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LER-1979-043, /03L-0:on 790201,axial Power Distribution Monitoring Sys Detector Alarm Setpoint Was Set Nonconservatively.Setpoint Reset.Personnel Received Addl Training |
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| 3151979043R03 - NRC Website |
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REGULATORWNFORMATION DISTRIBUTION TEM (RIDS) l ACGESS I ON NBR i 7909190472 DOC ~ DATE; 79/09/13 NOTARIZEDt NO FACIL:50 315 Donald C ~
Cook Nuclear Power Pl anti Uni t 1i Indiana 8
AUTH BYNAME AUTHOR Al FILIATION RISCHLINGiJ,L, Indiana 8 Michigan Power Co, RECIP,NAME RECIPIENT AFFILIATION Region 3i Chicagoi Office of the Director
SUBJECT:
LER 79 003/03L 0:on 790201iaxial power distribution mointoring sys detector alarm setpoint was set nonconservatively<Setpoint reset, Personnel received addi training<
DISTRIBUTION CODE:
A002S COPIES RECEIVED!LTR
'NCl 'IZE:
TITLE: Incident Repor ts DOCKET 05000315 ES PQ ~+ ~eeeoee~eeeeee~ee+e w~~w~ee~~~~sweeereee+~+~e
~+<we eeeweeeree~weew epee~e eey~~~tp~~e year ee~w~o e RECIPIENT ID CODEiNAME ACTION:
05 BC INTERNAL: 01 REG F ILE 09 ISE 14 TA/EDO 16 EEB 18 PLANT SYS BR 20 AD PLANT SYS 23 ENGR BR 25 PHR SYS BR 27 OPERA LIC BR 29 AUX SYS BR HANAUERiSi TMI~H STREFT EXTERNAL: 03 LPDR 29 ACRS COPIES CTTR ENCI 1
1 2
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1 1
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16 RECIPIENT ID CODE/NAME 0?
NRC PDR 11 MPA 15 NOVAK/KNIEL 17 AD FOR ENG~
19 I8C SYS BR" 22 REAC SAFT UR 24 KREGER 26 AD/SITE ANAL 28 ACOENT ANLYS E-JORDAN/IE STS GROUP LEADR I
00 NSIC COPIES LTTR ENCL 1
1 3
1 i
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1 1
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1 1
TOTAL NUMBER OF COPIES REQUIRED o LTTR 08 ENCL 48
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DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 September 13, 1979 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Comm'ion Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-58 Docket No. 50-315
Dear Mr. Keppler:
Pursuant to the reciuirements of the Appendix A Technical Specifications the following report/s are submitted:
RO 79-042/03L-0 RO 79-043/03L-O.
Sincerely, F~<D.V. Shaller Plant Manager
/bab cc:
J.ED Dolan R.W. Jurgensen R.F. Kroeger R. Kilburn R.J. Vollen BPI R.E.
Masse RO:III R.C. Callen MPSC P.W. Steketee, Esq.
R. Walsh, Esq.
G. Charnoff, Esq.
J.M. Hennigan G. Olson PNSRC J.F. Stietzel E.L. Townley Dir., IE (30 copies)
Dir., MIPC (3 copies)
U. S. NUCLEAR REGULATORY COMMISSION NRC FORM 366 f7g771 [OD1]
7 8
CON'T
~01 7
8
'lCENSEE EVENT REPORT
> CONTROL BLOCK:
QI
{PLEASE PRINT OR TYPE ALI.REQUIRED INFORMATION) 1 6
M I D
C C
1 Qo0 0
0 0
0 0
0 0
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OQo4 1
1 1 IQs~Qs 9
LICENSEE CODE 14, 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 REPoRT ~LQ P
5 P
0 P
3 1
5 Q 0
8 1
4 7
9 Qs 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 ON AUGUST 14, WHX'LE XSOLATING A PRESSURIZER LEVEL TRANSMITTER Q
80 3 j (NLP-1 5 2 )
THE ASSOC lATED P RES SURI ZER PRESSURE TRANSMITTER (NPP-1 5 2 )
4 WAS ISOLATED ~
WHEN NPP 1 52 WAS VALVED BACK IN z INDICATION DIFFERED FROM THE OTHER PRESSURIZER PRESSURE CHANNELS.
