LER-1979-032, Forwards LER 79-032/03L-0 |
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Commonwe& Edison Dresden Nuclea;Wwer Station,.
R.R. #1 Morris, Illinois 60450
- - Telephone 815/942-292(1 May 30, 1979 BBS LTR /179-433 James G. Keppler, Regional Director Directorate of Regulatory Operations U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Region III Reportable Occurrence Report #79-32/031-0, Docket #050-237 is hereby submitted* *to your office in _accordance wf°th Dresden Nuclear Power Station Techriical Specification 6.6.B.2.(b), condittons leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limi~ing condition for oper?-
tion.
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B. B. Stephenson Station Superintendent Dresden Nuclear Power.Station BBS:lcg Enclosure cc:
Director of Inspection & Enforcement
- Director of Management Information &
File/NRG
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Program Control I***
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LICENSEE CODE 14 15 I o I - lo Io Io Io Io 1-lo Io 1014 LICENSE NUMBER 25 26 I i I 1 I 1.1 1 10l
- 1 10 LICENSE TYPE 30 57 CAT 58 CON'T
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[§TI] I IRM.' s 17 and 18 in the "A" trip system were found downscale during rod pulls to heat-I [QJJ] I ing power.
Since T.S.*Table 3.1.1 requires three operable instrument channels per J
[.QJJJ. I trip system, operator immediately initiated a manual.half-scram.
Event had minimal I
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safety significance since remaining two chann~ls in the iiAi' *.trip system were operable.
[QJTI I No effect on public health or safety.**
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SYSTEM CODE I II Al@
9 10 LER/RO CVENT YEAR REPORT I 7 I 9 I NUMBER 21 22 ACTION FUTURE TAKEr~
ACTION EFFECT ON PLANT
_:.* COMPONENT CODE.
CAUSE
CAUSE CODE SUBCODE.
COMP.
VALVE SUBCODE
. SUBCODE w ~@. I i NI s I T I R I u I@ ~@
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11 l=.I 23 SHUTDOWN METHOD 12 13 18' 19
- 20.
SEQUENTIAL OCCURRENCE REPORT REPORT NO.
CODE TYPE 10131 2 1 I/I 1°1 3 1
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24 26 2 7 28 29 JO 31 r::;::;...
ATTACHMENT NPRD*4 PRIME C.OMP *.
SUPPLIER*
. REVISION NO.
32 COMPONENT.
MANUFACTURER 80
. HOURS *~. SUBMITTED
.FORM :;us.
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. 37 40 41
. 42 W@ I c I o Is Io *1@
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS@
47 I IRM 17 failed because of a faulty connector' due to 'apparent minor damage during *re-
[IIJJ fueling.
Connector was replaced and tested satisfactorily.
IRM 18 had a loose input
It was tightened and the downxcale. alarm cleared. - This was. the.1':S.\\::q [ITIJ.__f_i_* r_s_t_o_c_c_u_r,....e_n_c....,e_* o_f_
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using surveillance DIS 700-4.
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FACILIT'f
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. *.. DISCOVERY DESCRIPTION 32 ITTIJ UJ@ I 0 I 0 I 0 l@I NA I ~@
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- .*_>_***_:*I B ATIVITY cJ~TENT 12 l1
- 44 45 46 RELEASED OF RELEASE
. AMOUNT OF ACTIVITY @
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. 110 11 PERSONNEL EXPOSURES
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TYPE DESCillPTION
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. *. :i'* *:* LOSS OF OR DAMAGE TO FACILITY 143'
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DEVIATION REPORT
_ Commonwealth Edison DVR t-10.
STA UNIT YEAR N~
D 2 -
79-5 PART 11 TITLE OF DEVIATION Unit 2 IRM 17 & 18 Downscale SYSTEM AFFECTED 700
PLANT CONDITIONS
Neutron Monitoring System StartuE MODE*
PWR (MWT)
DESCRIPTION OF EVENT
iRM's 17 & 18 both downscale during rod pull to heating power DESCRIPTION OF GAUSE
.Unknown at this time
' I'
OCCURRED 5-:1-79 2200
.DATE TIME TESTING 0
CJ.m
. : LOAD (MWE}
- YES NO EQUIPMENT DD YES FAILURE.
. N/A WR NO.
3174 Randall Black
~w;i..w.&J~_~R~ES-P~O~N~S~l~BL-E~SU_P_f-RV-l~S~O-R~~~--
DATE PART 2 I OPERATING ENGINEERS COMMENTS All control rods inserted and mode switch moved to refuel position.
Manual half scram initiated immediately on Channel B.
SAFETY-TYPE OF DEVIATION EVENT OF POTENT I AL TECH SPEC "NON-REPORTABLE ANNUAL
. RELATED REPORTABLE OCCURRENCE PUBLIC INTEREST VIOLATION
,OCCURRENCE REPORT I NG : - WR ISSUED D
D 10CFR21 14 DAY D
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30 DAY NOTIFICATION 6.6.B.2.b
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REPORTABLE CCCURRENCE ACTION ITEM NQ.
NUMBER *
~- 79-32-03L--0 24-HOUR NRC NOTIFICATION DTPH NLA REGION I I I DATE TIME DTGM NLA REGION 11 I Be DOL CATE TIME RESPONSIBLE* COMPANY OFFICER INFORMED OF 10CFR21 ND ONS AND THEIR REPORT TO C
. *. REVl EW AND COMPLETED YES CB YES 5J D
,D NO D NO D PROMPT ON-SITE NOTIFICATION A. Roberts - Asst. Supt.
- - S/15/79 1600 TITLE DATE TIME N/A TITLE DA.TE
- TIME PROMPT OFF-SITE NOTIFICATION F..A. Palmer 5/16/79
. 10: 30 TITLE DATE-TLME -
J. R. Gilliom
... 5/16/79 10:30 TITLE DATE TIME.
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DATE TIME
- _ 5/10/.79.:*..
DATE
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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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