LER-1980-078, /03L-0:on 801027,reactor Protection Sys Channel 1 Tripped on Shutdown/Bypass High Pressure Trip.Caused by Loose Solder Connection in Lead from Pressure Detector Element & Loose Lock Nut.Connection Repaired |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3461980078R03 - NRC Website |
|
text
U.S. NUCLEAR REGULATORY COMMISSION 4RC F OIM 366 i7 77)
LICENSEE EVENT REPORT CONTROL BLOCK: l l
l l
l l
lh (PLE ASE PRINT OR TYPE ALL REQUlRED INFORMATION) l 6
l o l H l D I B l S l 1 l@l 0 l e l 0 l 0 l '8 l 0 l 0 l 6 l e l 0 l 6 l@l 4 l 1 l 1 l 1 l 1 l@l l
l@
3 8 9 LICENSEE CODE 14 15 LICENSE NUMdER 25 26 LICENSE TYPE JO DI CAI Sd l L l@l 0 l 5 l 0 l - l 0 l 3 l 416 l@l 110 l 217 l 8 l 6 l@l 1 l 1 l 2 ] 6 l CON'T lolil i
8 60 61 DOCKET NUMBER ha 69 EVENT DATE 74 75 REPORT OATE 80 s
EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h l (NP-33-80-106) On 10/27/80 at 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br />, Reactor Protection System (RPS) Channel 1 l
o 2 ITTTl I tripped on a shutdown / bypass high pressure trip. Since the non-nuclear instrumentationi l 0141 I reactor coolant system (RCS) pressure input signal comes from RPS Channel 1, a chain ofl l o i s i l events occurred which caused RCS pressure to drop to 640 psig. The station entered thel l o ls l l action statement of T.S. 3.3.1.1, and the failed channel was placed in the tripped conf j o l 7 l l dition within one hour. There was no danger to the public or station personnel. There l l
t o IR I l was no release of primary coolant and pressure remained within limits.
OE CODE S BC E COMPONENT CODE SUB ODE S
E lIl Al@ y@ lE l@ l Il Nl Sl Tl Rl Ul@ ]@ ]@
o 9 7
8 9
10 11 12 13 18 19 20 SEouENTIAL OCCURRENCE REPORT REVISION LER/Ro EVENT YEAR REPORT NO.
CODE TYPE NO.
l 8l 0l l-l l0 l7 l8 l l0l3l lL l l_l
@ yu RE
,,,,,, 21 22 23 24 26 27 28 23 30 31 32 K N AC O ON PL NT E
HOURS SB IT FO 1 8.
5 PPLIE MAN FACTURER ls_J@lzl@
l zl@
Iz l@
l el el el el I vi@
LNj@
l Nl@
l R l 3 l 6 l 9 l@
33 34 34 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l i l o l ]The cause was a loose solder connection in the lead coming from the pressure detector l j i j [ element. The lock nut on the pipe between the detector housing and amplifier housing I
lt g,,,,lvas loose. The housing had rotated with respect to each other putting a stress on thel g l wiring soldered connection. Apparently the housing had been bumped by construction l
g l personnel during the past outage. The connection was repaired and-RPS Channel 1 operable on 10/30/80. so 7
8 9
'STjgs oTHERsTATVs b $iSEONRY
'C v
DISCOVERY OESCRIPTioN sPowER [1_15_j l C l@ l0 l0 l0 l@lNA l
lA l@l Operator observation l
ACTivn Y CO TENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION oF RELEASE l
[zj @ [_zj@l NA l
l NA i
6' PERSONNEL nPOSuEES l 0 l 0 l 0 lhl TYPE @l DESCRIPTION l
NUM8E R Zl NA i 7 PERSONNE L INJU IES Nuv8ER oESCRIPTION l
ITT 1 I e 10 l o l@l NA 80 7
8 9 11 12 LOSS of OR DAMAGE To FACILITY TYPE
DESCRIPTION
l LL12J LzJ@l NA 80 H 9 10 i i i i li 1% SUE [@UESCRIPTIO*4 g 012 0 2 05~13 i
i i i i i i i i Ly_
l NA 68 69 80 %
- o F
8
'3 10 419-259-5000, Ext. 231
{
~ NAME OF PHEPAREH _
DVR 80-192 hhn Wrn" PHONE:
v
a l
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-106 DATE OF EVENT: October 27, 1980 FACILITY:
Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: -Reactor Protection System (RPS) Pressure Transmitter Failure Conditions Prior to Occurrence: The unit was in Mode 3 with Power (MWT) = 0 and Load (Gross MWE) = 0.