NPP-152 OUTPUT WAS ADJUSTED FOR PROPER OUTPUT ~
ON AUGUST 2 2 i IT WAS DISCOVERED THAT THERE WAS A 30 PSI DIFFERENCE BETWEEN THE PRESSURIZER PRESSURE o
s INDICATION AND A HEISE GAUGE
(
SEE SUPPLEMENT) 7 8
9 80
~O9 7,
8 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~Is QI,
~RQIo
~CQ>>
I N
0 T
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9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LF RgRO EVENT YEAR REPORT NO.
CODE TYPE NO.
QI RssosI ~
+
~<>
4 21 22 23 24 26 27 28 29 30, 31 32 ACTION FUTURE
- EFFECT, SHUTDOWN ATTACHMENT NPRDR PRIME COMP.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FORM SUB.
SUPPLIER MANUFACTURER PJQ16 ~Q19
~Q20
~Q2
~ Q23 gJQ24 ~ Q26 Q26 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o
THESE PRESSURIZER PRESSURE TRANSMITTERS WERE INSTALLED DURING THE LAST REFUELING OUTAGE BECAUSE THEY ARE ENVIRONMENTALLYQUALIFIED FOR USE UNDER POST ACCIDENT CONDITIONS."
AS OF THIS TIME, XT IS THE INVESTXGATION IS STILL OPEN (SEE SUPPLEMENT) 80 7
8 9
FACILITY STATUS Ts POWER OTHER STATUS Q 1
0 0
NA METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q2
~CQ31 TECHNICIAN OBSERVATION 44 45 46
~s
~Q>> ~Q>>
7 8
9 10 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ 6
~Z Q33
~ZQ34 NA 7
s 8
9 10 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39
~oo 0
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NZ 7
8 9
11 12 13 PERSONNEL INJURIES NU BER DESCRIPTION~41 s
~O~
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8 9
11 12 LOSS OF OR DAMAGETO FACILITYQ43 TYPE
DESCRIPTION
Z Q42 NA 8
9 10 P U8 L IC ITY 7
8 9
10 80 LOCATIONOF RELEASE Q 45 80 44 80 80 80 NRC USC ONLY 80 ss 00 s
68 69616-465-5901 J. L. Rischling PHONE:
NAME OF PREPARER
~3 NOT KNOWN WHAT CAUSEDALL OF THESE TRANSMITTERSTO DRIFT ~
HOWEVERS
SUPPLEMENT TO LER 5 79-042/03L-0 SUPPLEMENT TO EVENT DESCRIPTION INSTALLED FOR TEST PURPOSES.
ALL PRESSURXZER PRESSURE TRANSMITTERS WERE RE-CALXBRATED ON AUGUST 22, AND FOUND TO BE READING FROM 2.5 TO 4
PERCENT LOW.
THESE EVENTS WERE NON-CONSERVATIVE IN RESPECT TO T.S.
TABLE 2.3-1 XTEM 10 AND, TABLE 3.3-1 ITEM 10.
SUPPLEMENT TO CAUSE DESCRIPTION AND THE PRESSURIZER PRESSURE INDXCATION XS 'BEING PERXODICALLY CHECKED TO INSURE THESE TRANSMITTERS (BARTON-MODEL NO.
763)
HAVE NOT DRIFTED AGAIN.
IF A DEFXNITE CAUSE IS DETERMINED A SUPPLEMENTAL LER WILL BE SUBMITTED.
UNIT-2 IS NOT AFFECTED BY. THIS EVENT AS THE BARTON TRANSMXTTERS ARE NOT YET XNSTALLED.
