LER-1979-025, Forwards LER 79-025/03L-0 |
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j ---o;. ~mr&nwealth9son Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS ~TR 117 %417 May 24, 1979 James G. Keppler, Regional Director:~;~
Directorate of Regula~ory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report; 1179-25/031-0, Docket 11050'-237 is hereby submitted to ybur office in accordance with Dresden Nuclear Power Station Technical Specificat16n 6.6.B.2.(b),
conditions leading to operation in a degraded mode permitted.
by a limiting ~ondition for operation or plant-shutdown re-quired by a limiting conditio~ for operation.
BBS:lcg En_closure ephenson Station Superintendent Dresden Nuclear Power Station cc:
Director of inspection & Enforcement Director of Management*-Information & Erogram Control File/NRC
.\\Y 2 91979
~. e
, Commonwealth Edison DEVIATION REPORT Ov NO.
STA UNIT YEAR NO.
D -
12 -
2 -
79 -
44
~eART l(TITLE OF DEVIATION OCf!;!~~~79 1700 U2 Turb. 1st Stage Press. 45% Scram Bypass SYSTEM AFFECTED 590
PLANT CONDITIONS
Reactor Protection System
DESCRIPTION OF EVENT
Refuel MODE.
0 PWR (MWT)
, LOAD(MWE)
DATE TIME TESTING 0
GU CJ YES NO Found PS2-504C Channel "A" Logic and PS2-504D (Channel "B" Logic) to trip 10 PSI above Tech Spec limit (~400 PSI).
Tested each switch several times and trip points repeated at 410 PSI incr.
Station established limits 387 PSI +/- 5 PSI.
DESCRIPTION OF C~USE Unit shutdown, and switches at 0 PSI.Under this condition the bourdon tubes seem to "relax" (metal stress).
OTHER.APPLICABLE INFORMATION Reset switches to 389. PSI incr and 386 PSI incr respectively.
Verified repeatability.
EQUIPMENT UD YES FAILURE ONO DR NO.
N/A WR NO.
PART 2 I OPERATING ENGINEERS* COMMENTS N/A Alan R. Zapatocky 4/25/79 RESPO_NSIBLE SUPtRVISOR DATE All control rods fully inserted.
Rx mode switch-in refuel.
Redundant instrumentation was operable.
SAFETY-TYPE OF DEVIATION EVENT OF POTENTIAL TECH SPEC NON-REPORTABLE ANNUAL RELATED REPORTABLE OCCURRENCE PUBLIC INTEREST VIOLATION OCCURRENCE REPORT I NG WR ISSUED D 14 DAY D 10CFR21
~
30 DAY NOT I FI CATJ ON D
6.6.B.2. b REPORTABLE CCCURRENCE ACTION ITEM NO.
NUMBER XlGm 25 ---o3L-0 N/A 24-HOUR NRC NOTIFICATION DTPH N/A REGION I I I DATE TIME
- -oTGM N/A REGION I I I & DOL CATE TIME RESPONSIBLE COMPANY OFFICER INFORMED OF IOCFR21 CONDITIONS AND THEIR REPORT TO NBC ACCEPTANCE BY STATION REVIEW AS REOU I RED DATE RESOLUTION APPROVED AND AUTHORIZED FOR DISTRIBUTION 86*5176 10*77 (FORM 15*S2*t)
YES [!]
YES 0 D
D NO D NO 0 PROMPT ON-SITE NOTIFICATION B. B. Stephenson 5/11/79 TITLE DATE TIME N/A TITLE DATE TIME PROMPT OFF-SITE NOTIFICATION F. A. Palmer 5/11/79 11:24 Tl TLE s?1Alh9 TIME J. R. Gilliom 11 :24 TITLE DATE TIME TITLE DATE TIME
__ John W. Wujciga ~~-J+-i
~fa-1/ry PE RAT I NG ENG I DATE
'l.'rtl!l\\l~!!t!~Y ?t~Y
- ~* -*~~TROL BLOCK: I. **; "'* I I~
(PLEASE PRINT OR TYPE AL.UIRED INFORMATION) rn,
I, L, D, R 1 s, 2 101 o 1 o 1 _, o 1 o 1 o 1 o, o 1 _, o, o 101 4 1 1, 1, 1, 1 101 1
, cv 7
8 9
LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58
.COf)l:T *
. l:2EJ
~~~~~ L!:JG) I o I s I o I o I o I 2 I 3 11 IGJ o I 4 I 2 I s I 1 I 9 I© I o I 5 I 2 I 4 I 1 I 9 I G) 7
- 8. ---* 60----- --61 *--...
DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
I While performing monthly surveillance DIS 500-7 ~ PS 504C and Ps* 504D tripped at 410 PSif TIT.TI I Tech Spec 3.1.1 requires tr{p at first st~ge turbine pressure less than that at 45%
[ill].
~
1rated steam flow (400 psi).
Safety implicati~ns minimal since unit shutdown for re-
[Q))J* -1 fueling during month.
Simil~r event ref~* in RO /178-29-03L-0.
[ill]
. [IT?]
(())]
7 8 9 rrm*
1 a*.
SYSTEM CODE I I I A I@
9 10 '.
@ LEA/RO LVENT YEAR 17 REPORT I 7 I 9 I NUMBER 21 22
CAUSE
CODE w@
11 l.=.I
CAUSE
COMP.
SUBCODE COMPONENT CODE SUBCODE LIJ@ IIINlslrlRlul@ UJ@
12 13 18 19
. SEQUENTIAL OCCURRENCE*
REPORT REPORT NO.
CODE TYPE I o I 21 s 1 171 Io I 3 I L!J 24 26 27 28 29 30 VALVE SUB CODE Lz.J@
20 L=J 31 REVISION NO.
l.Q_J 32 80
. *. ACTION FUTURE EFFECT
.SHUTDOWN t:;:;...
ATTACHMENT NPAD-4 PRIME COMP.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FOAM :>UB.
SUPPLIER MANUFACTURER l!J@LJJ@ UJ@ UJ I 0 I 01 01 01
~@) ~@ W IB 10 16 19 I 33 34
. 35 36 37 40 41 42 43 44 47
.CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
lJ))]. I Cause attributable to instrument drift during prolonged shutdown period. *.PS 2-504C &*** *
((OJ !PS 2-504D reset *t.o.389 psi and 386 psi incr¢!'lsfng, respectiv~]y, and repeat_abiU.,.,ty"-----'
ITm !verified.
Switches will continue to. be* tested monthly per DIS 500-7.
.. CTIIJ [ill]
7 8
9 80 FACILITY
% POWER
. DE] L!Ll@ I 01 ol ol@)l..__NA ___
OTHER STATUS METHOD OF
(:;:;\\
DISCOVERY DISCOVERY DESCRIPTION 0
~~~I _____
M_o_n~th_l_y.__S_u_rv_e_1~*1~1_a_n_c~e ____ __,
7..
10 12 1'3 ACTIVITY CONTENT
~
RELEASED OF RELEASE AMOUNT O.F ACTIVITY ~
~
L_ij@ UJ@l.._* __ N_A _____ ___.
7 8
9 10 11 44 45 46 LOCATION OF RELEASE @**
80
- 44.
45 NA BO.
PERSONNEL EXPOSURES r::;:;.,
.. NUMBER
. (.;:;\\TYPE
DESCRIPTION
"ITI2] I 0 I 0 I 0 lW@..... I _. _N_A ___ __,_ _ _..,... ________________ __,
7 8
9 11 12 13 80 PERSONNEL INJURIES
(;";\\
r r.-r::-1 I NIUMBE,R*
jCr::l[DESCRIPTION~
. -7 q 0 J 3 () 0 ~ Q °'
~0 0
0 ~~--*--*=NA;.;:_ _________
l_f _____
f_..;_f ____ __.
7 8
9 11 12 LOSS OF OR DAMAGE TO FACILITY 143' TYPE
DESCRIPTION
~
Eli) W@
NA 80 1
B 9
10 80 issu:~eu~:;CFllPTION@
NRC USE ON Ly ITliJ LNJ@'-----.u.Q...------....---------------J I I I I I I I I I I I I I ~
7 8
9 10 68 69 80* c;;
0 a.
<J John Dunbar NAME OF PREPARE~.~-~~~~~~~~~~--~-~
PHONE:_..:;X;-...-_4:...:;8:...:9~--------
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| 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 | |
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