/03X-1:on 830428,pressurizer Sample Isolation Valve Failed to Close.Caused by Personnel Error & Inadequate Maint Procedures.Torque Switch Reset,Valve Stem Cleaned & Lubricated & Maint Order 1-83-3114-00 Rewritten| ML20140B702 |
| Person / Time |
|---|
| Site: |
Davis Besse  |
|---|
| Issue date: |
01/17/1986 |
|---|
| From: |
Long J TOLEDO EDISON CO. |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML20140B691 |
List: |
|---|
| References |
|---|
| LER-83-020-03X, LER-83-20-3X, NUDOCS 8601270096 |
| Download: ML20140B702 (3) |
|
LER-1983-020, /03X-1:on 830428,pressurizer Sample Isolation Valve Failed to Close.Caused by Personnel Error & Inadequate Maint Procedures.Torque Switch Reset,Valve Stem Cleaned & Lubricated & Maint Order 1-83-3114-00 Rewritten |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3461983020R03 - NRC Website |
|
text
.
NRC FORM 364:
U.S. NUCLEAR REGULATORY COMMISSION (7 77)
LICENSEE EVENT REPORT CONYROL BLOCK: l l
l l
l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
10111 lo l H i n i B l S I i l@l e l e l -l e l e 1 e 10101 - 10 l e l@l 4 l i l 1 l 111 l@l l
l@
7 8 9 LICENSEE CODE 14 15 LICENSE NUM8ER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T ITTTI
%U I t l@le 15 I e l e le 1314 l 6 l@l e l 4 l ? l 8 l 813 l@l l
l l
l l
l@
7 8
60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES Oio lo lal l (NP-33-83-27) On April 28, 1983 at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br /> while attempting to shut RC240B from l g[ the Control Room, the valve would not shut unless the close button was repeatedly l
l pushed. RC240B was declared inoperable, placing the unit in the action statement l
o 4
' i o i s ; l of Technical Specification 3.6.3.1, which requires the inoperable valve to be l
0 s l restored within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or isolate the affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or be l
[TlTl I in Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in Cold Shutdown within the following l
l 0 la l l 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
I CO E S 8C E COMPONENT CODE SUSC dE SU E
l S l D l@ Wh Wh l V l A l L l V l 0 l P lh W@ (Z_J @
O 9 7
8 9
10 11 12 13 19 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION L
EVENT YE AR REPORT No.
CODE TYPE No.
@,a=ER/Rol 8131 1-1 I e 1210 i td le13i [x_l t-j l11 1
_ 21 22 23 24 26 27 N
M 30 31 32 KN AC O P NT ME HOURS
$ SMI FOR 8.
SUPPL MANUF C RER
% [34jij@
l_Z_j@
lZl@
l0l0leIel
[_YJ@ Wg lN l@
lLl2lejel@
33 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l The cause was inadequate maintenance procedures and lack of proper training.
Under,
, o
- MWO 83-2864, the valve stem was found dirty and not lubricated, and the torque i
,, l switch was not set properly. The torque switch was set to the E-15 settings and g
3 3 l the valve stem cleaned'and lubricated. RC240B was returned to service at 1855 l
, 4 l hours on 4/28/83 removing the unit from the action statement.
l
'ST E E
^
'4 POWER OTHER STATUS dis O RY DISCOVERY DESCRIPTION
[_Ej@ l 0 l 9 l 8 l@l NA l
[AJ@l Operator observation l
i s ACTivlTY CO TENT RELEASE @D OF RELEASE @l AM3UNT OF ACTIVITY LOCATION OF RELEASE NA l
l NA l
i 6 PEASONNEL EXPOS ES RiPTIO~ @
NUu8E R TYPE oES:
leIeIsl@[JJ@lNA
_j i 7 h,,.' I e luM8ER PeRSONNE L INauEiES oESCRiPTiON@
eso127oo96 e6o117 Gl Gl@l NA PDR ADOCK 050 6
l 7
8 9 11 12 3
80 W ' "="R PT ON' '
'^c' " @
^
@ W@l NA l
7
. 9 10 80 oESCRiPTiON @
NRC USE ONLY ISSUE [N_jhl NA l
lllllllllllllj 2 O 7
8 9 10 68 69 80 DVR 83-047 NAME OF PREPARER PHONE:
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-83-27 DATE OF EVENT: April 28, 1983 FACILITY:
Davis-Besse Unit 1 i
IDENTIFICATION OF OCCURRENCE:
Pressurizer Sample Isolation Valve (RC240B) failed to close Conditions Prior to Occurrence:
The unit was Mode 1, with Power (MWT) = 2716 and Load (Gross MWE) = 900.
