LER-1979-057, /01T-0:on 791019,while in Shutdown,Three of 16 MSIV Scram Limit Switches Found W/Setpoints Greater than 10%.Caused by Not Performing Field Calibr on Switch Setpoints Set by Manufacturer.Limit Switches Readjusted |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2371979057R01 - NRC Website |
|
text
....,
e Common<h Edison Dresden Nudear Power Station R.R. #1 Morris, Illinois 60450
- Telephone 815/942-2920 October 31, 1979 BBS LTR /179-874 James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory.Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report 1179-57/0lT-0, Docket 11050-237 is hereby.submitted to your office ih accordance with Dresden Nuclear Power Station Technical*Specification 6.6.B.l:(a), failu:re of the reactor protection sys;tem or other.systems subject to limiting safety system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety system setting in the technical specifica-tions or failure to. complete the required protective *function.
BBS:lcg Enclosure f;~p~k11A Station Superintendent Dresden Nuclear Power Station cc:
Director of Inspection & Enforcement Director of Management Information & Program Control Ft1e/NRC
/
.:~...
~~OCK !
..
~ -.*::.~:.:,~TOR TVP.L REOUIR<D INFDRMATIONI
))~*Lr ]L In IR Is Ir IG)I o Io I - I o Io Io Io I 0.1-Io Io IG)l 4 11 11 11 11 101 I I@
8 9
LICENSEE CODE 14 15 LICENSE NUM8E;1 ""
25 26 LICENSE TYPE JO 57 CAT 58
~~~~~~* ~©10 1 s 10 10 10 12 13 17"' GI 11.0 I 1 I 91) I 9 1011 I 0 j 3 11 I 7 I 8
60 61 DOCKETNUM8ER 68 69
. EVENT"OATE
EVENT DESCRIPTION AND PROBABLE CONSEQUE.NCES@
.....,,, --~-
9jG)
BO C[I] fWhile in the S/D mode of operation the MSIV scram*limitswit'ches were checked.
r~..:. -~_J.._... _
-* "t";;,;;~~;,,,.
QI] I Of the 16 limit switches 3 were--found to have setpoints) 10%.. This event was
.--**-****v*
- .,._~*,.
~
I of minimal safety significance since the switches with setpoints.) 10% were all**
I located ori the inboard MSIV' s and all the outboard MSIV' s had setpoints..l...lQ~_ *'
o:IJ.
(([] I as required by Tech. Spec. Table* 3.1.1 ~*:*This is the -first..e:v~n.t.:.~of..,J:.his __ :t;yp_g __ ~L 82]
[ill Dresden.
8 9 iTil 8
SYSTEM CODE I IIAI@
9 10 t::::\\
LER/RO CVENT YEAR
~REPORT 17 19 I NUMBER 21 22
CAUSE
CAUSE COMP.
CODE SUBCODE COMPONENT CODE SUB CODE 1.!J@ UJ@ I I IN I s IT IR I u I@ -- L.:J@
11 12 13 1B 19 l:::J 23 SEQUENTIAL REPORT NO.
I o I s 1 71 24 26 OCCURRENCE cooe Io 11 I 2B 29 REPORT TYPE L.:.J 30 VALVE SUBCODE L_j@
20 l.=1 31 TAKEN ACTION ON PLANT METHOD HOURS 22 ATTACHMENT SUBMITTED NPRD-4 FORM!:iUB.
PRIME COMP.
SUPPLIER
REVISION NO.
~
32 COMPONENT MANUFACTURER BO IN I 0 11 IS I@
ACTION FUTURE EFFECT
- - SHUTDOWN
~
L!J@~@ ~@ ~@)
0 1°1 °1 I
33 34 35 36 3 7 40 L!J@
41
~@) L!:J@
42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS I The Namco Snap Lock Limit Switch setpoints were* set by the manufacturer..The need* for ill] field calibration of the *exact limit switch tr.ip point did not seem necessary at the IITI time of installation.
The limit switches were readjusted and demonstrated operable.
I I1JJ I Unit 3 MSIV scram limit switches to be tested during the next refueling outage.
