LER-1978-082, /03L-0:on 780722,surveillance Testing on Personnel Airlock Not Performed within Required 72-h.Caused by Procedure Scheduling Deficiency.Test Not Adaptable to 7-day Schedule.Airlock Tested as Required |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3461978082R03 - NRC Website |
|
text
_ _. - _ _ _ _ _ _
U. S. NUCLEAM M3uuu*a un a w.
RC FORM 366O
.d
~ s LICENSEE EVENT REPORT
'77)
~
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI NTROL ELOCX: l l
l l
l l
lh 6
l1 l1 l1 l1 l@l l
l@
1 lS l1 l@l O l O I -l 0 l 0 l N ! P l F l-l 013 l@l4 lH ID lB
.S 26 uCENSE TYPE 40
$7 CAT 66 2
UCENSE NUMSER 8
9.
UCENSEE CooE to 13 0 l8 Il I5 17 l8 l@
3l11 Eu',"T l L@] 0] 5 l 0 { - l 0 { 3 l 4 l 6 @l 0 l 7 l 2 l 2 I 7 ) 8 @75
- cN T 74 REPORT oATE 40 68 69 EVENT oATE 60 El CoCKET NuMSER EVENT OESCRIPTION AND PROBABLE CONSEQUENCES h 3
1 a t a l 1 On 7/22/78, the Shif t Foreman found no enerv or evidence of a surveillance test eer-Technical Soecification Surveillance f
formed on the personnel airlock since 7/16/78.
o i31 I d everv 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> whenever i
, o g 41 [ Requirement 4.6.1.3a requires the personnel airlock be teste There was no danger to the health and safety of the public or oisj i the airlock is in use.
The integrity of the personnel airlock was verified before and after i
, o is J l unit personnel.
Therefore, the integrity of containment was
[
lo ! 71 I the occurrence by surveillance testing.
l (NP-33-78-98) fa6aI i not violated during this period.
80 SUS E
COMPONENT CooE Su8 Code Su E
7 8 9 S-l Al@ l D l@ l Z l@ l Pl El Nl El Tl R l@ W@ y @
Co to_ts.)
i 13 19 20 7
8 9
to it 12 13 REVt51oN OCCURRENCE REPORT CCoE TYPE No.
SEQUENTIAL p/@,at;o,g 17 18 I l-l I 0181 21 W
1013I I LI l-l O
REPcRT No.
EVENT YEAR LER/Ro 21 22 23 24 25 27 28 29 30 31 32
- 'u'a5*S$#
Pc" US0s.
'"s'u"c'P$ E ['
uEOu"[2CEIER u
T N TCYod oUt NT
""SEE" wouRs 22 l G [ g g g l34Z lg gg l1 0l 0l 0l l
l Y lg l42 Nlg l43A [g lC l3 l1 l0 lg s
M 44 47 36 3
40 di CAUSE OESCRIPTlON ANO CORRECTIVE ACTIONS @
33 34 l~i ) o l l The cause of the occurrence can be attributed to procedure scheduling de listed. l l test is not adaptable to the 7 day surveillance test schedule on which it was l: 13j
/
l l The test was performed and the personnel airlock was declared operable on
,,,2j The surveillance test was removed from the surveillance test sch g,,3l [ 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />.
is perfor=ed when required.
I l placed on the Monthly Log Sheet to assure the test 80 ti i4 i 7
8 9 otsCovERY oESCRIPTToN l
h POWER oTHER STATUS at Y
l l Cl@l Shif t Foreman review of log l t i s l y@ l 0l 0 l 0 l@l NA ao 44 4s as LoCAT1oNo,REuASE@
iz is 84 ig,
.Meuuf o,,cTiv,Tv @ l 7
l
.EuAsto e, aEuisE l NA ITA l_ zl @ l zi@l NA
' ' nRsoNNd Ex,osSEs eEsCR,:.oN (sy I
NuM.ER Tvn fiTTI Io I o 10 l@l zl@l NA PER5oNNEL INJURIES l
NUMBER CE5CRtPT1oN iA]-l01010l@l NA h
910 e[r v LCSS or CR C ace o PACIUTY
(
l TYPE DISCRIPUoM
' ' " ~1 nn4 li 191 i z l@l NA m
80
- ) V e
7 4 9 10 issut E CRIPT1oM i
i i i i !
