LER-1977-090, /03L-0:on 771107,during Review of Deficiency in Steam & Feedwater Rupture Control Sys Monthly Test,Reactor Coolant Pump Found Inoperable.Caused by Component Failure. Voltage Regulating Diode Replaced |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3461977090R03 - NRC Website |
|
text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
U.S. NUCLEAR REGULATORY COMMISSION
+
NRC F!RM 366 (7 77r LICENSEE EVENT REPORT
,,..e
' CONTROL BLOCK: l l
l l
I l lh QLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONF 1
d l 0l Hj Dl B l Sl 1l@l 0 l 0 l -l 0 l 0 l N l P l F l - l 0 l 3 l@l 4 l 1 l 111l 1l@]
l l@
7 8 9 LICENSEE CODE 14 15 uCENSE NUMBEH 25 26 LICENSE TYPE JG
$1 CAF $$
CCN'T lol11 Eu g l L yg)[ 0l5l0]-l0l3l4l6 Ql1 l1 I0]7!7!7l@l1l2l01117l7j@
7 8
60
' 61 CCJKET *.JMSER 6d 69 EVENT DATE 7 4'-
75 REPORT DATE 60
EVENT DESCRIPTION
AND P_ ROB ABLE CONSEQUENCES h in the SFRCS
[
I o 8 2 I I At 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> on November 7, 1977, during a review of a deficiency m m 101311 Mon hiv Tes't. aoNblemaffectingthe~RPSwasfound. One of the four RCP monitors
- - l RPS E "5T"T4 frc$%di-VW2--2'T-gocreo RPR. Channel. 21 was _ determined to be_. inoperable.
l
'I o I si F-channel -vas-declaredcinneerabia and tripped which placed. the statiott in Action _
[.
3' oflechnica1 Soecific'attorr 3.Y.l.1.- The redundant.aPS channels, wouid _.
I I o is i I statement 10171 l have Iicifea reXctor coddr if an overcurrent trip had occurred.
012-33-77-90) l
-, o ;g p g
... c:.:..
7 8 9
. CAUSE COMP.
VALV E Sv$7EM CAUJE CCDE -
COOE SUSCCDE -
CCMPONENT CODE SUSCODE SUSCOQE
~ ~ ' '
I I l A l @ l Elh~ ~. l A l @. l I l N ] S l T l R j U [g 'j X l g ~~l Zj g '
- - loisl 7
8 9
10 11
~
- - 1 +
t9 20 D
SEQU ENTI AL CCCURRENCE
. REPORT REVIS!CN g Qg/RD
,, EVENT YEAR REPORT NO.
CODE
' TvPE
.l LEP 1 r i; 7 l ; ____1___l l 0 !_9-l 0 l.
ri-1 10l3!
..l Li l_;,
l 3
,, _ _.p ; -- 2 2 22 24 26
~ 27 IS 29
~ JG ' * * ~
31 ' - '
32 1 ACTION PUTURE EFFECT
- - St.VTCOWN
..ATT ACHM E N T - N P R O-4 PRIME COMP. -
COM80NENT MOURS SU6MITTED v fCRu bus.
. SUPPLIER VANU P ACTt; A E H ACTION CN PL.4NT
\\
f TAKEN
" W
.4. Al@l% l@,...l ZJ@w.l..Z I
[ 0.] O LO g@ _ l2Nlg
_ l6lcl3}0lQ 24
.s
.6 e
ai 4
as -
44 -
a 22 CAUSE DESCRIPTICN ANG CORR.ECTIVE ACTIONS h
~
- - A cur-rentz PCv voltage transducer ! _.,,_
^- r i t o.}.F Compore.5t_dati-aiel v'as; the -cause-of this occurrence.
,7
-- g. [ +r &
current eni+or. had. a.def ective_ voltage.iragulating. :ener-diede. Cn
~
- Noiem5ei'10, T977, Control Syster
- s personnel' replaced-the voltage-regulating :ener
~
I.
.-,, M l-l..d16de.
The cha'anel_ was. d.clared. operable at 1405 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.346025e-4 months <br />..on. November. 10, 1977. whic'a 1
.z.
,..a..
.-m. ; removed the station fros. Action Statement 3 of TS 3.3.Ll.
u.
% POWE R '~-
OTHER STATUS I
RV OISCOVERY QESCRIPTION e
ST
' 0t l
Oo NA-. _,...,
__j_ _l 3,g NA. -
l t-
{ -t-ACTIVITY.
