LER-1980-070, /03L-0:on 800828,during Weekly Diesel Fuel Pump Test ST 5016.01,diesel Fuel Pump Failed to Start at Required 95 Psig.Caused by Broken Pressure Switch.Switch Repaired & Recalibrated |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3461980070R03 - NRC Website |
|
text
NT.C FORM 3G6 SPECIAL REPORT U. S. NUCLEAR REGULATORY CoMMISSloN ep, j
LICENSEE EVENT REPORT CONTROL BLOCK: l l
l l
l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
lo l t l l 0 l H l D l 'E l S l 1 l@l 0 l 0 l 0 l 0 l 0 l 0 l 0 l 0 l 0 l 0 l 0 l@l 4 l 1 l 1 l 1 l 1 l@l l
l@
7 8 9 LICENSEE CODE 14 lb LICENSE NUM8EH 25 26 LICENSE TYPE Jo
$ 7 CA T 58 COTT Iclil
,"7,,"c' lL l @ L. l0 l-l0 l3 l4 l 6 l@[ 0 l 8 l 2 l 8 l 8 l 0 @l110 l 0 l 3 l 8 l 0 l@
7 8
60 61 DOCKET NUMBER 68 6'J EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND FROBAOLE CONSEQUENCES h lol2j l (NP-33-80-78) On 8/28/80 during the weekly Diesel Fire Pump (DFP) Test, ST 5016.01, l
g l the DFP failed to start at the required pressure of 95 psig.
During tests in the l
ITT71 i following weeks, the problem recurred.
In the above cases, the pump would run but wasl g,3l l technically inoperable because it would not auto start at the required pressure. The l
- je l l station had entered the action statement of T.S. 3.7.9.1.
There was no danger to the l [TT71 1 Public or station personnel. The Electric Fire Pump was operable.
Because the prob- [
,3gg, l lem was not resolved in 7 days, this is being submitted as a Special Report.
l 7
8 9 80 DE CODE S SC E COMPONENT CODE SUSCOD'E S
E lIII) l Al Bl@ W@ l[ @ Q l Nl Sl Tl Rl Ul @ [Sj @ W @
T 8
9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LE R/RO EVENT YEAR R EPORT No.
CODE TYPE NO.
@,aE,Pg l218 l0 l l0 l7 l0 l l 0l 3[
lLl 8
u 22 23 24 26 27 28 29 30 31 32 KN AC O O6 NT E
D HOURS S8 T FOR b 8.
MA UF CTLRER LEjg[34XJg [Zjg [6Zjg l $l 0l $l Dl l Ylg l y lg' SUPPLIElA l g l Cl 7l 4l 2l g 33 33 3
3/
40 di 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS g l Af ter the first occurrence the cause was explained as a broken pressure switch.
Underl 1 MWO IC-606-80, the switch was repaired and recalibrated. The switch has been recali-I 1
p TTI I brated three additional times when the problem recurred each week up until 9/20/80.
Itl g l h2s successfully passed ST 5016.01 since then during the weekly tests. A maintenance l g l electrician will oversee the starting sequence of upcoming weekly tests to look for l
7 s 9 adverse conditions.
so SA S
% POWER oTHER STATUS IS O RY DISCOVERY DESCRIPTION d @ l0l0l0l@l NA l
l Bl@l Surveillance Test ST 5016.01 l
1 5
' AC'TIVITY CO$ TENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE [Zj @ (_Zj@l NA l
l NA l
1 6 rEnSONNEL ExPOSukES NUMGER TYPE
DESCRIPTION
@ l 0l 0l 0l @ l Zl @ l NA l
PERSONNE t iNau'RtES DESCRIPTION @
NUMBER T I 0l 0l Ol@l NA l
8 9 11 12 LOSS OF OR DAVAGE TO FACILITY TDPE
DESCRIPTION
, _}2] [_ Zj@l 1
NA l
d 9 io ISSUE ISCRt' TION
- l '1 Llij81 e
N^
l llll111111llli S 010070[c%;iar
'o
- 5 frR 80-144, lh fSEPARER R
Frohne 419-259-5000, Ext. 794
{
PHONE:
SPECIAL REPORT TOLEDO EDISON COMPANY
' DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-78 DATE OF EVENT: August 28, 1980 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:
Diesel Fire Pump would not start at required pressure Conditions Prior to Occurrence: The unit was in Mode 5 with Power (MWT) = 0 and Load (Gross MWE) = 0.
Description of Occurrence: On August 28, 1980 at OC;$ Tours during the performance of the Diesel Fire Protection System Pump Weekly Test, ST 5016.01, the Diesel Fire Pump failed to start at the proper fire water header pressur'. The required decreasing e
starting pressure is 95 psig but the pump did not start until the pressure had dropped to 64 psig.
A check of the pressure switch revealed that it was broken. The pump was declared inoperable. The station had entered the action statement of Technical Speci-fication 3.7.9.1.
This requires two high pressure pumps to be operable in all modes.
Action Statement (a) requires the pump to be restored to operable status within 7 days or in lieu of any other report required by Technical Specification 6.9.1, submit a Special Report within the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy la this,sytem. This is not a mode restraint.
Hewever, on September 4, 1980 at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />, during the next weekly run of ST 5016.01, the same problem was encountered. This. time the Diesel Fire Pump did not start until the pressure had dropped to 85 psig. The diesel was placed in standby but was tzchnically inoperable due to the problem with the starting pressure.
Again on September 18, 1980 the pump would not start until the pressure had dropped to 90 psig.
It was placed in standby.
In all of the above cases the Diesel Fire Pump could be operated but was inoperable because it would not auto start at 95 psig.
Breause the problem was not corrected in the first seven days, these events are being submitted as a Special Report per Tec'anical Specification 6.9.2.
Designation of Apparent Cause of Occurrence: The failure to start at the required pres-cure in the first event appeared to be due to a damaged pressure switch which had been accidentally bumped.
Ir as repaired and recalibrated. However, when the problem repeated it was apparent there was more involved.
The switch has since been recalibrated three additional times and the problem recurred u, until September 20, 1980.
Investiga-tion is continuing to find the sources of the problem.
Corrective Ac; ton: Under Maintenance Work Order IC-606-80 the first event was corrected by replacing c broken glass and recalibration of the pressure switch.
ST 5016.01 was successfully performed on August 30, 1980. The diesel fire pump was declared operable.
LER #80-070
SPECIAL REPORT TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE PAGE 2 SUPPLEMENTAL > INFORMATION FOR LER NP-33-80-78 When the problem recurred during the next weekly test run, Maintenance Work Order IC-615-80 was issued and again the pressure switch was recalibrated. On September 13, 1980 under Maintenance Work Order 80-3196, a problem in the starting relay was corrected by replacing the AC2 coil.
ST 5016.01 was again successfully performed, and the Diesel Fire Pump was declared operable. When the problem recurred on September 18, 1980, the switch was again recalibrated. On September 20, 1980,. the Diesel Fire Pump was declared operable.
A maintenance electrician will accompany the operator for the upcoming weekly surveil-lance tests on the Diesel Fire Pump to oversee the starting sequence and look for any cdverse conditions.
Failure Data: Previous failures of the Diesel Fire Pump were reported in Lt.censee Event Reports NP-33-78-52 (78-042), NP-33-78-68 (78-034), and NP-33-80-30 (30-021).
LER #80-070 1
e 1
\\
|
|---|
|
|
| | | 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 | |
|