! i r i i i !!
- - rrrri iN f@i NA 40 ;
68 69 a
P 8 9 to m y999y
I w
TOLEDO EDISON CCEPANY s
DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMLWAL INFORMATION FOR LER NP-33-78-98_
i t
DATE OF EVENT _: July 22, 1978 1
~
FACILITY: Davis-Besse Unit 1 1
l Failure to perform surveillance testing on the per-1 IDENTIFICATION OF OCCURRENCE:
sonnel airlock within the required 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> The unit was in Mode 3, with Power (MWT) = 0, Conditions Prior to Occurrence:
and Load (MWE) = 0.
While reviewing the Unit Log on July 22, 1978 at 1105 5
hours, the Shif t Foreman found no entry or evidence of Surveillance Test ST 50 Description of Occurrence:
" Containment Airlock Seal Leakage Test" being performed on the personnel airloc To remain within Technical Specification since July 16, 1978 at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />.
4.6.1.3a, the personnel airlock must be tested within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> af ter opening or b The Shif t Foreman declared the personnel airlock inoperable i d surveillance
\\ declared inoperable.
jand directed Instrument and Control personnel to perform the requ re i
tesc.
The cause of the occurrence can be Designation of Apparent Cause of Occurrence:
The surveillance test schedule attributed to procedure scheduling deficiency.23,1978 at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> outsi e t d
he 72 stated that the test was not due until July This surveillance test is to be hour limit of Technical Specification 4.6.1.3t.
is performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> whenever the airlock is in use; therefore, this test not adaptable to the 7 day surveillance test schedule.
There was no danger to the health and safety of the public Analysis of Occurrence:The integrity of the personnel airlock was verified before 5061.05. Therefore, the integrity or to unit personnel.
and af ter the occurrence by Surveillance Test ST of containment was not violated during this period.
Surveillance Test ST 5061.05 was performed at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on The unit then
Corrective Action
and the personnel airlock was declared operable.
satisfied Surveillance Requirement 4.6.1.3a and was removed from the action state-July 22, 1978, The surveillance test was removed from ment of Technical Specification 3.6.1.3.
the the surveillance test schedule and placed on the Monthly Log-Sheet to-assure test is performed when required.
On July 6,1978, the emergency air lock was not shown to be opera-
)
Failure Data:
Event
%j tional within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the airlock had been opened (see Licensee In this case, only one door was tested hy the surveillance Report NP-33-77-15).