Description of Occurrence:
On April 28, 1983, at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br /> while attempting to shut RC240B from the Control Room, the valve would not shut unless the close button was pushed repeatedly.
RC240B was declared inoperable, and the unit entered the action statement of Technical Specification 3.6.3.1 which requires the inoperable valve to be restored to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or isolate the affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or be in at least Hot Standby t
within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in Celd Shutdown within the following i
30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
7 Designation of Apparent Cause of Occurrence: The apparent cause i
of this occurrence was the valve operator torquing out due to a dirty and improperly lubricated valve stcm.
The root cause of this occur-y ance was a lack of proper training and inadequate Maintenance Pro-cedures (MP's) for conducting maintenance on Limitorque valve operators.
Analysis of Occurrence:
There was no danger to the health and safety of the public or station personnel.
The redundant upstream isolation valve (RC240A) was operable had containment isolation been required.
Corrective Action
At 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br />, RC240A was closed and tagged iso-lating the affected penetration.
Maintenance Work Order 83-2864 was issued to investigate the control scheme of RC240B.
It was observed that the valve stem was dirty and lacked lubrication. Additionally, the torque switch was found to be set at 3 open and 1 close. The required setting per E-15 was 2 open and 2 close.
The torque switch was reset to the E-15 value, and the valve sten was cleaned and lub-ricated.
RC240B was tested per Surveillance Test ST 5064.01 and returned to service.
RC240A was declared operable at 1855 hours0.0215 days <br />0.515 hours <br />0.00307 weeks <br />7.058275e-4 months <br /> on April 28, 1983, removing the unit from the action statement.
RC240B had been incorporated into the station Preventive Maintenance Program for routine inspection and lubrication, however, the preventive maintenance had not yet been performed.
When RC240B was inspected, it was noted that it had the older style torque switch.
Maintenance Work order 1-83-3114-00 has been written to replace the torque switch with
(
the new style.
No documentation was found that changed the torque
. oTOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL IhTORMATION FOR LER NP-33-83-27 PAGE 2 Corrective Action Cont':
switch settings from the E-15 value.
Presently, all maintenance work orders involving Limitorque torque switch settings require documentation of as-found and as-left settings.
When RC240B failed, it was our understanding that there were two different styles of torque switches for the SMB-000 size operators.
During subsequent conversations with Limitorque, they informed us that they only make one style of torque switch for the SMB-000 operators.
Therefore, the torque switch will not be changed out.
In addition, y
maintenance procedures MP1410.32 and 1411.04 thru 1411.07 have been written to test the valver using Motor Operated Valve Analysis and Test System (MOVATS) and provide detailed instructions for corrective and preventive maintenance.
We have also initiated a training program and certification process to ensure that only qualified personnel work on Limitorque operators.
Failure Data:
A previous failure of RC240B failing to close was reported in Licensee Event Report NP-33-80-18 (80-014).