No
- II3J I further action necessary, 8
9 FACILITY STATUS
% POWER OTHER STATUS iJIJ l_QJ@ I 0 I 0 I 0 l@I N/A B
9 10 12 11 ___
- 44_,
ACTIVITY CONTENT Q\\
RELEASED OF RELEASE AMOUNT OF ACTIVITY~
C0 UJ@) W@I N/A B
9 10 11 44 PERSONNEL EXPOSURES r:;;:;,.
80 METHOD OF DISCOVERY DISCOVERY DESCRIPTION 32 lE..JC'iV~l_E_x_t_e_r_n_a_l--'-S_o_u_r_c_e_-_Q~u_a_d ___ c_i_*t_i_*_e_s _____ ---1
~
~
~.
BO N/A
, LOCATION OF RELEASE @
45 BO NUMBER
~TYPE DESCRIPTION~
~
I 01 01 ~~~_N_/A
8 9
11 12 13 BO NUMBER DESCRIPTION 41 PERSONNEL INJU'11ES
~
~
I 01 0 I 01@..__* __
N_A ______________
_.J
- - 8 9
11 12 LOSS OF OR DAMAGE TO FACILITY 0 TYPE
DESCRIPTION
~
80 "Q2J ~@
N/A 8
9 1~0:----------------------------------------------------__J PUBLICITY
(';';\\
80 ISSUEDeDESCRIPTION ~
N RC USE ON l Y
- !T(j1 I NI t\\4 N/ A I *~
~L.::.I 111111111111
~
B 9
10 68 69 NAME OF PREPARER M. Korchynsky PHONE* X-422 0
a...,
-*****-~*** ******:
- -~"----,............ __., _____________ *-**---**::*-*---***-.*--..,..., ______ ~*--*----------'---------,---
J
e.
ATTACHMENT TO LICENSEE~EVENT REPORT79-57/01T-O COMMONWEALTH EDISON COMPANY (CWE)
DRESDEN. UNIT ILDRS-2 DOCKET iJ 050-237 Quad Cities Station was requested by the NRC to check the *MSIV scram limit switch setpoints.
Several setpoints were not L.10% as required by Tech Spec
While Dresden Unit 2 was in a S/D mode of operatiori, the MSIV scram limit switches were checked.
Of the sixteen (16) limit switches, three (3) were found tQ have setpoints highe~ than 10%.
MSIV 203-lA. had limit switch setpoints of 15% and 17%, while MSIV 203-lD had one (1) limit sw_itch with a set point of 10.3%.
This event was of minimal safety.significance since all the limit switches with high set points were located on the inboard MSIV's and all the outboard valves had limit switch setpoints of ~l0%. This is.the first event of this type at Dresden.
The Namco Controls Snap-.Lock Limit Switch set points were set by -the manu-facturer.
The need for field:calibration of.-the exact limit switch trip.point.
did not seem necessary.at the tiine *of.installation.* The.limit switches were re-adjusted and demonstrat~d operabre." -* The Unit 3 M.SIV s<;r?Jil limit switches will be similarly tested c,iuring F~*e. next refueling outage~.. No further action is, necessary.
r.~-... -..,.,::-*.:-
---'~; *,.,....
- ~_-.
- . ~*~* ;*.. ~-~~:*.-::\\,: *...
A
- . *:.~'
. ('.