test.-
LER #78-082
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000346/LER-1978-002-03, /03L-0:on 780103,control Rod Group 5 Rod 12 Absolute Position Indication Declared Inoperable.Caused by Component Failure of Absolute Position Indicator Reed Switch.Switch Replaced | /03L-0:on 780103,control Rod Group 5 Rod 12 Absolute Position Indication Declared Inoperable.Caused by Component Failure of Absolute Position Indicator Reed Switch.Switch Replaced | | | 05000346/LER-1978-002, Forwards LER 78-002/03L-0 | Forwards LER 78-002/03L-0 | | | 05000346/LER-1978-003-03, /03L-0:on 780103,unidentified RCS Leakage Greater than 1,66 Gallon Per Minute.Caused by Loose Packing on Valve DH2735.Valve Repacked & Stroked | /03L-0:on 780103,unidentified RCS Leakage Greater than 1,66 Gallon Per Minute.Caused by Loose Packing on Valve DH2735.Valve Repacked & Stroked | | | 05000346/LER-1978-003, Forwards LER 78-003/03L-0 | Forwards LER 78-003/03L-0 | | | 05000346/LER-1978-004, Forwards LER 78-004/03L-0 | Forwards LER 78-004/03L-0 | | | 05000346/LER-1978-004-03, /03L-0:on 780105,inlet Balancing Dampers to Emergency Ventilation Sys Fans 1-1 & 1-2 Found Closed.Cause Unknown.Dampers Returned to Balance Position & Locknut Tightened | /03L-0:on 780105,inlet Balancing Dampers to Emergency Ventilation Sys Fans 1-1 & 1-2 Found Closed.Cause Unknown.Dampers Returned to Balance Position & Locknut Tightened | | | 05000346/LER-1978-005-03, /03L-0:on 780106,auxiliary Feed Pump Turbine 1-1 Speed Control Lost & Declared Inoperable.Caused by Short Circuits & Blown Fuses Due to Design Deficiency.Higher Current Rated Relays Installed & Circuit Modified | /03L-0:on 780106,auxiliary Feed Pump Turbine 1-1 Speed Control Lost & Declared Inoperable.Caused by Short Circuits & Blown Fuses Due to Design Deficiency.Higher Current Rated Relays Installed & Circuit Modified | | | 05000346/LER-1978-005, Forwards LER 78-005/03L-0 | Forwards LER 78-005/03L-0 | | | 05000346/LER-1978-006-03, /03L-0:on 780107,computer Alarm Indicated That Steam & Feedwater Rupture Control Sys Steam Generator to Feedwater Differential Pressure Channel 1 Had Tripped.Caused by Component Failure.Input Buffer 1-3 in Channel 1 Replaced | /03L-0:on 780107,computer Alarm Indicated That Steam & Feedwater Rupture Control Sys Steam Generator to Feedwater Differential Pressure Channel 1 Had Tripped.Caused by Component Failure.Input Buffer 1-3 in Channel 1 Replaced | | | 05000346/LER-1978-006, Forwards LER 78-006/03L-0 | Forwards LER 78-006/03L-0 | | | 05000346/LER-1978-007-03, /03L-0:on 780109,during Monthly Surveillance Test ST 5081.01,diesel Generator 1-1 Tripped on High Crankcase Pressure.Caused by Dirty Crankcase Vent Oil Collector.Vent Oil Collector Disassembled & Cleaned | /03L-0:on 780109,during Monthly Surveillance Test ST 5081.01,diesel Generator 1-1 Tripped on High Crankcase Pressure.Caused by Dirty Crankcase Vent Oil Collector.Vent Oil Collector Disassembled & Cleaned | | | 05000346/LER-1978-007, Forwards LER 78-007/03L-0 | Forwards LER 78-007/03L-0 | | | 05000346/LER-1978-008-03, /03L-0:on 780112,both Containment Spray Pumps Found Inoperable.Caused by Personnel Error.Spray Pump Circuit Breakers re-energized | /03L-0:on 780112,both Containment Spray Pumps Found Inoperable.Caused by Personnel Error.Spray Pump Circuit Breakers re-energized | | | 05000346/LER-1978-008, Forwards LER 78-008/03L-0 | Forwards LER 78-008/03L-0 | | | 05000346/LER-1978-009-03, /03L-0:on 