LER #83-020 O
O
., - -, - - - _ -,, +,,
,,-------.w
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000346/LER-1983-001, Forwards LER 83-001/03L-0 | Forwards LER 83-001/03L-0 | | | 05000346/LER-1983-001-03, /03L-0:on 830114,loss of Power to Loop 2 Main Feedwater Block Valve Initiated Feedwater Transient.Caused by Control Rod Insertion from Approx 95% to 75%.Rods Withdrawn | /03L-0:on 830114,loss of Power to Loop 2 Main Feedwater Block Valve Initiated Feedwater Transient.Caused by Control Rod Insertion from Approx 95% to 75%.Rods Withdrawn | | | 05000346/LER-1983-002, Forwards LER 83-002/03L-0 | Forwards LER 83-002/03L-0 | | | 05000346/LER-1983-002-03, /03L-0:on 830114 & 15,after Reactor Trips,Rcs Dose Equivalent I-131 Exceeded Tech Spec Limit.Caused by Slight Leakage of Fission Products Through Fuel Cladding.Caused by Temp & Pressure Changes.Situation Monitored | /03L-0:on 830114 & 15,after Reactor Trips,Rcs Dose Equivalent I-131 Exceeded Tech Spec Limit.Caused by Slight Leakage of Fission Products Through Fuel Cladding.Caused by Temp & Pressure Changes.Situation Monitored | | | 05000346/LER-1983-003, Forwards LER 83-003/03L-0 | Forwards LER 83-003/03L-0 | | | 05000346/LER-1983-003-03, /03L-0:on 830119,MSIV MS100 Failed to Shut Completely Following Reactor Trip on 830118.Cause Unknown. Valves Disassembled & Inspected W/No Problems Found.Valve Tested & Returned to Svc | /03L-0:on 830119,MSIV MS100 Failed to Shut Completely Following Reactor Trip on 830118.Cause Unknown. Valves Disassembled & Inspected W/No Problems Found.Valve Tested & Returned to Svc | | | 05000346/LER-1983-004, Forwards LER 83-004/03L-0 | Forwards LER 83-004/03L-0 | | | 05000346/LER-1983-004-03, /03L-0:on 830119,during Cooldown,Jumper on Pressure Switch PSH-RC2B4 Had Been Left in Place Since 820823.Caused by Lack of Administrative Control & Design Error.Procedure Rewritten to Provide Adequate Switch | /03L-0:on 830119,during Cooldown,Jumper on Pressure Switch PSH-RC2B4 Had Been Left in Place Since 820823.Caused by Lack of Administrative Control & Design Error.Procedure Rewritten to Provide Adequate Switch | | | 05000346/LER-1983-005-03, /03L-0:on 830127,acceptance Criteria of Containment Airlock Seal Leakage Surveillance Test ST 5061.05 Did Not Agree W/Tech Spec Surveillance Requirements.Caused by Procedure Deficiency | /03L-0:on 830127,acceptance Criteria of Containment Airlock Seal Leakage Surveillance Test ST 5061.05 Did Not Agree W/Tech Spec Surveillance Requirements.Caused by Procedure Deficiency | | | 05000346/LER-1983-005, Forwards LER 83-005/03L-0 | Forwards LER 83-005/03L-0 | | | 05000346/LER-1983-006-03, /03L-0:on 830126,door 311,auxiliary Bldg Southeast Stairway at 585-ft Level,Found Open.Caused by Failure of Closure Mechanism Due to Normal Wear.Closure Mechanism Replaced | /03L-0:on 830126,door 311,auxiliary Bldg Southeast Stairway at 585-ft Level,Found Open.Caused by Failure of Closure Mechanism Due to Normal Wear.Closure Mechanism Replaced | | | 05000346/LER-1983-006, Forwards LER 83-006/03L-0 | Forwards LER 83-006/03L-0 | | | 05000346/LER-1983-007-03, /03L-0:on 830131,loss of 120-volt Ac Essential Bus Y1 Experienced.Pressurizer Level Indication from LT-RC-14-3 Lost.Loss of Y1 Caused by Failure of YV1 Inverter Input Fuse.Root Cause Unknown | /03L-0:on 830131,loss of 120-volt Ac Essential Bus Y1 Experienced.Pressurizer Level Indication from LT-RC-14-3 Lost.Loss of Y1 Caused by Failure of YV1 Inverter Input Fuse.Root Cause Unknown | | | 05000346/LER-1983-007, Forwards LER 83-007/03L-0 | Forwards LER 83-007/03L-0 | | | 05000346/LER-1983-008, Forwards LER 83-008/03L-0 | Forwards LER 83-008/03L-0 | | | 05000346/LER-1983-008-03, Battery 2P Cell 18 & Battery 1P Cell 33 Specific Gravity Found Below 1.200 & Battery 1N Pilot Cell 33 