U. S. NUCLEAR REGULATORY COMMISSION NRC FOQM 366 [7-77)
ICfNSfffVfNTRfPQRT TE'
+CONTROL BLOCK:
Q1 tPLEASE PRINT OR TYPE ALI.REQUIRED INFORMATION)
I 6
M I 0
C C
1 QE 0
0 0
0 0
0 0
0 0
0 0
Q24 1
1 1
1 Q4~QE 7
8 9
LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T
~ol
~LQE 0
5 0
0 0
3 1
5 QT 0
2 0
1 7
9 QE 0
9 1
9 7
9 Q9 7
8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10
~02 ON FEBRUARY 1 i XT WAS DISCOVERED THAT AFTER SWITCHING APDMS DETECTORS ON JANUARY 22 g THE APDMS DETECTOR F ALARM SETPOINT WAS SET AT THE T ~ S ~
VALUE~
UPON DISCOVERY 'HE,'ALWL% SETPOINT VALUE WAS RESET TO THE 6
PROPER VALUE~
THIS IS NON-CONSERVATIVE IN RESPECT TO A P REVIOUS 6
COMMXTMENT STATED XN RO 3 1 6/7 8 6 8 AND RO 3 15/7 8 5 8 THIS EVENT l
IS NON CONSERVATIVE IN RESPECT TO T ~ S 3
3 3
6 l3 ~
~OB 7
8 9
80
~09 7
8 SWITCHED AND THE T.S.
VALUE WAS USED FOR THE POWER LEVEL F ALARM SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~IB Qll A
QTE
~X QTE I
N S
T R
U QT4
~S QEE
~Z QTE 9
10 11 12 13 18 19 20
'I SEQUENTIAL OCCURRENCE REPORT REVISION LERlRO EVENT YEAR REPORT NO.
CODE TYPE Ql REPoRT ~
+
~04 3
Q~
~03
+L QD 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATIACHMENT NPRDQ PRIME COMP.
COMPONENT'~QTE
~ Q19 PJ QEO ~ QET
~ Q22 PJQ24 ~ QEE Q29 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27
~1 0
THIS CONDITION EXISTED FROM JANUARY 22, WHEN AN APDMS DETECTOR WAS SETPOINT.
THE TRACES DURING THIS OCCURRENCE HAVE BEEN REVIEWED AND THERE WAS SUFFICIENT. MARGIN SO THAT THERE WOULD HAVE BEEN NO.F 7
8 9
FACILITY STATUS
% POWER 1
0 0
OTHER STATUS Q30 NA METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32
~B Q31 DATA REVIEW 44 45 46 9
E Q29 ~Q29 8
9 10 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT@ACTIVITY Q36 EKI L'JQ33 '3 7
8 9
11 PERSONNEL EXPOSURES 7
8 9
11 12 13 PERSONNEL INJURIES
~OII Q49 NA LOCATION OF RELEASE Q NA 45 44 7
8 9
9 11 12 LOSS OF OR DAMAGETO FACILITY~43 T'gE
DESCRIPTION
VXOLATXONS.
TO PREVENT THXS FROM RECURRING SEE SUPPLEMENT 80 80 80 80 80 7
8 era 7
8 9
10 PUBLICITY ISSUED DESCRIPTION i
~Q44 9
10 NAME OF PREPARER J. L. Rischling NRC USE ONLY 68 69 616-465-5901 PHONE:
80 44O 9
80 g 0
0.
99
I
SUPPLEMENT TO LER 8 79-043 03L-0 SUPPLEMENT TO CAUSE DESCRIPTION THE NUCLEAR SECTION PERSONNEL RECEIVED ADDITIONALTRAINING, AND THE ALARM SETPOINT VALUES ARE NOW POSTED AT THE APDMS.
THIS EVENT WAS DETERMINED TO BE REPORTABLE ON AUGUST 14, DUE TO A SIMILAR EVENT OCCURRING ON UNIT-2 IN JULY (RO-316/79- 029.