780112,component Cooling Water Heat Exchanger 1-1 Outlet Isolation Valve SW 1424 Declared Inoperable.Caused by Component Failure.Solenoid Valve in Control Scheme Found Burned Out.Unit Removed | /03L-0:on 780112,component Cooling Water Heat Exchanger 1-1 Outlet Isolation Valve SW 1424 Declared Inoperable.Caused by Component Failure.Solenoid Valve in Control Scheme Found Burned Out.Unit Removed | | | 05000346/LER-1978-009, Forwards LER 78-009/03L-0 | Forwards LER 78-009/03L-0 | | | 05000346/LER-1978-010-03, /03L-0:on 780115, Reactor Coolant Pump Monitor on Channel 1 Found Out of Tolerance & Reactor Protection Sys Declared Inoperable.Caused by Defective Module.New Module Calibr & Installed | /03L-0:on 780115, Reactor Coolant Pump Monitor on Channel 1 Found Out of Tolerance & Reactor Protection Sys Declared Inoperable.Caused by Defective Module.New Module Calibr & Installed | | | 05000346/LER-1978-010, Forwards LER 78-010/O3L-0 | Forwards LER 78-010/O3L-0 | | | 05000346/LER-1978-011, Forwards LER 78-011/03L-0 | Forwards LER 78-011/03L-0 | | | 05000346/LER-1978-011-03, /03L-0:on 780116,during Surveillance Test,Decay Heat Pump 1-1 Failed to Start.Caused by Fuses in Breaker for Decay Heat Motor Failing to Make Proper Contact.Control Power Fuese Pulled & Reinserted.Pump Returned to Svc | /03L-0:on 780116,during Surveillance Test,Decay Heat Pump 1-1 Failed to Start.Caused by Fuses in Breaker for Decay Heat Motor Failing to Make Proper Contact.Control Power Fuese Pulled & Reinserted.Pump Returned to Svc | | | 05000346/LER-1978-012, Forwards LER 78-012/03L-0 | Forwards LER 78-012/03L-0 | | | 05000346/LER-1978-012-03, /03L-0:on 780124,personnel Airlock Failed Leak Rate Test.Caused by Loose Shaft Seal Due to Routine Use of Personnel & Escape Lock (Exit/Entry to Containment).Shaft Seals Tightened to Prevent Excessive Leakage | /03L-0:on 780124,personnel Airlock Failed Leak Rate Test.Caused by Loose Shaft Seal Due to Routine Use of Personnel & Escape Lock (Exit/Entry to Containment).Shaft Seals Tightened to Prevent Excessive Leakage | | | 05000346/LER-1978-013-03, /03L-0:780119,Cell 32 in Station Battery 1N Electrolyte Specific Gravity Decreased 0.003 Greater than Allowed by Tech Spec 3.8.2.3.Caused by Electrolyte Stratification Due to Low Battery Loading | /03L-0:780119,Cell 32 in Station Battery 1N Electrolyte Specific Gravity Decreased 0.003 Greater than Allowed by Tech Spec 3.8.2.3.Caused by Electrolyte Stratification Due to Low Battery Loading | | | 05000346/LER-1978-013, Forwards LER 78-013/03L-0 | Forwards LER 78-013/03L-0 | | | 05000346/LER-1978-014, Forwards LER 78-014/03L-0 | Forwards LER 78-014/03L-0 | | | 05000346/LER-1978-014-03, /03L-0:on 780123,quandrant Power Tilt in Excess of Steady State & Transient Limits Indicated by Unit Process Computer.Caused by Detector Inadvertently Left Off Scan After Testing.Test Procedure Being Modified | /03L-0:on 780123,quandrant Power Tilt in Excess of Steady State & Transient Limits Indicated by Unit Process Computer.Caused by Detector Inadvertently Left Off Scan After Testing.Test Procedure Being Modified | | | 05000346/LER-1978-015, Forwards LER 78-015/03L-0 | Forwards LER 78-015/03L-0 | | | 05000346/LER-1978-015-03, /03L-0:on 780131,feedwater Steam Generator 1 Channel 2 Pressure Differential Switch Did Not Actuate at Desired Setpoint During Surveillance Test.Caused by Pressure Differential Switch Out of Tolerance | /03L-0:on 