Voltage Read Below 2.13.Caused by Tech Spec 4.8.2.3.2 Too Stringent for Batteries | Battery 2P Cell 18 & Battery 1P Cell 33 Specific Gravity Found Below 1.200 & Battery 1N Pilot Cell 33 Voltage Read Below 2.13.Caused by Tech Spec 4.8.2.3.2 Too Stringent for Batteries | | | 05000346/LER-1983-009, Forwards LER 83-009/03L-0 | Forwards LER 83-009/03L-0 | | | 05000346/LER-1983-010, Forwards LER 83-010/03L-0 | Forwards LER 83-010/03L-0 | | | 05000346/LER-1983-010-03, /03L-0:on 830207,during Performance of Auxiliary Feedwater Sys Channel Functional Test,Isolation Valve MS106A Failed to Close Electrically.Caused by Dirty & Improperly Lubricated Valve Stem.Valve Stem & Drive Nut Cleaned | /03L-0:on 830207,during Performance of Auxiliary Feedwater Sys Channel Functional Test,Isolation Valve MS106A Failed to Close Electrically.Caused by Dirty & Improperly Lubricated Valve Stem.Valve Stem & Drive Nut Cleaned | | | 05000346/LER-1983-011-03, /03L-0:on 830211,auxiliary Feedwater Pump Turbine 2 Overspeed Trip Alarm Sounded.Caused by Personnel Error. Personnel Bumped Turbine Overspeed Trip Linkage Causing Trip of Trip Throttle Valve When Removing Case Guards | /03L-0:on 830211,auxiliary Feedwater Pump Turbine 2 Overspeed Trip Alarm Sounded.Caused by Personnel Error. Personnel Bumped Turbine Overspeed Trip Linkage Causing Trip of Trip Throttle Valve When Removing Case Guards | | | 05000346/LER-1983-011, Forwards LER 83-011/03L-0 | Forwards LER 83-011/03L-0 | | | 05000346/LER-1983-012, Forwards Revised LER 83-012/01X-2 | Forwards Revised LER 83-012/01X-2 | | | 05000346/LER-1983-012-01, Operating Practice of Requiring One ECCS Room Cooler to Be Valved Into Svc in Each ECCS Room Less Conservative than Updated FSAR Assumptions. Caused by Lack of Procedural Control.Fsar Reviewed | Operating Practice of Requiring One ECCS Room Cooler to Be Valved Into Svc in Each ECCS Room Less Conservative than Updated FSAR Assumptions. Caused by Lack of Procedural Control.Fsar Reviewed | | | 05000346/LER-1983-013, Forwards LER 83-013/03L-0 | Forwards LER 83-013/03L-0 | | | 05000346/LER-1983-013-03, /03L-0:on 830304,chlorine Detector AE5358B Tripped Causing Shutdown of Control Room Normal Ventilation Sys. Caused by Component Failure.Orifice Cleaned & Wick Replaced | /03L-0:on 830304,chlorine Detector AE5358B Tripped Causing Shutdown of Control Room Normal Ventilation Sys. Caused by Component Failure.Orifice Cleaned & Wick Replaced | | | 05000346/LER-1983-014-03, /03L-0:on 830305,rod 12 of Group 7 Began to Ratchet Trip Into Core.Caused by Blown Fuse in Transfer Switch Module Assembly B Phase.Blown Fuse Replaced.Control Rod 7-12 Successfully Latched & Pulled | /03L-0:on 830305,rod 12 of Group 7 Began to Ratchet Trip Into Core.Caused by Blown Fuse in Transfer Switch Module Assembly B Phase.Blown Fuse Replaced.Control Rod 7-12 Successfully Latched & Pulled | | | 05000346/LER-1983-014, Forwards LER 83-014/03L-0 | Forwards LER 83-014/03L-0 | | | 05000346/LER-1983-015, Forwards LER 83-015/03L-0 | Forwards LER 83-015/03L-0 | | | 05000346/LER-1983-015-03, /03L-0:on 830304,emergency Diesel Generator Output Oscillated Unsteadily.Cause Isolated to Electric Governor Control Sys.Breaker Will Be Repaired Upon Receipt of Assistance from Manufacturer | /03L-0:on 830304,emergency Diesel Generator Output Oscillated Unsteadily.Cause Isolated to Electric Governor Control Sys.Breaker Will Be Repaired Upon Receipt of Assistance from Manufacturer | | | 05000346/LER-1983-016-03, Amplifier of Startup Level Transmitter LT-SP9A3 for Steam Generator 1-2 Failed. Caused by Component Failure within Amplifier.Amplifier Replaced | Amplifier of Startup Level Transmitter LT-SP9A3 for Steam Generator 1-2 Failed. Caused by Component Failure within Amplifier.Amplifier Replaced | | | 