)
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| 05000315/LER-1979-001-03, /03L-0 on 790122:during Mode 1,position of Rod F-6 Showed Deviation of Greater than 12 Steps from Demand Position.Caused by Drift in Signal Conditioning Module | /03L-0 on 790122:during Mode 1,position of Rod F-6 Showed Deviation of Greater than 12 Steps from Demand Position.Caused by Drift in Signal Conditioning Module | | | 05000316/LER-1979-001-03, /03L-0 on 790111:at 100% Power,Quadrant Power Tilt Ratio Alarm Per Tech Spec 4.2.4 Was in Error.Calculation of Tilt Ratio Is Required Every 12-h;first Survey Was Missed Because Alarm Instruments Were Being Calibr | /03L-0 on 790111:at 100% Power,Quadrant Power Tilt Ratio Alarm Per Tech Spec 4.2.4 Was in Error.Calculation of Tilt Ratio Is Required Every 12-h;first Survey Was Missed Because Alarm Instruments Were Being Calibr | | | 05000316/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000315/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000315/LER-1979-002-03, /03X-1:on 790127,injection of Boric Acid Caused Increase of Neutron Flux in Reactor Core.Axial Flux Difference Exceed Limits & Alarm Did Not Function Properly. Caused by Hardware Failure | /03X-1:on 790127,injection of Boric Acid Caused Increase of Neutron Flux in Reactor Core.Axial Flux Difference Exceed Limits & Alarm Did Not Function Properly. Caused by Hardware Failure | | | 05000316/LER-1979-002-03, /03L-0 on 790106:during Startup,Auxiliary Feedwater Motor Operated Valve Would Not Close Due to Broken Wire in SMB-0-25 Operator.Caused by Vibration & Use of Solid Conductor | /03L-0 on 790106:during Startup,Auxiliary Feedwater Motor Operated Valve Would Not Close Due to Broken Wire in SMB-0-25 Operator.Caused by Vibration & Use of Solid Conductor | | | 05000315/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000316/LER-1979-003-03, /03L-0 on 790106:reactor Trip/Safety Injection Occurred.Caused by Freezing of Steam Generator/Main Steam Pressure Sensing Lines.Freezing Due to Failure to Close Off Steam Vent Openings in West Steam Encl | /03L-0 on 790106:reactor Trip/Safety Injection Occurred.Caused by Freezing of Steam Generator/Main Steam Pressure Sensing Lines.Freezing Due to Failure to Close Off Steam Vent Openings in West Steam Encl | | | 05000315/LER-1979-003-03, /03L-0 on 790120:during Review of Completed Surveillance Tests,Discovered That Test on Solid State Protection Sys Train a Exceed 1-h Limit Imposed by Tech Specs.Caused by Technician Overlooking 1-h Limit | /03L-0 on 790120:during Review of Completed Surveillance Tests,Discovered That Test on Solid State Protection Sys Train a Exceed 1-h Limit Imposed by Tech Specs.Caused by Technician Overlooking 1-h Limit | | | 05000316/LER-1979-004-01, /01T-0 on 780802:turbine Low Fluid Oil Pressure Switches Set at non-conservative Value.Initially Calibr at Vendors Recommended Setpoints;Were Not Recalibr Per Tech Specs | /01T-0 on 780802:turbine Low Fluid Oil Pressure Switches Set at non-conservative Value.Initially Calibr at Vendors Recommended Setpoints;Were Not Recalibr Per Tech Specs | | | 05000316/LER-1979-004, Forwards LER 79-004/01T-0,79-005/03L-0 & 79-006/03L-0 | Forwards LER 79-004/01T-0,79-005/03L-0 & 79-006/03L-0 | | | 05000315/LER-1979-004-03, /03L-0 on 790206:both Doors of Containment Airlock Were Inadvertently Opened.Caused by Interlock Cable Being Too Loose to Operate Locking Mechanism.Tension Was Adjusted & Interlock Then Tested Satisfactorily | /03L-0 on 790206:both Doors of Containment Airlock Were Inadvertently Opened.Caused by Interlock Cable Being Too Loose to Operate Locking Mechanism.Tension Was Adjusted & Interlock Then Tested Satisfactorily | | | 05000315/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000315/LER-1979-005-03, /03L-0 on 780624:unit Was Operated W/Positive Moderator Temp Coefficient for 3-h.Caused by Rod Withdrawal & Consequent Xe Build Up.Procedure Being Revised | /03L-0 on 780624:unit Was Operated W/Positive Moderator Temp Coefficient for 3-h.Caused by Rod Withdrawal & Consequent Xe Build Up.Procedure Being Revised | | | 05000316/LER-1979-005-03, /03L-0 on 790117:solid State Protection Sys Tested Unsatisfactorily.Caused by Failure of Universal Logic Card A-214 | /03L-0 on 790117:solid State Protection Sys Tested Unsatisfactorily.Caused by Failure of Universal Logic Card A-214 | | | 05000315/LER-1979-006-03, /03L-0 on 790208:pressurizer Relief Tank Diaphragm Ruptured,Causing Ice Condenser Inlet Doors to Be Indicated Open.Caused by Pressure Surge in Lower Containment.Unit Shut Down & Doors Closed | /03L-0 on 790208:pressurizer Relief Tank Diaphragm Ruptured,Causing Ice Condenser Inlet Doors to Be Indicated Open.Caused by Pressure Surge in Lower Containment.Unit Shut Down & Doors Closed | | | 05000316/LER-1979-006-03, /03L-0 on 790123:svc Water Supply Check Valve to AB diesel,ESW-143,failed to Seat.Caused by Normal Wear of Split Center Disc of Carbon Steel Check Valve,Centerline Part D-10495-26 | /03L-0 on 790123:svc Water Supply Check Valve to AB diesel,ESW-143,failed to Seat.Caused by Normal Wear of Split Center Disc of Carbon Steel Check Valve,Centerline Part D-10495-26 | | | 05000316/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000316/LER-1979-007-03, /03L-0 on 790213:during Surveillance Test on Containment Pressure Set 3,high-high Bistable Trip Point Was Found to Exceed Tech Specs.Caused by Drifting Bistable. Bistable,Westinghouse Model 63V-BC-OHEA-F,was Replaced | /03L-0 on 790213:during Surveillance Test on Containment Pressure Set 3,high-high Bistable Trip Point Was Found to Exceed Tech Specs.Caused by Drifting Bistable. Bistable,Westinghouse Model 63V-BC-OHEA-F,was Replaced | | | 05000315/LER-1979-007-03, /03L-0 on 790218:suction Valve of West Centrifugal Charging Pump Found Closed.Caused by Mistaken Closing Following Surveillance Testing.Incident Is Being Reviewed | /03L-0 on 790218:suction Valve of West Centrifugal Charging Pump Found Closed.Caused by Mistaken Closing Following Surveillance Testing.Incident Is Being Reviewed | | | 05000316/LER-1979-008-03, /03L-0 on 790303:main Turbine Stop Valve C Closure Limit Switch Failed Conservatively (Closure Indication Received).Cause Unknown.Switch Replaced | /03L-0 on 790303:main Turbine Stop Valve C Closure Limit Switch Failed Conservatively (Closure Indication Received).Cause Unknown.Switch Replaced | | | 05000316/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000315/LER-1979-008-03, /03L-0 on 790207:containment Atmospheric Air Particulate & Gaseous Radiation Monitoring Sys Pump Was Continuously Tripping.Caused by Misalignment of Pump Bypass Flow Adjustments Due to Normal Pump Wear.Flow Rate Adjusted | /03L-0 on 790207:containment Atmospheric Air Particulate & Gaseous Radiation Monitoring Sys Pump Was Continuously Tripping.Caused by Misalignment of Pump Bypass Flow Adjustments Due to Normal Pump Wear.Flow Rate Adjusted | | | 05000315/LER-1979-009-03, /03L-0 on 790223:in Mode 1 Both Emergency Diesel Generators Were Inoperable on Separate Occasions.Caused by AB Diesel Generator Running in Parallel & Other Emergency Generator Out for Maint.Operating Procedures Revised | /03L-0 on 790223:in Mode 1 Both Emergency Diesel Generators Were Inoperable on Separate Occasions.Caused by AB Diesel Generator Running in Parallel & Other Emergency Generator Out for Maint.Operating Procedures Revised | | | 05000316/LER-1979-009-03, /03L-0 on 790303:2W Svc Water Pump Amp Pegged Meter Stopped,Constituting Inoperable Pump.Caused by Burr Formed Between Impeller Ring & Bowl.Pump Shaft & Bowl Replaced | /03L-0 on 790303:2W Svc Water Pump Amp Pegged Meter Stopped,Constituting Inoperable Pump.Caused by Burr Formed Between Impeller Ring & Bowl.Pump Shaft & Bowl Replaced | | | 