Description of Occurrence: On October 27, 1980 at about 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br />, the RPS Channel 1 pressure indication failed high causing RPS Channel 1 to trip on a shutdown / bypass high pressure trip. Also, because the non-nuclear instrumentation (NNI) reactor coolant system (RCS) pressure input signal was coming from RPS Channel 1, the following occurred: The pressurizer heaters turned off, the spray valve opened, and the power operated relief valve (PORV) received an open signal.
Since the PORV block valve, RCll, was closed, the PORV did not open.
Upon indication of decreasing RCS pressure due to the open spray valve, the operators manually closed both the spray valve and its block valve. RCS pressure dropped to about 640 pounds. The unit was placed in Action Statement 3 of Technical Specification 3.3.1.1 which required the failed RPS channel to be tripped within one hour. The channel was tripped in about 30 minutes.
Designation of Apparent Cause of Occurrence: The apparent cause of the occurrence was a loose solder connection found in the Channel 1 pressure detector signal lead coming from the pressure detector element.
Investigation revealed that the lock nut on the connecting pi,.a between the detector housing and the amplifier housing was loose, enabling one to be rotated with respect to the other.
This would put a rotational stress on the soldered connections.
There had been scaffolding installed near the detector during the refueling outage.
It appears that construction personnel may have bumped the housing on the detector or amplifier causing a weakening of the soldered connection.
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. There was no release of primary coolant and pressure re-mained in the allowable operating band at all times.
Corrective Action
Within 30 minutes the NNI RCS pressure input signal was changed over to RPS Channel 2, thus restoring all NNI functions lost. Under Maintenance Work Order IC-720-80, the locknut was tightened, the broken pressure transmitter lead was discovered and repaired, a transeitter calibration and time response performed, and the channel returned to service, thus removing the unit from the action statement of Technical Specification 3.3.1.1.
All other containment pressure transmitter lock-nuts were checked tight, and none found loose.
RPS Channel 1 was declared operable at 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> on October 30, 1980.
LER #80-078 I
r TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION. UNIT ONE SUPPLDIENTAL INFORMATION FOR LER NP-33-80-106 PAGE 2 Failure Data: There ' ave been no previous failures of this type.
LER #80-078 i
t i
2
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000346/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000346/LER-1980-001-01, /01T-0:on 800103,during Plant Heatup,Safety Features Actuation Sys Channels 1 & 3 Tripped at 1,600 Psig, Causing Level 2 Actuation.Operators Correctly Tripped Reactor Coolant Pumps.Caused by Procedural Deficiency | /01T-0:on 800103,during Plant Heatup,Safety Features Actuation Sys Channels 1 & 3 Tripped at 1,600 Psig, Causing Level 2 Actuation.Operators Correctly Tripped Reactor Coolant Pumps.Caused by Procedural Deficiency | | | 05000346/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000346/LER-1980-002-03, /03L-0:on 800103,after Actuating of Safety Features Actuation Sys Level 2,demin Water Valve DW68318 Did Not Indicate Closed & Monitor Light Did Not Indicate Properly.Caused by Maladjusted Position Indicator Switch | /03L-0:on 800103,after Actuating of Safety Features Actuation Sys Level 2,demin Water Valve DW68318 Did Not Indicate Closed & Monitor Light Did Not Indicate Properly.Caused by Maladjusted Position Indicator Switch | | | 05000346/LER-1980-003-03, /03L-0:on 