLANT'BFN) - UNITS 1g 2q AND 3 - DOCKET NOS ~ 50-259~ 50-260'ND 296 FACILITY OPERATING LICENSE DPR-33'2'ND 68 - VOLUNTARY LICENSEE EVENT REPORT (LER) 50-260/94011 The enclosed voluntary report provides details concerning the failure of a magnesium alloy rotor motor on a Reactor Water Recirculation System (RWRS) pump discharge isolation valve that placed Unit 2 in a Limiting Condition for Operation.
On October 1,
- 1994, TVA commenced shutdown for the Unit 2 Cycle 7 outage.
Preparations were under way to align the Residual Heat Removal (RHR) system into the shutdown cooling mode.
An attempt to close RWRS Pump B discharge isolation valve from the main control room failed.
TVA's initial investigation identified a phase to ground short in the motor circuit.
The valve was subsequently manually closed.
This, condition is not reportable in accordance with 10 CFR 50.73.
The RWRS discharge isolation valve operators for both loops of RWRS are driven by magnesium alloy rotor motors.
These valves were in a high humidity environment for some portion of Unit 2 Cycle 7 operation.
TVA's failure analysis identified corrosion products on the rotors for both valve operator motors..
Previous industry guidance has been issued regarding the use of motors with magnesium rotors (e.g.,
Information Notice 86-02, "Failure of Valve Operator Motor During Environmental Qualification Testing" ).
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f% A 9503140132 950309 PDR ADOCK 05000260 S
PDR
Ik II
U,. S. Nuclear Regulatory Commission Page 2
March 9,, 1995 Because of the potential generic applicability'f the issues surrounding the event to other utilities, TVA is submitting this voluntary, report.
Sincerely, R.
D.
chon
.Site V'face President PAB 1E-BPN Enclosure
0 0
1
U.'S. Nuclear Regulatory Commission Page 3
March 9, 1995 cc- (Enclosure),:
INPO Records Center Suite 1500 1100 Circle 75 Parkway
.Atlanta,, Georgia 30339 Paul Krippner American Nuclear Xnsurers Town Center, Suite 300S 29 South Main Street
.West Hartford, Connecticut 06107 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 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 Rockville, Maryland
.20852 E. V. Imbro, NRR/RS B
U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 E. J.
- Leeds, NRR/DRPW U.S. Nuclear, Regulatory Commission On'e White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
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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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