05000316/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000315/LER-1979-010-03, /03X-1 on 790223:diesel Essential Svc Water Check Valves 1-ESW-111 & 1-ESW-114 Not Functioning Properly.Caused by Excessive Wear at Split Disc Hinge Points.Discs Replaced | /03X-1 on 790223:diesel Essential Svc Water Check Valves 1-ESW-111 & 1-ESW-114 Not Functioning Properly.Caused by Excessive Wear at Split Disc Hinge Points.Discs Replaced | | | 05000315/LER-1979-010, Forwards LER 79-010/03X-1 | Forwards LER 79-010/03X-1 | | | 05000316/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000316/LER-1979-010-03, /03L-0 on 790306:during Surveillance Test on Turbine Driven Auxiliary Feed Pump,Pump Was Over Max Recommended Temp.Possible Cause Was Foreign Matl in Bearing Oil.Oil Was Changed | /03L-0 on 790306:during Surveillance Test on Turbine Driven Auxiliary Feed Pump,Pump Was Over Max Recommended Temp.Possible Cause Was Foreign Matl in Bearing Oil.Oil Was Changed | | | 05000316/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000316/LER-1979-011-03, /03L-0 on 790327:outer Door Seal of Lower Containment Air Lock Found Leaking.Caused by Force Placed on Seal During Installation of Security Gate at Air Lock Entrance.Seal Tightened & Outer Seal Retested | /03L-0 on 790327:outer Door Seal of Lower Containment Air Lock Found Leaking.Caused by Force Placed on Seal During Installation of Security Gate at Air Lock Entrance.Seal Tightened & Outer Seal Retested | | | 05000315/LER-1979-011-03, /03L-0 on 790223:auxiliary Feedwater Discharge Valve Would Not Close from Control Room.Caused by Loose Connection in Hot Shutdown Panel.Connection Tightened & Correct Valve Operation Verified | /03L-0 on 790223:auxiliary Feedwater Discharge Valve Would Not Close from Control Room.Caused by Loose Connection in Hot Shutdown Panel.Connection Tightened & Correct Valve Operation Verified | | | 05000316/LER-1979-012-03, /03L-0 on 790330:hydraulic Control Values Did Not Return to Normal Position Placing Hydraulic Lock on Operator Cylinder.Caused by Dirt in Hydraulic Pilot Valve.Hydraulic Fluid Replaced | /03L-0 on 790330:hydraulic Control Values Did Not Return to Normal Position Placing Hydraulic Lock on Operator Cylinder.Caused by Dirt in Hydraulic Pilot Valve.Hydraulic Fluid Replaced | | | 05000315/LER-1979-012-03, /03L-0 on 790226:containment Air Monitor Pump Overheated.Caused by Worn Rubber Spider in Lovejoy L-100 Coupling.Spider Replaced & Air Sampler Retested | /03L-0 on 790226:containment Air Monitor Pump Overheated.Caused by Worn Rubber Spider in Lovejoy L-100 Coupling.Spider Replaced & Air Sampler Retested | | | 05000316/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000315/LER-1979-013-03, /03L-0 on 790303:auxiliary Feed Valve FMO-212 Would Not Shut from Control Room.Caused by Broken Wire in Valves Motor Operator.Breakage Is a Result of Vibration & Use of Solid Conductor Wire.Wire Replaced | /03L-0 on 790303:auxiliary Feed Valve FMO-212 Would Not Shut from Control Room.Caused by Broken Wire in Valves Motor Operator.Breakage Is a Result of Vibration & Use of Solid Conductor Wire.Wire Replaced | | | 05000316/LER-1979-013-03, /03L-0 on 790407:during Rapid Shutdown,Pressure Was Allowed to Drop to 2,190 Lb Psig.Caused by Spray Valve Which Was Slow to Respond.Spray Placed in Manual & Throttled Back | /03L-0 on 790407:during Rapid Shutdown,Pressure Was Allowed to Drop to 2,190 Lb Psig.Caused by Spray Valve Which Was Slow to Respond.Spray Placed in Manual & Throttled Back | | | 05000315/LER-1979-014-03, /03L-0 on 790301:while in Mode 1,indicated Position of Rod F-6 Discovered to Be Oscillating within 15 Steps of Bank Demand Position.Caused by Signal Conditioning Module Connector.Cleaning & Reinstallation Corrected Limits | /03L-0 on 790301:while in Mode 1,indicated Position of Rod F-6 Discovered to Be Oscillating within 15 Steps of Bank Demand Position.Caused