LER-1979-008, Forwards LER 79-008/03L-0 |
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| 2371979008R00 - NRC Website |
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Commonwealth Edison
> oresden Nuclear Power Station
. ii R.R. #1 i.. :... '.... '/ Morris, Illinois 60450
~*"*'-"""'--Ielephone_815/.9!12,2920. _______________________________ _
February 9, 1979 BBS LTR # ~9-135 James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
.Reportable Occurrence Report //79-8/031-0, Docket #050-237 is hereby submitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.2.(b),
conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown re-quired by a limiting condition for operation.
BBS:lcg Enclosure B.B. Stephenson Station Superintendent Dresden Nuclear Power Station cc:
Director of Inspection & Enforcement
. 7 9 0 2 2 2 0 0/ (
Director of Management Information & Program Control File/NRC
1.J nC1-""01'+ ::t2~
l7*nl""
LlCE.NSEE EVENT REPOP.T
.NUCLEAH REGULATOHY CUM.v11:;s10*~
SON TROL G LOC1':: r,_j _..____*..._l _..___! *__,_...._\\ __,! Q
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(PLEASE PRINT OR.TYPE ALL REQUIRED INFORMATION)
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9 LICE.\\JSSE CODE 14
- 5 LIC!ONSE NU~IUER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T
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GO 61 DOCKET NU\\IBER GS 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
I During steady state operation, the LPCI system minimum flow valve M0-2-1501-ll'.3.Ai failed to close completely while performing the *LPCI pump operability surveillance (DOS 1500-6).
The valve was closing when the breaker tripped.
The valve automati-I cally closes.when sufficient flow is sensed in the LPCI pump discharge header.
Safety significance was minimal since remaining 3 LPCI pumps were available to meet I
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I the required system flow.
No previous similar occurrences.
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9 SYSTE~.1 C,>.oJSE C,>.USE CODE CODE SUSCODE I S! Fl@ LU@ ~J@ 1z I 9
10 11 12 13 SEQL*ENTIAL
@ LER'RO LVENT YEP.A REPORT NO.
REPORT I 71 91 L::::J 10 I 01 81
- NUMBER 21 22 23 24 2G COMPONENT CODE ZI ZI ZI ZI z1@
18 OCCURRENCE CODE 1...---1 I 01 31 27 28 29 CO\\:?.
SUB CODE
~@
19 REPORT TYPE L.!'.J 30 VAL\\'E SU BC ODE w@
20 REVISION NO.
L=l lQJ 31 32 ACTION FUTURE EFFECT SHUTDOWN Q
- ATTACHMENT NPRD*4 PRIME CCMP.
SUPPLIER COMPONENT MANUFACTURER 80 TAKEN ACTION ON ?L,>.NT METHOD HOURS ~ SUBMITTED FQR.\\1 :;us.
W@UJ@
LzJ@
Lll.1 01 01 01 01 Ll!J@
LBJ@)
33 34 35 36 37 40 41 42 Ul@
I zl 91 91 91@)
CAUSE CE:SCRIPTION AND CORRECTIVE ACTICNS @
43
- 44 47 The cause of the failure is unknown.
The valve operator motor and the thermal ove:.:..J OJJJ I load contacts were checked with no anomalies found.
The breaker was reset and the valve was successfully cycled three times from the control room.
While cycling, electrical maintenance checked the amperage of the motor and found it satisfactcrry.
ITm No further corrective action is planned.
8 9
FACILITY STATUS
% POWER OTHER STATUS @
METHOD OF
~
80
~Li@
10 18 17 l@)l.__ __ N_A ______ ~
DISCOVERY DISCOVERY DESCRIPTION '231
~~~l~~~S_u_r_v_e_1_*_1_1_an~c_e_*~T_e_s_t_i_n_g ___
8 0
ACTIVITY 10 12 11 CON TENT
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44 P.ELSASED o;: REL::,>.SE AMOU~.JT OF ACTIVITY
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NA ___
7 ij 9
10 11 44 45 46 80 LOCATION OF RELEASE NA 45 80 80 80 NRC USE ONLY
DEVIATION REPORT *
DVR NO.
- ~commonwealth Edison.
STA UNIT YEAR NO; o* 2 12 PART 1/ Tl TLE OF DEVIATION OCCURRED
~1-T6=r9--o-152--c=
Flow Vlv Brkr Trip LPCI Min DATE TIME*
SYSTEM AFFECTED 1500
PLANT CONDITIONS
TES*Ti i-..!G LPCI Run 2208 725
!XJ CJ MODE PWR (MWT)
LOAD(MWE)
YES NO DESCRIPTION OF. EVENT While conducting LPCI pump'operability surveillance DOS 1500-6, the LPCI min flow vlv. breaker tripped when the vlv.. was attempting to close.