05000346/LER-1983-016, Forwards LER 83-016/03L-0 | Forwards LER 83-016/03L-0 | | | 05000346/LER-1983-017-03, /03L-0:on 830411,spent Fuel Pool (SFP) Level Verification Surveillance Test Ordered Later than Tech Spec Requirement.Caused by Personnel Error.Sfp Level Verified. Memo on Schedules Planned | /03L-0:on 830411,spent Fuel Pool (SFP) Level Verification Surveillance Test Ordered Later than Tech Spec Requirement.Caused by Personnel Error.Sfp Level Verified. Memo on Schedules Planned | | | 05000346/LER-1983-020, Forwards Resubmittal of LER 83-020,Rev 1,correcting Inadvertent Listing of Page 1 Sequential Number as 83-027 | Forwards Resubmittal of LER 83-020,Rev 1,correcting Inadvertent Listing of Page 1 Sequential Number as 83-027 | | | 05000346/LER-1983-020-03, /03X-1:on 830428,pressurizer Sample Isolation Valve Failed to Close.Caused by Personnel Error & Inadequate Maint Procedures.Torque Switch Reset,Valve Stem Cleaned & Lubricated & Maint Order 1-83-3114-00 Rewritten | /03X-1:on 830428,pressurizer Sample Isolation Valve Failed to Close.Caused by Personnel Error & Inadequate Maint Procedures.Torque Switch Reset,Valve Stem Cleaned & Lubricated & Maint Order 1-83-3114-00 Rewritten | | | 05000346/LER-1983-021-03, /03L-0:on 830502,operator Found Fuel Handling Access Corridor Door 406 Ajar.Caused by Failure of Closure Mechanism.Closure Mechanism Adjusted to Force Door Closed | /03L-0:on 830502,operator Found Fuel Handling Access Corridor Door 406 Ajar.Caused by Failure of Closure Mechanism.Closure Mechanism Adjusted to Force Door Closed | | | 05000346/LER-1983-022-03, /03L-0:on 830513,determined Erratic Generator Output in Response to Speed Change Input on 830413 Reportable.Caused by Loose Connection on Electronic Governor Control Box.Terminal Screw Cross Threaded | /03L-0:on 830513,determined Erratic Generator Output in Response to Speed Change Input on 830413 Reportable.Caused by Loose Connection on Electronic Governor Control Box.Terminal Screw Cross Threaded | | | 05000346/LER-1983-023-03, /03L-0:on 830510,120-volt Ac Essential Bus Y4 Lost,Resulting in Deenergizing Reactor Protection & Safety Features Actuation Sys Channel 4.Caused by Blown Fuse in Inverter YV4.Power Restored to Bus | /03L-0:on 830510,120-volt Ac Essential Bus Y4 Lost,Resulting in Deenergizing Reactor Protection & Safety Features Actuation Sys Channel 4.Caused by Blown Fuse in Inverter YV4.Power Restored to Bus | | | 05000346/LER-1983-024-03, /03L-0:on 830511,while Starting Up from 830510 Reactor Trip,Quadrant Power Tilt in Quadrant Yz Exceeded Tech Spec steady-state Limit.Caused by Inherent Design of B&W NSSS & Negative Moderator Temp Coefficient | /03L-0:on 830511,while Starting Up from 830510 Reactor Trip,Quadrant Power Tilt in Quadrant Yz Exceeded Tech Spec steady-state Limit.Caused by Inherent Design of B&W NSSS & Negative Moderator Temp Coefficient | | | 05000346/LER-1983-026-03, /03L-0:on 830524,one Half Channel Trip in Steam & Feedwater Rupture Control Sys (Sfrcs) Channel 2 Received. Caused by Component Failure.Input Buffer Replaced | /03L-0:on 830524,one Half Channel Trip in Steam & Feedwater Rupture Control Sys (Sfrcs) Channel 2 Received. Caused by Component Failure.Input Buffer Replaced | | | 05000346/LER-1983-027-03, /03X-1:on 830428,valve RC240B Declared Inoperable. Caused by Inadequate Maint Procedures & Lack of Proper Training.Torque Switch Set to E-15 Settings & Valve Stem Cleaned & RC240B Returned to Svc | /03X-1:on 830428,valve RC240B Declared Inoperable. Caused by Inadequate Maint Procedures & Lack of Proper Training.Torque Switch Set to E-15 Settings & Valve Stem Cleaned & RC240B Returned to Svc | | | 05000346/LER-1983-028-03, /03L-0:on 830603 & 17,fuel Handling Area Radiation Monitors RE8446 & 7 Found Deenergized.Caused by