800103,during Auxiliary Feedwater Pump Test,Pump l-1 Was Declared Inoperable.Caused by Improperly Adjusted Slip Clutch Between Governor Manual Speed Adjustment Shaft & Remotely Controlled Speed Changer Motion | /03L-0:on 800103,during Auxiliary Feedwater Pump Test,Pump l-1 Was Declared Inoperable.Caused by Improperly Adjusted Slip Clutch Between Governor Manual Speed Adjustment Shaft & Remotely Controlled Speed Changer Motion | | | 05000346/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000346/LER-1980-004-03, /03L-0:on 800107,control Rod 5-11 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals.Possibly Caused by Isolation of Position Indication Cabling & Electrical Penetration | /03L-0:on 800107,control Rod 5-11 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals.Possibly Caused by Isolation of Position Indication Cabling & Electrical Penetration | | | 05000346/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000346/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000346/LER-1980-005-03, /03L-0:on 800110,Tech Spec Late Date Passed W/O Performance of Boric Acid Flowpath Heat Tracing Weekly Test. Caused by Known Deficiency in Design of Sys Resulting in Inability to Maintain Min Temp Necessary During Startup | /03L-0:on 800110,Tech Spec Late Date Passed W/O Performance of Boric Acid Flowpath Heat Tracing Weekly Test. Caused by Known Deficiency in Design of Sys Resulting in Inability to Maintain Min Temp Necessary During Startup | | | 05000346/LER-1980-006-03, /03L-0:on 800112,found Fiberglass Insulation Stuffed Into Open Wall Ventilator Between Water Treatment Bldg & Svc Water Valve Room,Causing Fire Damper to Be Inoperable.Figerglass Removed | /03L-0:on 800112,found Fiberglass Insulation Stuffed Into Open Wall Ventilator Between Water Treatment Bldg & Svc Water Valve Room,Causing Fire Damper to Be Inoperable.Figerglass Removed | | | 05000346/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000346/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000346/LER-1980-007-03, /03L-0:on 800116,ref Position Verification for Group 5,rod 11,was Made 1-h & 40 Minutes Late.Caused by Operator Oversight Due to Lack of Adequate Reminder Sys. Multiple Timer Sys Will Prevent Recurrence | /03L-0:on 800116,ref Position Verification for Group 5,rod 11,was Made 1-h & 40 Minutes Late.Caused by Operator Oversight Due to Lack of Adequate Reminder Sys. Multiple Timer Sys Will Prevent Recurrence | | | 05000346/LER-1980-008-03, Gap Discovered in Wall Where Five two-inch Conduits Go from Electrical Penetration Room 2 to Cable room.Six-inch Gap Around Ventilation Duct Also Found.Caused by Improper Initial Installation | Gap Discovered in Wall Where Five two-inch Conduits Go from Electrical Penetration Room 2 to Cable room.Six-inch Gap Around Ventilation Duct Also Found.Caused by Improper Initial Installation | | | 05000346/LER-1980-008, Forwards Revised LER 80-008/03L-1 | Forwards Revised LER 80-008/03L-1 | | | 05000346/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000346/LER-1980-009-03, /03L-0:on 800122,discovered That NI-7 Indication on Computer Group 38 Was Reading Less than Heat Balance Power,Putting NI-7 Below Instrumentation Operability Limit Line.Caused by Extremely Tight Calibr Band at 100% Power | /03L-0:on 800122,discovered That NI-7 Indication on Computer Group 38 Was Reading Less than Heat Balance Power,Putting NI-7 Below Instrumentation Operability Limit Line.Caused by Extremely Tight Calibr Band at 100% Power | | | 05000346/LER-1980-010-01, /01T-0:on 800214,reanalysis of RCS Pipe Restraints Per IE Insp Rept 50-346/79-23 Revealed Design Deficiency on Two Reactor Coolant Hot Leg Pipe Whip Restraints at Top of Each RCS Hot Leg.Caused by Design Error | /01T-0:on 800214,reanalysis of RCS Pipe Restraints Per IE Insp Rept 50-346/79-23 Revealed Design