by Signal Conditioning Module Connector.Cleaning & Reinstallation Corrected Limits | | | 05000315/LER-1979-014, Forwards LER 79-014/03L-0 & 79-015/03L-0 | Forwards LER 79-014/03L-0 & 79-015/03L-0 | | | 05000316/LER-1979-014-03, /03L-0 on 790404:on Two Occasions Rod Position Indication Exceeded 12-step Limit.Caused by Drifting of Signal Conditioning Modules,Which Were Adjusted for Proper Output | /03L-0 on 790404:on Two Occasions Rod Position Indication Exceeded 12-step Limit.Caused by Drifting of Signal Conditioning Modules,Which Were Adjusted for Proper Output | | | 05000315/LER-1979-015-03, /03L-0 on 790302:while Operating at Full Power, Pressurizer Relief Tank Rupture Disc Blew Out,Causing Ice Condenser Inlet Doors to Open.Caused by Pressure Fluctuations Resulting in Weakened Rupture Discs | /03L-0 on 790302:while Operating at Full Power, Pressurizer Relief Tank Rupture Disc Blew Out,Causing Ice Condenser Inlet Doors to Open.Caused by Pressure Fluctuations Resulting in Weakened Rupture Discs | | | 05000316/LER-1979-015-03, /03L-0 on 790409:during Plant Startup,Small Crack & Pinhole Leak Found in Body of FMO-232,at Inlet Side of Valve Adjacent to Weld.Cause of Crack Not Determined. Radiographs of Area Reviewed | /03L-0 on 790409:during Plant Startup,Small Crack & Pinhole Leak Found in Body of FMO-232,at Inlet Side of Valve Adjacent to Weld.Cause of Crack Not Determined. Radiographs of Area Reviewed | | | 05000315/LER-1979-016-03, /03L-0 on 790304:two Manual Containment Isolation Valves Were Inadvertantly Left Open Following Routine Sample of Instrument Room.Caused by Personnel Oversight.Both Valves Were Returned to Their Normally Closed Positions | /03L-0 on 790304:two Manual Containment Isolation Valves Were Inadvertantly Left Open Following Routine Sample of Instrument Room.Caused by Personnel Oversight.Both Valves Were Returned to Their Normally Closed Positions | | | 05000316/LER-1979-016-03, /03L-0 on 790412:failure of Interlock,Which Prevents Opening Both Containment 650 Ft Level Airlock Doors.Caused by Slack in Actuator Cables & Weak Spring.One Cable & Spring Replaced | /03L-0 on 790412:failure of Interlock,Which Prevents Opening Both Containment 650 Ft Level Airlock Doors.Caused by Slack in Actuator Cables & Weak Spring.One Cable & Spring Replaced | | | 05000315/LER-1979-017-03, /03L-0 on 790312:spent Fuel Pit Exhaust Ventilation Unit Flow Failed to Meet Acceptance Criteria. Caused by Slight Closing of Intake Grills Due to Sys Vibration.Grill Damper Linkage Securely Fastened | /03L-0 on 790312:spent Fuel Pit Exhaust Ventilation Unit Flow Failed to Meet Acceptance Criteria. Caused by Slight Closing of Intake Grills Due to Sys Vibration.Grill Damper Linkage Securely Fastened | | | 05000316/LER-1979-017-03, /03L-0 on 790423:while Performing STP 022, Essential Svc water-142, Essential Svc Valve to 2 Cd Diesel Did Not Seat Properly.Caused by Excessive Wear of Split Disc Hinge Points.Stainless Steel Discs Were Substituted | /03L-0 on 790423:while Performing STP 022, Essential Svc water-142, Essential Svc Valve to 2 Cd Diesel Did Not Seat Properly.Caused by Excessive Wear of Split Disc Hinge Points.Stainless Steel Discs Were Substituted | | | 05000316/LER-1979-017, Forwards LER 79-017/03L-0 | Forwards LER 79-017/03L-0 | | | 05000315/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000316/LER-1979-018-03, /03L-0 on 790423:during Investigation of Periodic Alarms for Steam Generator High Steam Line Flow,Controller 2 Py 506B (Turbine Impulse Pressure) Was in Manual Control. Caused by Controller Not Being Returned to Automatic | /03L-0 on 790423:during Investigation of Periodic Alarms for Steam Generator High Steam Line Flow,Controller 2 Py 506B (Turbine Impulse Pressure) Was in Manual Control. Caused by Controller Not Being Returned to Automatic | |
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