Blown Radiation Monitoring Cabinet Fuse.Fuse Replaced | /03L-0:on 830603 & 17,fuel Handling Area Radiation Monitors RE8446 & 7 Found Deenergized.Caused by Blown Radiation Monitoring Cabinet Fuse.Fuse Replaced | | | 05000346/LER-1983-029-03, /03L-0:on 830612,main Steam Safety Valve on Steam Generator 1-1 Header Actuated.Cause Unknown.All Main Steam Safety Valves Will Be Tested | /03L-0:on 830612,main Steam Safety Valve on Steam Generator 1-1 Header Actuated.Cause Unknown.All Main Steam Safety Valves Will Be Tested | | | 05000346/LER-1983-030-03, /03L-0:on 830614,during Change in ECCS Coil Assembly 1,floor Plugs Forming Part of Negative Pressure Boundary & Fire Barriers Removed.Caused by Personnel Error. Floor Plugs Reinstalled & New Procedure Written | /03L-0:on 830614,during Change in ECCS Coil Assembly 1,floor Plugs Forming Part of Negative Pressure Boundary & Fire Barriers Removed.Caused by Personnel Error. Floor Plugs Reinstalled & New Procedure Written | | | 05000346/LER-1983-031-01, /01T-0:on 830708,chlorine Detectors AE4863A & B Determined Inadequately Protected Against All Types of Missiles.Caused by Bechtel Design Error.Tornado Procedure AD 1827.06 Modified | /01T-0:on 830708,chlorine Detectors AE4863A & B Determined Inadequately Protected Against All Types of Missiles.Caused by Bechtel Design Error.Tornado Procedure AD 1827.06 Modified | | | 05000346/LER-1983-033-03, Fire Detection Zone Reactor Coolant Pump 1-2,containment Level 603 Went Into Alarm & Could Not Be Reset.Caused by Failed Smoke Detector.Detector Replaced | Fire Detection Zone Reactor Coolant Pump 1-2,containment Level 603 Went Into Alarm & Could Not Be Reset.Caused by Failed Smoke Detector.Detector Replaced | | | 05000346/LER-1983-036-03, /03L-0:on 830715,safety Features Actuation Signal Channel 4 Containment Radiation Monitor RE2007 Failed Low. Monitor Also Inoperable on 830721 Due to Spiking.Exact Cause Unknown | /03L-0:on 830715,safety Features Actuation Signal Channel 4 Containment Radiation Monitor RE2007 Failed Low. Monitor Also Inoperable on 830721 Due to Spiking.Exact Cause Unknown | | | 05000346/LER-1983-036, Revised LER 83-036/03X-1:on 830715 & 21,safety Features Actuation Sys Channel 4 Containment Radiation Monitor RE2007 Failed Low.Caused by Detector failure.RE2007 Replaced | Revised LER 83-036/03X-1:on 830715 & 21,safety Features Actuation Sys Channel 4 Containment Radiation Monitor RE2007 Failed Low.Caused by Detector failure.RE2007 Replaced | | | 05000346/LER-1983-038-03, /03L-1:on 830725,half Trip of Steam & Feedwater Line Rupture Control Sys Actuation Channel 1 & Spurious Trip of Logic Channel 1 Occurred.Caused by Failed Power Supply & Relay Driver Board,Respectively.Parts Replaced | /03L-1:on 830725,half Trip of Steam & Feedwater Line Rupture Control Sys Actuation Channel 1 & Spurious Trip of Logic Channel 1 Occurred.Caused by Failed Power Supply & Relay Driver Board,Respectively.Parts Replaced | | | 05000346/LER-1983-039-03, /03X-1:on 830726,discovered That W/Hand Wheel for Containment Personnel Hatch Inner Door in Shut Position, Door Partially Open.Caused by Design Error.Personnel Lock Repaired & Returned to Operable Status | /03X-1:on 830726,discovered That W/Hand Wheel for Containment Personnel Hatch Inner Door in Shut Position, Door Partially Open.Caused by Design Error.Personnel Lock Repaired & Returned to Operable Status | | | 05000346/LER-1983-040-03, Auxiliary Feed Pump 1-1 Failed to Respond to Speed Change Signals from Automatic & Manual Control.Caused by Design Deficiency in Clutch Mechanism.New Design Slip Clutch Installed | Auxiliary Feed Pump 1-1 Failed to Respond to Speed Change Signals from Automatic & Manual Control.Caused by Design Deficiency in Clutch Mechanism.New Design Slip Clutch Installed | |
|