DESCRIPTION OF C.~USE Un kl). own OTHER APPLICABLE INFORMATION (2-1501-13A)
Breaker reset; vlv was exercised three times successfully DR NO.
T. A. Ciesla EQUl.PMENT [iJ YES FAILURE ONO NA WR NO.
719
.*. RESPQ_NSIBLE SUP!'RVISOR PART 2 I OPERATING ENGINEERS COMMENTS
_:Redundant< LP CL.pumps_ available to meet reduced system flow.
TYPE OF DEVIATION REPORTABLE OCCURRENCE.
EVENT OF POTENTIAL PUBLIC INTEREST TECH SPEC VIOLATION NON-REPORTABLE OCCURRENCE ANNUAL REPORT I NG
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1-26-79 DATE
.SAFETY-
. RELATED WR ISSUED
. YES iXl
':..* -...J
\\
9:55 AM
<.... TIME
'9: 55 AM
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| 05000237/LER-1979-001-03, /03L-0 on 790103:torus Level Increased to -1 Inch, Due to Repetitive Starts of HPCI Turbine.Increase in Torus Level Determined to Be Result of Inadequate Procedure.Hpci Surveillance Procedures to Be Amended | /03L-0 on 790103:torus Level Increased to -1 Inch, Due to Repetitive Starts of HPCI Turbine.Increase in Torus Level Determined to Be Result of Inadequate Procedure.Hpci Surveillance Procedures to Be Amended | | | 05000237/LER-1979-001, Forwards LER 79-001/03X-1 | Forwards LER 79-001/03X-1 | | | 05000010/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000010/LER-1979-001-03, /03L-0 on 790518:while Digging Ditch for New Pipe, Const Personnel Observed Water Running Into Trench from Proximity of Radwaste return-to-storage Line.Caused by Return Line to 1A Storage Leaking from Aluminum Line | /03L-0 on 790518:while Digging Ditch for New Pipe, Const Personnel Observed Water Running Into Trench from Proximity of Radwaste return-to-storage Line.Caused by Return Line to 1A Storage Leaking from Aluminum Line | | | 05000010/LER-1979-002-03, /03L-0 on 780825:during Monthly Surveillance DI5 5400-2,offgas Monitor 1 Tripped at Greater than 100%, Which Is Not within Setpoint Limit.Caused by Instrument Drift.Setpoint Recalibr | /03L-0 on 780825:during Monthly Surveillance DI5 5400-2,offgas Monitor 1 Tripped at Greater than 100%, Which Is Not within Setpoint Limit.Caused by Instrument Drift.Setpoint Recalibr | | | 05000010/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000237/LER-1979-002, Forwards LER 79-002/01X-1 | Forwards LER 79-002/01X-1 | | | 05000237/LER-1979-002-01, /01X-1 on 790103:during Normal Operation,Hpci Turbine Failed to Start During Quarterly Flow Test.Caused by Partial Engagement of Interlock Dump Valve Operating Lever. Lever Adjusted.Hpci Started to Verify Operability | /01X-1 on 790103:during Normal Operation,Hpci Turbine Failed to Start During Quarterly Flow Test.Caused by Partial Engagement of Interlock Dump Valve Operating Lever. Lever Adjusted.Hpci Started to Verify Operability | | | 05000237/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000237/LER-1979-003-03, /03L-0 on 790105:PS 2-1430-1466D Tripped at 105 Psi.Caused by Instrument Drift | /03L-0 on 790105:PS 2-1430-1466D Tripped at 105 Psi.Caused by Instrument Drift | | | 05000237/LER-1979-004-03, /03L-0 on 790111:LPCI Sys Full Flow Test Valve MO-2-1501-38B Failed While Securing D LPCI Pump.Caused by Broken Pinion Gear on Valve Operator Motor Shaft | /03L-0 on 790111:LPCI Sys Full Flow Test Valve MO-2-1501-38B Failed While Securing D LPCI Pump.Caused by Broken Pinion Gear on Valve Operator Motor Shaft | | | 05000237/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000237/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000237/LER-1979-005-03, /03L-0 on 790119: During Normal Operation, Mass Spectometer Leak Detector Downscale Condition Annunciated & High Rad Alarm & Half Scram Occurred Twice on Same Day. Log Rad Monitor Replaced | /03L-0 on 790119: During Normal Operation, Mass Spectometer Leak Detector Downscale Condition Annunciated & High Rad Alarm & Half Scram Occurred Twice on Same Day. Log Rad Monitor Replaced | | | 05000237/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000237/LER-1979-008-03, /03L-0 on 