CC TENT R ELE AS E D -
AMC'UNT OF AC'dVIIY
- - LOCATION 0F RELEASE g ' S4, } 2L.[g'op mELEASE I.
I
_I 2f4hl
- - NA-
^
l l NA l '
p.;/ ;,
y _.__
PERSONNEL EXPCSURES NUMBER TYPE OESCRIPTION l
I? Ibl M. _~. ~~g'.T
- _[ g-p l -[ A I O ! A 1
y y
7 8 9 11 12 O
Q h-O
' LI
~~'N
'h'#';
PERSONNE L INJURIES n.:
+g y
j b3 NUM8ER CESCmPTION l
.-H.g l 0 l o_LO_jgi m
_. = u.-
n a >
n LOSS OF CR OAuAGE TO 84CILITY fsof'54"i"' "
- - 8002040M")
i v;,
NRC USE CNLY y __.
oEsemcNhy PUS LICITY esuso I;
l ll IIl1iiI1 : 1
- - g.pLl@l m
NA sd u -
s., n--- -
,a [DVR,i454-1 --%,M en,,
~--T, Dave: Mi.tchell t,..;,4aygg 419-259-5000, Ext. 223 (
/
T TOLEDO EDIiON COMPANY h
DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION SUPPLEMENTAL INFORMATION FOR LER NP-33-77-90 DATE 0F EVENT: November 7, 1977 ACILITY: Davis-Besse Unit 1 IDENTIFkCATIONOF0CCURRENCE: -Inability of Reactor Protection System. (RPS). Channel -
' ~
. 2 to-recognize a locked rotor. (hig&L. current) condition. for. Reactor.-Coolant Pump,__.
(RCP) motor 2-2.
Conditions"FIior co Occurrenew-l The. unit -was, in Mode-2gi:th Power..(MWI) = 0 and
t
.a.
Load (MWE) = 0.
Desci:1 priori of'0Feurrence: Ar L340: hours-on November 7,1-972,..during a review of.
e
),
a deficiency ~in the Steam and: F7eeiiwEei.'tGipture Control Systam. ;(SFRCS) Monthly _,
,1,.
Test, ST 5031.14, a problem gffecting the RPS was found.
One of the four RCP m'onitors from RCF; motor 2-2 (-going.to RPS Channel 2) _was determined. to be..inopera j
..g-ble such char the RPS Channeiv2 would not-recognize a; locked rotor condition of.
- - the-2-2 pump motor. This -does. pat--affect the SFRCS since...it. ia concerned with loss of power to all four pump. motors, but does affect the-RPS.
The Technical Engineer was no.tified..and at 1335-hours, RPS Channel 2 was declared cinoperable and tripped which -placed the unit-in the Action;Stacament 3.of -Tech. -;;..
nical Specification (TS) 3.3.1,.l.
Designatiotr oF Apparent Causeiof Occurrence: Component failure was the cause of., -
~
this occurrence. A current ep;yoitage transducer if RCP. motor current monitor had a defective voltage regulating-zener diode.
i -
- -Analysis -of-Odedrrence: - Thergy--no -danger to.- the health ansi. safety.of the.public,.. --
or to station personnel. The redundant RPS channels would'have limited reactor.
power--if an overcurrent trip had -occurred.
Corrective Action
On November 10, 1977, the voltage-regulating sener diode was replaced. The transducer was reinstalled and the calibration was_ satisfactorily -
'chec'ked.MTST-5031.14;."SFRCS Monchly. Test",.was performed for RCP
- 2-23 RES J.hannel--/ 5 --
m-e 2 and a new _ response time check..was satisf actorily. perforced,. ~3-C m Tfie cha5 net %zs de51ared operable at 1405-hodrsr on Novembep40m117.7, which, removed.. :,
~
the station fr-om action Statetsent 3 of TS 3.3.1.1.-
1;.w-2.-
Failure-Dees: No previous failures of these transducers have occurred.