780131,feedwater Steam Generator 1 Channel 2 Pressure Differential Switch Did Not Actuate at Desired Setpoint During Surveillance Test.Caused by Pressure Differential Switch Out of Tolerance | | | 05000346/LER-1978-016-03, /03L-1:on 780202,absolute Position Indicator for Group 5,Rod 12,declared Inoperable.Caused by Component Failure in Penetration Area.Containment Conductors Connected to Spare Penetration Connector | /03L-1:on 780202,absolute Position Indicator for Group 5,Rod 12,declared Inoperable.Caused by Component Failure in Penetration Area.Containment Conductors Connected to Spare Penetration Connector | | | 05000346/LER-1978-016, Forwards LER 78-016/03L-1,LER 78-021/03L-1,LER 78-100/03L-1, LER 78-034-03L-1 & LER 78-024/03L-1 | Forwards LER 78-016/03L-1,LER 78-021/03L-1,LER 78-100/03L-1, LER 78-034-03L-1 & LER 78-024/03L-1 | | | 05000346/LER-1978-017, Forwards LER 78-017/03L-0 | Forwards LER 78-017/03L-0 | | | 05000346/LER-1978-017-03, /03L-0:on 780126,all Meteorological Channels Became Inoperable During Blizzard.Caused by Instrumentation Power Loss Due to Tripped Breaker at Meteorological Tower. Breaker Reset on 780128 | /03L-0:on 780126,all Meteorological Channels Became Inoperable During Blizzard.Caused by Instrumentation Power Loss Due to Tripped Breaker at Meteorological Tower. Breaker Reset on 780128 | | | 05000346/LER-1978-018-03, /03L-0:on 780208,diesel Generator 1-1 Making Unusual Noises During Monthly Test.Unusual Noise Traced to Turbocharger.Exact Cause Undetermined.Turbocharger Replaced & Diesel Generator Monthly Test Completed | /03L-0:on 780208,diesel Generator 1-1 Making Unusual Noises During Monthly Test.Unusual Noise Traced to Turbocharger.Exact Cause Undetermined.Turbocharger Replaced & Diesel Generator Monthly Test Completed | | | 05000346/LER-1978-018, Forwards LER 78-018/03L-0 | Forwards LER 78-018/03L-0 | | | 05000346/LER-1978-019-03, /03L-1:on 780210,decay Heat Cooler Outlet Valve DH14A & DH14B Mechanical Stops Found Incorrectly Opened. Caused by Personnel Incorrectly Resetting Stops After Previous Work Completion.Stops Tagged & Records Marked | /03L-1:on 780210,decay Heat Cooler Outlet Valve DH14A & DH14B Mechanical Stops Found Incorrectly Opened. Caused by Personnel Incorrectly Resetting Stops After Previous Work Completion.Stops Tagged & Records Marked | | | 05000346/LER-1978-020, Forwards LER 78-020/03L-0 | Forwards LER 78-020/03L-0 | | | 05000346/LER-1978-020-03, /03L-0:on 780210,reactor Protection Sys Channel 3 Hot Leg Temp String TI-RC3B4 Declared Inoperable.Caused by Loose Wire Connection.Loose Terminal at Temp Element Tightened,Rendering TI-RC3B4 Operable | /03L-0:on 780210,reactor Protection Sys Channel 3 Hot Leg Temp String TI-RC3B4 Declared Inoperable.Caused by Loose Wire Connection.Loose Terminal at Temp Element Tightened,Rendering TI-RC3B4 Operable | | | 05000346/LER-1978-021-03, /03L-1:on 780220,absolute Position Indicator for Control Rod 12 of Group 5 Declared Inoperable.Caused by Component Failure in Penetration Area.Conductors Connected W/Spare Penetration Connectors | /03L-1:on 780220,absolute Position Indicator for Control Rod 12 of Group 5 Declared Inoperable.Caused by Component Failure in Penetration Area.Conductors Connected W/Spare Penetration Connectors | | | 05000346/LER-1978-022-03, /03L-0:on 780223,flow Transmitter FTRC1A3 Found Inoperable.Caused by Defective Flow Transmitter Amplifier. Amplifier Replaced & Flow Transmitter