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000237/LER-1979-001-03, /03L-0 on 790103:torus Level Increased to -1 Inch, Due to Repetitive Starts of HPCI Turbine.Increase in Torus Level Determined to Be Result of Inadequate Procedure.Hpci Surveillance Procedures to Be Amended | /03L-0 on 790103:torus Level Increased to -1 Inch, Due to Repetitive Starts of HPCI Turbine.Increase in Torus Level Determined to Be Result of Inadequate Procedure.Hpci Surveillance Procedures to Be Amended | | | 05000237/LER-1979-001, Forwards LER 79-001/03X-1 | Forwards LER 79-001/03X-1 | | | 05000010/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000010/LER-1979-001-03, /03L-0 on 790518:while Digging Ditch for New Pipe, Const Personnel Observed Water Running Into Trench from Proximity of Radwaste return-to-storage Line.Caused by Return Line to 1A Storage Leaking from Aluminum Line | /03L-0 on 790518:while Digging Ditch for New Pipe, Const Personnel Observed Water Running Into Trench from Proximity of Radwaste return-to-storage Line.Caused by Return Line to 1A Storage Leaking from Aluminum Line | | | 05000010/LER-1979-002-03, /03L-0 on 780825:during Monthly Surveillance DI5 5400-2,offgas Monitor 1 Tripped at Greater than 100%, Which Is Not within Setpoint Limit.Caused by Instrument Drift.Setpoint Recalibr | /03L-0 on 780825:during Monthly Surveillance DI5 5400-2,offgas Monitor 1 Tripped at Greater than 100%, Which Is Not within Setpoint Limit.Caused by Instrument Drift.Setpoint Recalibr | | | 05000010/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000237/LER-1979-002, Forwards LER 79-002/01X-1 | Forwards LER 79-002/01X-1 | | | 05000237/LER-1979-002-01, /01X-1 on 790103:during Normal Operation,Hpci Turbine Failed to Start During Quarterly Flow Test.Caused by Partial Engagement of Interlock Dump Valve Operating Lever. Lever Adjusted.Hpci Started to Verify Operability | /01X-1 on 790103:during Normal Operation,Hpci Turbine Failed to Start During Quarterly Flow Test.Caused by Partial Engagement of Interlock Dump Valve Operating Lever. Lever Adjusted.Hpci Started to Verify Operability | | | 05000237/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000237/LER-1979-003-03, /03L-0 on 790105:PS 2-1430-1466D Tripped at 105 Psi.Caused by Instrument Drift | /03L-0 on 790105:PS 2-1430-1466D Tripped at 105 Psi.Caused by Instrument Drift | | | 05000237/LER-1979-004-03, /03L-0 on 790111:LPCI Sys Full Flow Test Valve MO-2-1501-38B Failed While Securing D LPCI Pump.Caused by Broken Pinion Gear on Valve Operator Motor Shaft | /03L-0 on 790111:LPCI Sys Full Flow Test Valve MO-2-1501-38B Failed While Securing D LPCI Pump.Caused by Broken Pinion Gear on Valve Operator Motor Shaft | | | 05000237/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000237/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000237/LER-1979-005-03, /03L-0 on 790119: During Normal Operation, Mass Spectometer Leak Detector Downscale Condition Annunciated & High Rad Alarm & Half Scram Occurred Twice on Same Day. Log Rad Monitor Replaced | /03L-0 on 790119: During Normal Operation, Mass Spectometer Leak Detector Downscale Condition Annunciated & High Rad Alarm & Half Scram Occurred Twice on Same Day. Log Rad Monitor Replaced | | | 05000237/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000237/LER-1979-008-03, /03L-0 on 790126: LPCI Min Flow Value MO-2-1501-13A Failed to Close Completely During LPCI Pump Operability Surveillance.Cause of Failure Unknown | /03L-0 on 790126: LPCI Min Flow Value MO-2-1501-13A Failed to Close Completely During LPCI Pump Operability Surveillance.Cause of Failure Unknown | | | 05000237/LER-1979-009-03, /03L-0 on 790121:plant Chimney Sampling Sys Operating Incorrectly.Caused by Purge