v
.e m
e m,
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000289/LER-1977-016-01, /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | | | 05000289/LER-1977-016, Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | | | 05000320/LER-1977-016, /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | | | 05000346/LER-1977-017, Forwards LER 77-017/01T-0 | Forwards LER 77-017/01T-0 | | | 05000346/LER-1977-017-01, /01T-0:on 771020,both Auxiliary Feed Pump Suctions Lined Up to Deaerator Storage Tanks W/O Cooling Water Supply Shifting to Svc Water,Resulting in Water Greater than 200 F as Cooling Water for Auxiliary Feed Pump Bearings | /01T-0:on 771020,both Auxiliary Feed Pump Suctions Lined Up to Deaerator Storage Tanks W/O Cooling Water Supply Shifting to Svc Water,Resulting in Water Greater than 200 F as Cooling Water for Auxiliary Feed Pump Bearings | | | 05000346/LER-1977-018, Forwards LER 77-018/01T-0 | Forwards LER 77-018/01T-0 | | | 05000346/LER-1977-018-01, /01T-0:on 771108,station Review Board Found Auxiliary Feed Pump Turbine Governor Valve Vibrational Closure Design Deficiency.Caused by Lack of Force to Hold Valve Open.Requests Design Mod for Pump Turbines | /01T-0:on 771108,station Review Board Found Auxiliary Feed Pump Turbine Governor Valve Vibrational Closure Design Deficiency.Caused by Lack of Force to Hold Valve Open.Requests Design Mod for Pump Turbines | | | 05000346/LER-1977-019-01, /01T-0:on 771117,auxiliary Feedwater Valves AF 599 & AF 608 Found Closed,Rendering Steam & Feedwater Rupture Control Sys Pressure Switch Inputs Inoperable.Caused by Procedural Deficiency.Tests Revised | /01T-0:on 771117,auxiliary Feedwater Valves AF 599 & AF 608 Found Closed,Rendering Steam & Feedwater Rupture Control Sys Pressure Switch Inputs Inoperable.Caused by Procedural Deficiency.Tests Revised | | | 05000346/LER-1977-019, Forwards LER 77-019/01T-0 | Forwards LER 77-019/01T-0 | | | 05000346/LER-1977-077-03, /03L-0:on 771010,decay Heat Valve Pit Cover Removed to Inspect Decay Heat Isolation Valves DH11 & DH12 & to Perform Wiring Change on DH12.Insp Required for Leakage & Preventive Maint | /03L-0:on 771010,decay Heat Valve Pit Cover Removed to Inspect Decay Heat Isolation Valves DH11 & DH12 & to Perform Wiring Change on DH12.Insp Required for Leakage & Preventive Maint | | | 05000346/LER-1977-077, Forwards LER 77-077/03L-0 | Forwards LER 77-077/03L-0 | | | 05000346/LER-1977-078-03, /03L-0:on 771011,during Functional Test,Reactor Protection Sys Channel 1 Accidentally de-energized.Caused by Error in Maint Work Order.Personnel Instructed | /03L-0:on 771011,during Functional Test,Reactor Protection Sys Channel 1 Accidentally de-energized.Caused by Error in Maint Work Order.Personnel Instructed | | | 05000346/LER-1977-078, Forwards LER 77-078/03L-0 | Forwards LER 77-078/03L-0 | | | 05000346/LER-1977-079-03, /03L-0:on 771011,source Range Defector NI-1 Indication Failed Low Twice,Then Returned to Normal Operation by Itself.Cause Unknown | /03L-0:on 771011,source Range Defector NI-1 Indication Failed Low Twice,Then Returned to Normal Operation by Itself.Cause Unknown | | | 05000346/LER-1977-079, Forwards LER 77-079/03L-0 | Forwards LER 77-079/03L-0 | | | 05000346/LER-1977-080, Forwards LER 77-080/03L-0 | Forwards LER 77-080/03L-0 | | | 05000346/LER-1977-080-03, /03L-0:on 771016,governor Valve on Auxiliary Feed Pump 1-2 Found Closed During Auxiliary Feedwater Sys Monthly Test Performance.Caused by Possible Design Deficiency. Excessive Vibration Under Investigation by Maint Personnel | /03L-0:on 771016,governor Valve on Auxiliary Feed Pump 1-2 Found Closed During Auxiliary Feedwater Sys Monthly Test Performance.Caused by Possible Design Deficiency. Excessive Vibration Under Investigation by Maint Personnel | | | 05000346/LER-1977-081, Forwards LER 77-081/03L-0 | Forwards LER 77-081/03L-0 | | | 05000346/LER-1977-081-03, /03L-0:on 771018,during Miscellaneous Instrument Shift Checks,Containment to Annulus