FTRC1A3 Returned to Svc on 780226 | /03L-0:on 780223,flow Transmitter FTRC1A3 Found Inoperable.Caused by Defective Flow Transmitter Amplifier. Amplifier Replaced & Flow Transmitter FTRC1A3 Returned to Svc on 780226 | | | 05000346/LER-1978-022, Forwards LER 78-022/03L-0 | Forwards LER 78-022/03L-0 | | | 05000346/LER-1978-023-03, /03L-0:on 780224,temp Indication for Reactor Protection Sys Channel 2 Spiked Tripping Channel & Shut Down Reactor.Caused by Faulty Connector Due to Dirt on Contacts. Channel 2 Temp String Modules Removed & Connectors Cleaned | /03L-0:on 780224,temp Indication for Reactor Protection Sys Channel 2 Spiked Tripping Channel & Shut Down Reactor.Caused by Faulty Connector Due to Dirt on Contacts. Channel 2 Temp String Modules Removed & Connectors Cleaned | | | 05000346/LER-1978-023, Forwards LER 78-023/03L-0 | Forwards LER 78-023/03L-0 | | | 05000346/LER-1978-024-03, /03L-1:on 780228,MSIV MS-101 Rendered Inoperable to Allow Maint Personnel to Remove Raised Metal on Two of Four Spring Guide Tubes.Cause of Raised Metal Unknown.Metal Filed Down,Valve Closing Time Adjusted & Valve Tested | /03L-1:on 780228,MSIV MS-101 Rendered Inoperable to Allow Maint Personnel to Remove Raised Metal on Two of Four Spring Guide Tubes.Cause of Raised Metal Unknown.Metal Filed Down,Valve Closing Time Adjusted & Valve Tested | | | 05000346/LER-1978-025-03, /03L-0:on 780304,RCS Leakage Found Greater than 1 Gallon Per Minute.Leakage Cause Undetermined.Leakages Processed Through Normal Containment Sump.Unidentified RCS Leakage Reduced Below 1 Gallon Per Minute in 5.5-h | /03L-0:on 780304,RCS Leakage Found Greater than 1 Gallon Per Minute.Leakage Cause Undetermined.Leakages Processed Through Normal Containment Sump.Unidentified RCS Leakage Reduced Below 1 Gallon Per Minute in 5.5-h | | | 05000346/LER-1978-025, Forwards LER 78-025/03L-0 | Forwards LER 78-025/03L-0 | | | 05000346/LER-1978-026, Forwards LER 78-026/03L-0 | Forwards LER 78-026/03L-0 | | | 05000346/LER-1978-026-03, /03L-0:on 780309,radiation Monitor Re 5029 Found Inoperable Due to Low Sample flow.12 Previous Radiation Monitor Inoperabilities Not Reported.Caused by Pump Motor Bearing Seizure Due to High Ambient Temp | /03L-0:on 780309,radiation Monitor Re 5029 Found Inoperable Due to Low Sample flow.12 Previous Radiation Monitor Inoperabilities Not Reported.Caused by Pump Motor Bearing Seizure Due to High Ambient Temp | | | 05000346/LER-1978-027, Forwards LER 78-027/03L-0 | Forwards LER 78-027/03L-0 | | | 05000346/LER-1978-027-03, /03L-0:on 780316,stop Valve AF3870 Failed to Open During Testing.Caused by High Differential Pressure Due to Check Valve AF39 & AF72 Leakage.Motor Operator Initially Not Adjusted for This Pressure,Causing Operator to Torque | /03L-0:on 780316,stop Valve AF3870 Failed to Open During Testing.Caused by High Differential Pressure Due to Check Valve AF39 & AF72 Leakage.Motor Operator Initially Not Adjusted for This Pressure,Causing Operator to Torque Out | | | 05000346/LER-1978-028-03, /03L-0:on 780318,channel 1 Steam Generator 1-1 Declared Inoperable.Caused by Water in Level Transmitter SP09B8 Connecting Box Due to Steam Leak.Connection Box Cleaned & Dried.Waterproof Fitting Will Be Installed | /03L-0:on 780318,channel 1 Steam Generator 1-1 Declared Inoperable.Caused by Water in Level Transmitter SP09B8 Connecting Box Due to Steam Leak.Connection Box Cleaned & Dried.Waterproof Fitting Will Be Installed | |
|