Valve V2 Being Stuck Open | /03L-0 on 790121:plant Chimney Sampling Sys Operating Incorrectly.Caused by Purge Valve V2 Being Stuck Open | | | 05000237/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000237/LER-1979-010-01, /01T-0 on 790202:section of Blowout Panel Blown Out,Breaching Secondary Containment.Cause Under Investigation | /01T-0 on 790202:section of Blowout Panel Blown Out,Breaching Secondary Containment.Cause Under Investigation | | | 05000237/LER-1979-010, Forwards LER 79-010/01T-0 | Forwards LER 79-010/01T-0 | | | 05000237/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000237/LER-1979-013-03, /03L-0 on 790223:after Diesel Generator Was Manually Started Prior to Taking Transformer Out of Svc, Water Pump Breaker Thermally Tripped & Redundant Power Supply Also Tripped.Cause Unknown | /03L-0 on 790223:after Diesel Generator Was Manually Started Prior to Taking Transformer Out of Svc, Water Pump Breaker Thermally Tripped & Redundant Power Supply Also Tripped.Cause Unknown | | | 05000237/LER-1979-014-03, /03L-0 on 790305:U2 Diesel Generator Failed to Start on First & Fifth Attempts.Caused by Bendix Gear Failure to Engage & Failure of Air Start Solenoid to Energize.Solenoid Was Replaced | /03L-0 on 790305:U2 Diesel Generator Failed to Start on First & Fifth Attempts.Caused by Bendix Gear Failure to Engage & Failure of Air Start Solenoid to Energize.Solenoid Was Replaced | | | 05000237/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000237/LER-1979-015, Forwards LER 79-015/01T-0 | Forwards LER 79-015/01T-0 | | | 05000237/LER-1979-016, Forwards LER 79-016/01T-0 | Forwards LER 79-016/01T-0 | | | 05000237/LER-1979-017-01, X2 for Dresden, Units 2 and 3 Re Inadequacies Observed in Implementation of Administrative Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection System or Engineered Saf | X2 for Dresden, Units 2 and 3 Re Inadequacies Observed in Implementation of Administrative Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection System or Engineered Safety Feature Sys | | | 05000237/LER-1979-017, Forwards LER 79-017/01T-0 | Forwards LER 79-017/01T-0 | | | 05000237/LER-1979-019, Forwards LER 79-019/03L-0 | Forwards LER 79-019/03L-0 | | | 05000237/LER-1979-020-03, /03L-0 on 790413:measured Leakage for Personnel Air Lock Was 54.63 Std Cubic Ft/H.Leakage Identified Through Outer Lower Handwell.Shaft Packing Was Replaced & Air Lock Retested | /03L-0 on 790413:measured Leakage for Personnel Air Lock Was 54.63 Std Cubic Ft/H.Leakage Identified Through Outer Lower Handwell.Shaft Packing Was Replaced & Air Lock Retested | | | 05000249/LER-1979-021-03, /03L-0:on 790821,during Normal Operation,Offgas Monitor 3A Took Step Increase W/No Power Change & hi-hi Trip Light Was On.Caused by Faulty V1 Electrometer Tube,Which Was Replaced.Monitors Will Be Tested Monthly | /03L-0:on 790821,during Normal Operation,Offgas Monitor 3A Took Step Increase W/No Power Change & hi-hi Trip Light Was On.Caused by Faulty V1 Electrometer Tube,Which Was Replaced.Monitors Will Be Tested Monthly | | | 05000237/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000237/LER-1979-022, Forwards LER 79-022/03L-0 | Forwards LER 79-022/03L-0 | | | 05000237/LER-1979-023-03, /03L-0 on 790406:during Radioactive Insp,Lack of Fusion Noted in Weld 4-4 on 4-inch Reactor Head Vent Line 2-0215-4.Weld Cut Out & Rewelded Per ASME Boiler & Pressure Vessel Code.Asme Hydrostatic Test Completed | /03L-0 on 790406:during Radioactive Insp,Lack of Fusion Noted in Weld 4-4 on 4-inch Reactor Head Vent Line 2-0215-4.Weld Cut Out & Rewelded Per ASME Boiler & Pressure Vessel Code.Asme Hydrostatic Test Completed | | | 05000249/LER-1979-023-03, /03L-0:on 790823,source Range Monitor Calibr Supplied Rod Block