Deficiency on Two Reactor Coolant Hot Leg Pipe Whip Restraints at Top of Each RCS Hot Leg.Caused by Design Error | | | 05000346/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000346/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000346/LER-1980-011-03, /03L-0:on 800131,during Normal Operation, Operations Personnel Received Half Trip on Steam & Feedwater Rupture Control Sys Channels 1/3.Caused by Spurious Trip from +25 Volt Dc Power Supply PS03 in Sglic Channel 1 | /03L-0:on 800131,during Normal Operation, Operations Personnel Received Half Trip on Steam & Feedwater Rupture Control Sys Channels 1/3.Caused by Spurious Trip from +25 Volt Dc Power Supply PS03 in Sglic Channel 1 | | | 05000346/LER-1980-012-03, /03L-0:on 800201,operator Noticed Loss of Control Room Position Indication for Letdown Cooler Isolation Valve MU2A.Caused by Design Deficiency.Apparently,Someone Brushed Up Against Disconnect Breaker Switch.Switch Reposition | /03L-0:on 800201,operator Noticed Loss of Control Room Position Indication for Letdown Cooler Isolation Valve MU2A.Caused by Design Deficiency.Apparently,Someone Brushed Up Against Disconnect Breaker Switch.Switch Repositioned | | | 05000346/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000346/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000346/LER-1980-013-03, /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel | /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel | | | 05000346/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000346/LER-1980-014-03, /03L-0:on 800208,pressurizer Sample Sys Containment Isolation Valve RC240B Failed to Close Twice. Caused by Improper Torque Switch Setting & Stripped Screw on Closing Contactor.Settings Readjusted & Switch Replaced | /03L-0:on 800208,pressurizer Sample Sys Containment Isolation Valve RC240B Failed to Close Twice. Caused by Improper Torque Switch Setting & Stripped Screw on Closing Contactor.Settings Readjusted & Switch Replaced | | | 05000346/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000346/LER-1980-015-03, /03L-0:on 800210,during Normal Startup,Control Rod 5-11 Absolute Position Indication Declared Inoperable.Caused by Numerous Asymmetric Rod Alarms.Data from Current Failure Evaluated | /03L-0:on 800210,during Normal Startup,Control Rod 5-11 Absolute Position Indication Declared Inoperable.Caused by Numerous Asymmetric Rod Alarms.Data from Current Failure Evaluated | | | 05000346/LER-1980-016, Forwards LER 80-016/03L-0 | Forwards LER 80-016/03L-0 | | | 05000346/LER-1980-016-03, /03L-0:on 800213,while Reviewing Station Log,Shift Foreman Discovered That Containment Airlock Seal Leakage Test Had Not Been Performed After Last Entry Into Containment During Startup.Caused by Procedural Inadequacy | /03L-0:on 800213,while Reviewing Station Log,Shift Foreman Discovered That Containment Airlock Seal Leakage Test Had Not Been Performed After Last Entry Into Containment During Startup.Caused by Procedural Inadequacy | | | 05000346/LER-1980-017-03, /03L-0:on 800217,operations Personnel Noted That Safety Features Actuation Sys Channel 3 Borated Water Storage Tank Level Indication Was Six Feet Higher than Other Meters.Caused by Freezing of Transmitter Sensing Line | /03L-0:on 800217,operations Personnel Noted That Safety Features Actuation Sys Channel 3 Borated Water Storage Tank Level Indication Was Six Feet Higher than Other Meters.Caused by Freezing of Transmitter Sensing Line | | | 05000346/LER-1980-017, Forwards LER 80-017/03L-0 | Forwards LER 80-017/03L-0 | | | 05000346/LER-1980-018-03, /03L-0:on 800226,safety Features Actuation Sys Channel 3 Borated Water Storatge Tank Level Indication Was Discovered Reading Four Feet Higher than Other Three Channels.Caused by Inadequate Design of Freeze Protection | /03L-0:on 800226,safety Features Actuation Sys Channel 