Differential Pressure Exceeded Water Gauge Tech Spec Limit.Caused by Procedure & Personnel Error.Startup Procedure Modified | /03L-0:on 771018,during Miscellaneous Instrument Shift Checks,Containment to Annulus Differential Pressure Exceeded Water Gauge Tech Spec Limit.Caused by Procedure & Personnel Error.Startup Procedure Modified | | | 05000346/LER-1977-082-03, /03L-0:on 771019,discharge & Recirculation Dampers of Emergency Ventilation Sys 2 Failed to Open When Fan Started.Caused by Loose & Dirty Controller Contacts.Module Removed & Reinserted, & Contacts Cleaned | /03L-0:on 771019,discharge & Recirculation Dampers of Emergency Ventilation Sys 2 Failed to Open When Fan Started.Caused by Loose & Dirty Controller Contacts.Module Removed & Reinserted, & Contacts Cleaned | | | 05000346/LER-1977-082, Forwards LER 77-082/03L-0 | Forwards LER 77-082/03L-0 | | | 05000346/LER-1977-083, Forwards LER 77-083/03L-0 | Forwards LER 77-083/03L-0 | | | 05000346/LER-1977-083-03, /03L-0:on 771025,stop Valve AF3872 Failed to Stroke When Given Open Signal.Caused by Component Failure. Torque Switch Replaced on 771027 | /03L-0:on 771025,stop Valve AF3872 Failed to Stroke When Given Open Signal.Caused by Component Failure. Torque Switch Replaced on 771027 | | | 05000346/LER-1977-084, Forwards LER 77-084/03L-0 | Forwards LER 77-084/03L-0 | | | 05000346/LER-1977-084-03, /03L-0:on 771025,surveillance Test ST 5080.01 Not Performed.Caused by Personnel Error.Test Performed Immediately & Computer Program Revised | /03L-0:on 771025,surveillance Test ST 5080.01 Not Performed.Caused by Personnel Error.Test Performed Immediately & Computer Program Revised | | | 05000346/LER-1977-086-03, /03L-0:on 771028,safety Features Actuation Sys Channel 4 Radiation Monitor RIS 2007 Failed to Respond to Internal Check Source.Caused by Component Failure.Low Amplifier Board Replaced & Monitor Recalibr | /03L-0:on 771028,safety Features Actuation Sys Channel 4 Radiation Monitor RIS 2007 Failed to Respond to Internal Check Source.Caused by Component Failure.Low Amplifier Board Replaced & Monitor Recalibr | | | 05000346/LER-1977-086, Forwards LER 77-086/03L-0 | Forwards LER 77-086/03L-0 | | | 05000346/LER-1977-087, Forwards LER 77-087/03L-0 | Forwards LER 77-087/03L-0 | | | 05000346/LER-1977-087-03, /03L-0:on 771024,safety Features Actuation Sys Channel 3 Containment Radiation Reaqdings Unreliable . Caused by Design/Fabrication Error.Facility Change Request 77-437 Issued for Permanent Repair | /03L-0:on 771024,safety Features Actuation Sys Channel 3 Containment Radiation Reaqdings Unreliable . Caused by Design/Fabrication Error.Facility Change Request 77-437 Issued for Permanent Repair | | | 05000346/LER-1977-088, Forwards LER 77-088/03L-0 | Forwards LER 77-088/03L-0 | | | 05000346/LER-1977-088-03, /03L-0:on 771027,source Range Detector NI-1 Indication Failed Low.Cause Unknown.Updated Rept Forthcoming | /03L-0:on 771027,source Range Detector NI-1 Indication Failed Low.Cause Unknown.Updated Rept Forthcoming | | | 05000346/LER-1977-089-03, /03L-1:on 771107,radiation Monitor RIS 2007 Was Showing Erratic Readings.Caused by Victoreen Low Range Amplifier Board 847-1-20 Failure.Board Replaced | /03L-1:on 771107,radiation Monitor RIS 2007 Was Showing Erratic Readings.Caused by Victoreen Low Range Amplifier Board 847-1-20 Failure.Board Replaced | | | 05000346/LER-1977-089, Forwards LER 77-089/03L-1.W/o Encl | Forwards LER 77-089/03L-1.W/o Encl | | | 05000346/LER-1977-090-03, /03L-0:on 771107,during Review of Deficiency in Steam & Feedwater Rupture Control Sys Monthly Test,Reactor Coolant Pump Found Inoperable.Caused by Component Failure. Voltage Regulating Diode Replaced | /03L-0:on 771107,during Review of Deficiency in Steam & Feedwater Rupture Control Sys Monthly Test,Reactor Coolant Pump Found Inoperable.Caused by Component Failure. Voltage Regulating Diode Replaced | | | 05000346/LER-1977-090, Forwards LER 77-090/03L-0 | Forwards LER 77-090/03L-0 | | | 05000346/LER-1977-091-03, /03L-0:on 771107,containment Radiation Monitor RIS 2006 Spiked & Reset Twice Causing Safety Features Actuation Sys Incident Level 1 Trips.Caused by Design Error | /03L-0:on 771107,containment Radiation Monitor RIS 2006 Spiked & Reset Twice Causing Safety Features Actuation Sys Incident Level 1 Trips.Caused by Design Error | | | 05000346/LER-1977-091, Forwards LER 77-091/03L-0 | Forwards LER 77-091/03L-0 | | | 05000346/LER-1977-092, Forwards LER 77-092/03L-0 | Forwards LER 77-092/03L-0 | | | 05000346/LER-1977-092-03, /03L-0:on 771101,facility Review Board Meeting Revealed That Surveillance Requirement of Venting Hpis Valve HP 72 Not Performed.Caused by Personnel Error.High Point Valve Vented & Modified | /03L-0:on 771101,facility Review Board Meeting Revealed That Surveillance Requirement of Venting Hpis Valve HP 72 Not Performed.Caused by Personnel Error.High Point Valve Vented & Modified | | | 05000346/LER-1977-093, Forwards LER 77-093/03L-0 | Forwards LER 77-093/03L-0 | | | 05000346/LER-1977-093-03, /03L-0:on 771114,reactor Protection Sys Daily Heat Balance Check Not Completed When Station Above 15% Rated Thermal Power During Oct-Nov 1977.Caused by Personnel Error. Surveillance Test Placed on Daily Testing Schedule | /03L-0:on 771114,reactor Protection Sys Daily Heat Balance Check Not Completed When Station Above 15% Rated Thermal Power During Oct-Nov 1977.Caused by Personnel Error. Surveillance Test Placed on Daily Testing Schedule | | | 05000346/LER-1977-094-03, /03L-0:on 771116,emergency Ventilation Sys Dampers Pdv 5014A & B Failed to Modulate Correctly to Draw Down Annulus.Caused by Defective Pressure Differential Controller.Dampers Replaced & Sys Retested | /03L-0:on 771116,emergency Ventilation Sys Dampers Pdv 5014A & B Failed to Modulate Correctly to Draw Down Annulus.Caused by Defective Pressure Differential Controller.Dampers Replaced & Sys Retested | | | 05000346/LER-1977-094, Forwards LER 77-094/03L-0 | Forwards LER 77-094/03L-0 | | | 05000346/LER-1977-095-03, /03L-0:on 771127,control Room Ventilation Isolation Damper HV 5311A Failed to Close on Radiation Monitor Trip.Caused by Component Failure.Damper Dismantled & Sealing Surfaces Cleaned & Lubricated | /03L-0:on 771127,control Room Ventilation Isolation Damper HV 5311A Failed to Close on Radiation Monitor Trip.Caused by Component Failure.Damper Dismantled & Sealing Surfaces Cleaned & Lubricated | | | 05000346/LER-1977-095, Forwards LER 77-095/03L-0 | Forwards LER 77-095/03L-0 | | | 05000346/LER-1977-097, Forwards LER 77-097/03L-0 | Forwards LER 77-097/03L-0 | | | 05000346/LER-1977-097-03, /03L-0:on 771129,radiation Monitor Re 2006 Tripped Safety Features Actuation Sys Channel 3 Containment Radiation Due to Sporadic Spiking.Caused by Component Failure in Radiation Detector.Detector Replaced | /03L-0:on 771129,radiation Monitor Re 2006 Tripped Safety Features Actuation Sys Channel 3 Containment Radiation Due to Sporadic Spiking.Caused by Component Failure in Radiation Detector.Detector Replaced | | | 05000346/LER-1977-100-03, /03L-0:on 771201 & 05,source Range Neutron Detector NI-1 Indication Dropped to Zero & Returned to Normal Operation W/O Assistance.Cause Unknown.After First Failure,Detector Replaced & Retested | /03L-0:on 771201 & 05,source Range Neutron Detector NI-1 Indication Dropped to Zero & Returned to Normal Operation W/O Assistance.Cause Unknown.After First Failure,Detector Replaced & Retested | | | 05000346/LER-1977-100, Forwards LER 77-100/03L-0 | Forwards LER 77-100/03L-0 | | | 05000346/LER-1977-101-03, /03L-0:on 771201,diesel Generator 1-1 Inoperable Due to Failure to Perform Required Surveillance Testing on Diesel Generator 1-2 within Required Tech Spec Interval. Caused by Personnel Error | /03L-0:on 771201,diesel Generator 1-1 Inoperable Due to Failure to Perform Required Surveillance Testing on Diesel Generator 1-2 within Required Tech Spec Interval. Caused by Personnel Error | |
|