Trip at 1.03E5,exceeding Tech Specs Limit.Caused by Drift & Temp Dependency in Source Range Monitor.Defective Component Not Yet Identified | /03L-0:on 790823,source Range Monitor Calibr Supplied Rod Block Trip at 1.03E5,exceeding Tech Specs Limit.Caused by Drift & Temp Dependency in Source Range Monitor.Defective Component Not Yet Identified | | | 05000237/LER-1979-025, Forwards LER 79-025/03L-0 | Forwards LER 79-025/03L-0 | | | 05000237/LER-1979-026, Forwards LER 79-026/03L-0 | Forwards LER 79-026/03L-0 | | | 05000249/LER-1979-027, Forwards LER 79-027/03L-0 | Forwards LER 79-027/03L-0 | | | 05000237/LER-1979-027-03, /03L-0 on 790502:during Startup,Main Turbine Tripped on High Water Level.Caused by Packing Leak on Isolation Valve for PS-263-60B.Packing Adjusted,Tested & Sys Lineup Returned to Normal | /03L-0 on 790502:during Startup,Main Turbine Tripped on High Water Level.Caused by Packing Leak on Isolation Valve for PS-263-60B.Packing Adjusted,Tested & Sys Lineup Returned to Normal | | | 05000237/LER-1979-027, Forwards LER 79-027/03L-0 | Forwards LER 79-027/03L-0 | | | 05000249/LER-1979-027-03, /03L-0:on 791003,half of Trip Sys Inoperable Due to Lifting of Flooding Magnetrol Switch Leads to Condenser Pit.Switch Leads Reattached.No Precise Cause Found | /03L-0:on 791003,half of Trip Sys Inoperable Due to Lifting of Flooding Magnetrol Switch Leads to Condenser Pit.Switch Leads Reattached.No Precise Cause Found | | | 05000237/LER-1979-028, Forwards LER 79-028/03L-0 | Forwards LER 79-028/03L-0 | | | 05000237/LER-1979-028-03, /03L-0 on 790508:N2 Line Low Temp Alarm Received & Frost Found on Inerting line.A0-2-1601 & Inerting Line Failed Leak Rate Test.Caused by Failure of Temp Recorder at N2 Vaporizer | /03L-0 on 790508:N2 Line Low Temp Alarm Received & Frost Found on Inerting line.A0-2-1601 & Inerting Line Failed Leak Rate Test.Caused by Failure of Temp Recorder at N2 Vaporizer | | | 05000237/LER-1979-029-03, /03L-0 on 790508:DIS 1400-3,pressure Switch 2-1430-1466D Failed to Trip.Caused by Sticky Plunger in Pressure Switch.Switch Removed,Cleaned & Reset to Trip at 94.5 Psig Increasing | /03L-0 on 790508:DIS 1400-3,pressure Switch 2-1430-1466D Failed to Trip.Caused by Sticky Plunger in Pressure Switch.Switch Removed,Cleaned & Reset to Trip at 94.5 Psig Increasing | | | 05000237/LER-1979-029, Forwards LER 79-029/03L-0 | Forwards LER 79-029/03L-0 | | | 05000249/LER-1979-030-03, During Scram Testing in Refuel Mode,Substantial Loss of Position Indication Noted for Control Rod Driveline H-9.Caused by Improperly Seated Socket,Suggesting Faulty Electrical pin-socket Alignment | During Scram Testing in Refuel Mode,Substantial Loss of Position Indication Noted for Control Rod Driveline H-9.Caused by Improperly Seated Socket,Suggesting Faulty Electrical pin-socket Alignment | | | 05000249/LER-1979-030, /03X-1 for Dresden Unit 3 Regarding a Supplement to LER 79-30/03L-0 Addressing the Cause and Corrective Actions for the Loss of Position Indication for CRD H-9 | /03X-1 for Dresden Unit 3 Regarding a Supplement to LER 79-30/03L-0 Addressing the Cause and Corrective Actions for the Loss of Position Indication for CRD H-9 | | | 05000237/LER-1979-031-03, /03L-0 on 790509:crack Found on 2D1 Feedwater Emergency Spill to Condenser Line & Crack Located on Pipe to Condenser Weld.Caused by Mechanical Failure.Cracked Portion Removed & Rewelded | /03L-0 on 790509:crack Found on 2D1 Feedwater Emergency Spill to Condenser Line & Crack Located on Pipe to Condenser Weld.Caused by Mechanical Failure.Cracked Portion Removed & Rewelded | | | 05000237/LER-1979-031, Forwards LER 79-031/03L-0 | Forwards LER 79-031/03L-0 | | | 05000237/LER-1979-032, Forwards LER 79-032/03L-0 | Forwards LER 79-032/03L-0 | |
|