3 Borated Water Storatge Tank Level Indication Was Discovered Reading Four Feet Higher than Other Three Channels.Caused by Inadequate Design of Freeze Protection | | | 05000346/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | | 05000346/LER-1980-019, Forwards LER 80-019/01T-0 | Forwards LER 80-019/01T-0 | | | 05000346/LER-1980-019-01, /01T-0:on 800325 Reactor Flux/Flow Trip Setpoints Were Not Verified to Be Properly Reset within 4-h of Manual Shutdown of Rcp.Caused by Attention Given to Feedwater Swings.Trip Setpoints Verified Later | /01T-0:on 800325 Reactor Flux/Flow Trip Setpoints Were Not Verified to Be Properly Reset within 4-h of Manual Shutdown of Rcp.Caused by Attention Given to Feedwater Swings.Trip Setpoints Verified Later | | | 05000346/LER-1980-020, Forwards LER 80-020/03L-0 | Forwards LER 80-020/03L-0 | | | 05000346/LER-1980-020-03, /03L-0:on 800306,control Operator Noted No Control Room Indication for Containment Vacuum Relief Isolation Valve CV5072.Caused by Breaker BE1139 Being Closed,Probably Resulting from Someone Bumping Into Breaker | /03L-0:on 800306,control Operator Noted No Control Room Indication for Containment Vacuum Relief Isolation Valve CV5072.Caused by Breaker BE1139 Being Closed,Probably Resulting from Someone Bumping Into Breaker | | | 05000346/LER-1980-021, Forwards LER 80-021/03L-0 | Forwards LER 80-021/03L-0 | | | 05000346/LER-1980-021-03, /03L-0:on 800313,during Diesel Fire Protection Pump Weekly Test,Pump Could Not Be Stopped W/Control Button. Once Stopped,Pump Could Not Be Started.Cause Not Determined by Scheme Check.Retrial of Pump Proved Successful | /03L-0:on 800313,during Diesel Fire Protection Pump Weekly Test,Pump Could Not Be Stopped W/Control Button. Once Stopped,Pump Could Not Be Started.Cause Not Determined by Scheme Check.Retrial of Pump Proved Successful | | | 05000346/LER-1980-022-03, /03L-0:on 800317,operations Personnel Noticed Loss of Control Room Indication for Containment Dihydrogen Analyzer 2 Discharge Line Valve CV5010E.Caused by Const Personnel Accidentally Opening Breaker | /03L-0:on 800317,operations Personnel Noticed Loss of Control Room Indication for Containment Dihydrogen Analyzer 2 Discharge Line Valve CV5010E.Caused by Const Personnel Accidentally Opening Breaker | | | 05000346/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000346/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000346/LER-1980-023-03, /03L-0:on 800327,discovered That Control Rod Groups 3 & 4 Were Moving in on Their Own.Group 3 Was 0% Withdrawn.Group 4 Was 90% Withdrawn.Caused by Component Failure.Component Replaced | /03L-0:on 800327,discovered That Control Rod Groups 3 & 4 Were Moving in on Their Own.Group 3 Was 0% Withdrawn.Group 4 Was 90% Withdrawn.Caused by Component Failure.Component Replaced | | | 05000346/LER-1980-024-03, /03L-0:on 800327,following Normally Initiated Reactor Trip,Auxiliary Feed Pump Turbine 1-2 Main Steam Isolation Valve MS-107 Closed.Cause Unknown.Further Investigation of Valve & Operator Will Be Pursued | /03L-0:on 800327,following Normally Initiated Reactor Trip,Auxiliary Feed Pump Turbine 1-2 Main Steam Isolation Valve MS-107 Closed.Cause Unknown.Further Investigation of Valve & Operator Will Be Pursued | | | 05000346/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000346/LER-1980-025-03, /03X-1:on 800330,control Rod Group 5,rod 11 Absolute Position Indication Declared Inoperable.Caused by Fluctuating Signals Resulting in Numerous Asymmetric Rod Alarms Due to Defective Reed Switch Assemblies | /03X-1:on 800330,control Rod Group 5,rod 11 Absolute Position Indication Declared Inoperable.Caused by Fluctuating Signals Resulting in Numerous Asymmetric Rod Alarms Due to Defective Reed Switch Assemblies | | | 05000346/LER-1980-025, Forwards LER 80-025/03X-1 | Forwards LER 80-025/03X-1 | |
|