790126: LPCI Min Flow Value MO-2-1501-13A Failed to Close Completely During LPCI Pump Operability Surveillance.Cause of Failure Unknown | /03L-0 on 790126: LPCI Min Flow Value MO-2-1501-13A Failed to Close Completely During LPCI Pump Operability Surveillance.Cause of Failure Unknown | | | 05000237/LER-1979-009-03, /03L-0 on 790121:plant Chimney Sampling Sys Operating Incorrectly.Caused by Purge Valve V2 Being Stuck Open | /03L-0 on 790121:plant Chimney Sampling Sys Operating Incorrectly.Caused by Purge Valve V2 Being Stuck Open | | | 05000237/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000237/LER-1979-010-01, /01T-0 on 790202:section of Blowout Panel Blown Out,Breaching Secondary Containment.Cause Under Investigation | /01T-0 on 790202:section of Blowout Panel Blown Out,Breaching Secondary Containment.Cause Under Investigation | | | 05000237/LER-1979-010, Forwards LER 79-010/01T-0 | Forwards LER 79-010/01T-0 | | | 05000237/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000237/LER-1979-013-03, /03L-0 on 790223:after Diesel Generator Was Manually Started Prior to Taking Transformer Out of Svc, Water Pump Breaker Thermally Tripped & Redundant Power Supply Also Tripped.Cause Unknown | /03L-0 on 790223:after Diesel Generator Was Manually Started Prior to Taking Transformer Out of Svc, Water Pump Breaker Thermally Tripped & Redundant Power Supply Also Tripped.Cause Unknown | | | 05000237/LER-1979-014-03, /03L-0 on 790305:U2 Diesel Generator Failed to Start on First & Fifth Attempts.Caused by Bendix Gear Failure to Engage & Failure of Air Start Solenoid to Energize.Solenoid Was Replaced | /03L-0 on 790305:U2 Diesel Generator Failed to Start on First & Fifth Attempts.Caused by Bendix Gear Failure to Engage & Failure of Air Start Solenoid to Energize.Solenoid Was Replaced | | | 05000237/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000237/LER-1979-015, Forwards LER 79-015/01T-0 | Forwards LER 79-015/01T-0 | | | 05000237/LER-1979-016, Forwards LER 79-016/01T-0 | Forwards LER 79-016/01T-0 | | | 05000237/LER-1979-017-01, X2 for Dresden, Units 2 and 3 Re Inadequacies Observed in Implementation of Administrative Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection System or Engineered Saf | X2 for Dresden, Units 2 and 3 Re Inadequacies Observed in Implementation of Administrative Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection System or Engineered Safety Feature Sys | | | 05000237/LER-1979-017, Forwards LER 79-017/01T-0 | Forwards LER 79-017/01T-0 | | | 05000237/LER-1979-019, Forwards LER 79-019/03L-0 | Forwards LER 79-019/03L-0 | | | 05000237/LER-1979-020-03, /03L-0 on 790413:measured Leakage for Personnel Air Lock Was 54.63 Std Cubic Ft/H.Leakage Identified Through Outer Lower Handwell.Shaft Packing Was Replaced & Air Lock Retested | /03L-0 on 790413:measured Leakage for Personnel Air Lock Was 54.63 Std Cubic Ft/H.Leakage Identified Through Outer Lower Handwell.Shaft Packing Was Replaced & Air Lock Retested | | | 05000249/LER-1979-021-03, /03L-0:on 790821,during Normal Operation,Offgas Monitor 3A Took Step Increase W/No Power Change & hi-hi Trip Light Was On.Caused by Faulty V1 Electrometer Tube,Which Was Replaced.Monitors Will Be Tested Monthly | /03L-0:on 790821,during Normal Operation,Offgas Monitor 3A Took Step Increase W/No Power Change & hi-hi Trip Light Was On.Caused by Faulty V1 Electrometer Tube,Which Was Replaced.Monitors Will Be Tested Monthly | | | 05000237/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000237/LER-1979-022, Forwards LER 79-022/03L-0 | Forwards LER 79-022/03L-0 | | | 05000237/LER-1979-023-03, /03L-0 on 790406:during Radioactive Insp,Lack of Fusion Noted in Weld 4-4 on 4-inch Reactor Head Vent Line 2-0215-4.Weld Cut Out & Rewelded Per ASME Boiler & Pressure Vessel Code.Asme Hydrostatic Test Completed | /03L-0 on 790406:during Radioactive Insp,Lack of Fusion Noted in Weld 4-4 on 4-inch Reactor Head Vent Line 2-0215-4.Weld Cut Out & Rewelded Per ASME Boiler & Pressure Vessel Code.Asme Hydrostatic Test Completed | | | 05000249/LER-1979-023-03, /03L-0:on 790823,source Range Monitor Calibr Supplied Rod Block Trip at 1.03E5,exceeding Tech Specs Limit.Caused by Drift & Temp Dependency in Source Range Monitor.Defective Component Not Yet Identified | /03L-0:on 790823,source Range Monitor Calibr Supplied Rod Block Trip at 1.03E5,exceeding Tech Specs Limit.Caused by Drift & Temp Dependency in Source Range Monitor.Defective Component Not Yet Identified | | | 05000237/LER-1979-025, Forwards LER 79-025/03L-0 | Forwards LER 79-025/03L-0 | | | 05000237/LER-1979-026, Forwards LER 79-026/03L-0 | Forwards LER 79-026/03L-0 | | | 05000249/LER-1979-027, Forwards LER 79-027/03L-0 | Forwards LER 79-027/03L-0 | | | 05000237/LER-1979-027-03, /03L-0 on 790502:during Startup,Main Turbine Tripped on High Water Level.Caused by Packing Leak on Isolation Valve for PS-263-60B.Packing Adjusted,Tested & Sys Lineup Returned to Normal | /03L-0 on 790502:during Startup,Main Turbine Tripped on High Water Level.Caused by Packing Leak on Isolation Valve for PS-263-60B.Packing Adjusted,Tested & Sys Lineup Returned to Normal | | | 05000237/LER-1979-027, Forwards LER 79-027/03L-0 | Forwards LER 79-027/03L-0 | | | 05000249/LER-1979-027-03, /03L-0:on 791003,half of Trip Sys Inoperable Due to Lifting of Flooding Magnetrol Switch Leads to Condenser Pit.Switch Leads Reattached.No Precise Cause Found | /03L-0:on 791003,half of Trip Sys Inoperable Due to Lifting of Flooding Magnetrol Switch Leads to Condenser Pit.Switch Leads Reattached.No Precise Cause Found | | | 05000237/LER-1979-028, Forwards LER 79-028/03L-0 | Forwards LER 79-028/03L-0 | | | 05000237/LER-1979-028-03, /03L-0 on 790508:N2 Line Low Temp Alarm Received & Frost Found on Inerting line.A0-2-1601 & Inerting Line Failed Leak Rate Test.Caused by Failure of Temp Recorder at N2 Vaporizer | /03L-0 on 790508:N2 Line Low Temp Alarm Received & Frost Found on Inerting line.A0-2-1601 & Inerting Line Failed Leak Rate Test.Caused by Failure of Temp Recorder at N2 Vaporizer | | | 05000237/LER-1979-029-03, /03L-0 on 790508:DIS 1400-3,pressure Switch 2-1430-1466D Failed to Trip.Caused by Sticky Plunger in Pressure Switch.Switch Removed,Cleaned & Reset to Trip at 94.5 Psig Increasing | /03L-0 on 790508:DIS 1400-3,pressure Switch 2-1430-1466D Failed to Trip.Caused by Sticky Plunger in Pressure Switch.Switch Removed,Cleaned & Reset to Trip at 94.5 Psig Increasing | | | 05000237/LER-1979-029, Forwards LER 79-029/03L-0 | Forwards LER 79-029/03L-0 | | | 05000249/LER-1979-030-03, During Scram Testing in Refuel Mode,Substantial Loss of Position Indication Noted for Control Rod Driveline H-9.Caused by Improperly Seated Socket,Suggesting Faulty Electrical pin-socket Alignment | During Scram Testing in Refuel Mode,Substantial Loss of Position Indication Noted for Control Rod Driveline H-9.Caused by Improperly Seated Socket,Suggesting Faulty Electrical pin-socket Alignment | | | 05000249/LER-1979-030, /03X-1 for Dresden Unit 3 Regarding a Supplement to LER 79-30/03L-0 Addressing the Cause and Corrective Actions for the Loss of Position Indication for CRD H-9 | /03X-1 for Dresden Unit 3 Regarding a Supplement to LER 79-30/03L-0 Addressing the Cause and Corrective Actions for the Loss of Position Indication for CRD H-9 | | | 05000237/LER-1979-031-03, /03L-0 on 790509:crack Found on 2D1 Feedwater Emergency Spill to Condenser Line & Crack Located on Pipe to Condenser Weld.Caused by Mechanical Failure.Cracked Portion Removed & Rewelded | /03L-0 on 790509:crack Found on 2D1 Feedwater Emergency Spill to Condenser Line & Crack Located on Pipe to Condenser Weld.Caused by Mechanical Failure.Cracked Portion Removed & Rewelded | | | 05000237/LER-1979-031, Forwards LER 79-031/03L-0 | Forwards LER 79-031/03L-0 | | | 05000237/LER-1979-032, Forwards LER 79-032/03L-0 | Forwards LER 79-032/03L-0 | |
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