LER-1979-027, Forwards LER 79-027/03L-0 |
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Commonweillllla Edison Dresden Nuclea.Wwer Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920. --~-____,_ __
May 30, 1979 BBS LTR #79-428 James G. Keppler,. Regional Director Directorate of Regulatory Op~rations - Region III U.S. Nuclear Regulatory COIDillission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report f/79-27/03L-0, Docket #050.,...237 is hereby submitted to your office in accordance with Dresden Nuclear Power Technical Specification 6.6.B.2.(b), conditions ieading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.
nson Station* Superi~tendent**.
Dresden Nuclear.Power Station BBS:lcg_
Enclosure cc:
Director o,f Inspection & '**Enforcement Director of Man~gement Information & PrograIIl Control FileiNRC
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L REauoREo o~FORMATIONI
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9 LICENSEE CODE 14 15
. _t;ICENSE.NUMBER 25 26 LICENSE TYPE JO 57 CAT 58 1 CON'T 1 0I]
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. 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT OATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES @
had I t ** [§]2]. I During startup main turbine trip~ed on high water. level.
"B" yarway reference leg f
drained because of a leak<<)rt **lo:cal pressure indicatio~ isolation val;e.. High Rx rorJ1 LI~~~~~~~~~~~~~~;__~_;_;.~~~~~~~~~~--:-~-=~~:---~
1*;;. pressure switches PS-263-SSC and D were isolated to is~late. leak.*. Since T. S. Table.
lnTi:l,.. 3.1.1 requires 2.. :instrument. channels p~r.. trip system,*. an orderly ~ shutdown was. be-.
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[fill
. gun inunediately.
Minimal safety significance. since both trip systems were still oper-1
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REPORT I z 1 9 I NUMBER 21 22.
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CAUSE
COMP.
VALVE CODE.
SUBCODE COMPONENT CODE SUB CO OE SUBCODE W@'L!J@ IVlAILIVIEtxl@l!J@LR.J@
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. REPORT NO.
CODE TYPE I
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26 27
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31 REVISION NO.
L.QJ 32 ACTION FUTURE
. EFFECT SHUTDOWN r:;::..
ATTACHMENT NPRD-4*
1 PRIME COMP.
C.OMPONENT.
MANUFACTURER 80 TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB.
SUPPLIER W@l.LJ@). L£J@. LLJ I ol ol ol ol W@.W ~@
33 34 35 36 3 7 40 41 42 43 I c I o 1 a* Io I@
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
44 47 [I)):] I A packing leak wa,s found.on the isolation valve for-PS-263-60B.
The l~ak.. was :i.solatedl
. which also isolated 263-ssc* and 55D (high reactor press.ure), and yarway hfgh side. for 263-59B, 58A; 58B~ 72B, and 72D.
The packing was adjusted, tested, and the system
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line up was r_eturned_ to normal:* *All instrUrnents returned to the pr_. op~r. range a$ ~he 1*
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DISCOVERY.
DISCOVERY DESCRIPTION @ *
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ATTACHMENT TO LICENSEE EVENr REPORT 79-027/031-0 COMMONWEALTH EDISON COMPANY (CWE)
DRESDEN UNIT (ILDRS2)
DOCKET # 050-237 During startup on Unit *2.at 1918 on May 2, 1979, the main turbine tripped on high water level. It was discovered that a packing leak existed on the isolation valve for the local pressure indi~atiori, PS-263-60B.
The "B" reference leg drained to an abnormally low level through*
the packing leak.
This resulted in an: upscale reading on all the yarways on instrument rack 2206.
The "B" reference leg _root valve was shut to isolate the leak which isolated the following components:. PS-263-SSC, SSD, LIS-263-58A, 58B, 72B, 72D, and LITS-263-59B.
A control systems.
technician locally isolated PI-263-60B (local pressure indica.tion) and PS-263-SSD (reactor.high pressure scram) via their comm9n,.. SeQSing line
The "B" reference leg root valve was then opened and the reference leg filled.
Since. Tech. *Spec *. Table 3.1. _l requires two in-**.,,;*
strument channels per trip system, an orderly. reactor shutdqwn was begun immediately.
The packing was tightened-and subjected to a hydro of 1000 psi.
No leaks were discovered.
The isolation valves. for PS-263-SSD and PI-263-60B were opened and the common sensing line root valve was opened, returning the system to normal.
This. event was* of minimal safety significance, since one -instrument channel per trip system was still capable of performing its intended function as. designed.
This was the first.occurrence of this type on Unit. 2.
There was no* ~ffect on public health or safety.
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e DEVIATION REPORT DVR NO.
Commonwealth Edison
,ST.~L* l.!NIT YEAR NO.
D 2 48 PART 1( TITLE OF DEVIATION OCCURRED 5-2-29
] 9J8 "B II Yarway level instrumentation r.eading upscale
.DATE TIME SYSTEM AFFECTED 263 PLANT CQNDITIONS TESTING Reactor Yessel. P~e$sure*~-
C. Rx pr. @)
D OCJ Startu*p TnC: t-*,.-:11mi>nt-c::--
MODE PWR(MWT) '585 psi
. LOAD(MWE) 0 YES NO
DESCRIPTION OF EVENT
At 1918 hrs cm 5-2-79 the main turbine tripped on high water level. It was discovered that a packing leak on the local pressure indicator 263-60B isolation valve had caused the. 'B' yarway reference leg to drain.
This caused yarway level instruments 263-59B, 263-58B, 263-72B, {ov.er)1;(!
DESCRIPTION OF GAUSE Packing leak on isolation valve to Pl-2_63-60B OTHER APPLICABLE INFORMATION When leak was isolated, level indication came back on scale as the condensing chamber began.
filling the reference leg.
EQUIPMENT IB:::J YES DR NO.
FAILURE ONO N/A WR NO.
3218 PART 2 I OPERATING ENGINEERS COMMENTS W. Pietryga 5-2-79 RESPONSIBLE SUP~RVISOR DATE Initiated insertion of Control Rods and completed insertion of all control rods within four hours.
Redundant ECCS and Rx scram instrumentation would have functioned* a.'s designed.
,
- 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
D [X]
(il 14 DAY 10CFR21 YES YES D
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D NOTIFICATION D
.NOD 30 DAY NO I
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6.6.B.2.b REPORTABLE CCCURHENCE ACTION ITEM NQ.
NUMBER
~. 7-9-27-..03L-0 N/A 24-HOUR NRC NOTIFICATION (Courtesy)
~TPH J. Barker.
- 5/3(79 REGION I I I DATE TIME
REGION I I I & DOL CATE TIM_E RESPONSIBLE COMPANY OFFICER INFORMED OF 10CFR21 ND ONS AND THEIR REPORT TO C
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REVIEW AND ACCEPTANCE BY iTATLON REVIE~*
AS REQUIRED DATE PROMPT ON-SITE NOTIFICATION
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B. B.
Stephenson 5/11/79 TITLE DATE*
TIME.
N/A
- - TITLE DATE TIME PROMPT OFF-SITE NOTIFICATION F. Palmer 5/11/79 12:20 Tl TLE J. R. Gilliom 5f1Yh9
~... ll ~~cr TITLE
.DATE TIME.
TIME
-.y
DESCRIPTION OF EVENT
and *263-58A to fail high.
The leak was isolated which also isolated pressure switch 263-SSD (Rx High Pressure Scram~ ~eactor shutdown commenced at 2103 as required by Technical Specifications.
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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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