LER-1980-032, /01T-0:on 801116,HPCI Sys Declared Inoperable. Caused by Oil Leak on HPCI Stop Valve Cover.Cover Replaced & Tested |
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8 EVENT OESCRIPTION AND PROB ABLE CONSEQUENCES h While demonstrating HPCI operability due to the RCIC system being inoperable, an l
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oil leak was discovered on the HPCI stop valve cover.
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g o,,, g inoperable. An orderly shutdown was initiated in accordance with Technical l
Specification 3.5.C.3 In addition, Automatic Blowdown, LPCI and Core Spray were g
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33 34 JS 36 23 40 41 42 43 44 47 CAUSE DESCRIPTION AND CCF.RECTIVE ACTIONS h li6cll Uoon exa.nination of the control valve cover. a pinhole leak was discovered on the l
litJi cover s outer cast surface and the interior machined surf ace.
An orderly shut-1 t
,, ge tl down was initiated. The cover was replaced with the cover from HPCI on Unit I which l 1,#3) l 1s currently in a refuel outage. The HPCI system was returned to service before the l l
24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limitation and was tested satisfactorily.
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NA H0YE 30N' 4-224i ' ext *174 a C Tubbs PHONE:
NAVE OF PREPARER
1.
LER NUMBER:
80-32/0lT 11.
LICENSEE NAME: Commonwealth Edison Company quad-Cities Nuclear Power Station Ill.
FACILITY NAX: Unit Two IV.
DOCKET NUMBER: 050-265 V.
EVENT DESCRIPTION
On November 16, 1980, the unit was being operated at 823 MWe.
At 0300, during the routine monthly performance of QOS 1300-3, "RCIC Motor Operated Valve Operability Test", it was discovered that M0-2-1301-49 would not open from the Control Room.
Per Technical Specification 3.5.E.2. HPCI was started to demonstrate its operability to allow con-tinued operations of the unit.
During the test, annunciator 902-3-G-10, HPCI Hi/Lo Oil Level, alarmed.
Upon personnel arriving at the HPCI turbine, it was discovered that the HPCI stop valve cover was leaking oil, and HPCI was subsequently declared inoperable.
Since the criteria of Technical Specification 3.5.E.2. could not be met, an orderly shutdown of the reactor was initiated. There are no previous instances of this mode of HPCI failure. At 1020 and 1145 RCIC and HPCI were respectively restored to service and the shutdown was terminated at 1340 on November 16.
VI.
PROBABLE CONSEQUENCES OF THE OCCURRENCE:
Per Technical Specification 3.5.E.3., continued reactor operation is not allowed with both the RCIC and HPCI systems inoperable.
In accordance with 3 5.E.3. an orderly shutdown was initiated in order to reduce pressure to less than 90 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. At all times the unit was operated in compliance with the Technical Specifications.
In addition,.1ormal feedwater, Automatic Blowdown, LPCI, and Core Spray were available.
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CAUSE
Upon examir.ation of the defective valve cover a pinhole leak was discovered.
This was located between the outer cast surface, and an interior machined surface.
It was postulated that the pinhole began as a defect in the casting process and became worse under pressure. The stop valve is an in-tegral part of the HPCI turbine supplied by General Electric Company.
Vill.
CORRECTIVE ACTION
The valve cover was replaced by an identical part from Unit I which is shutdown for refueling. The defective cover will be weld repaired and installed on Unit I before its startup. QOS 2300-2, HPCI Pump Operability, was completed to demonstrate the operability of Unit 2 HPCI.
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| 05000265/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000254/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000254/LER-1980-001-03, /03L-0:on 800111,while Performing Suppression Chamber to Drywell Pressure Separation Test,Differential Pressure Transmitter 1-8741-51 Was Not Indicating Properly. Caused by Personnel Error Due to Drawing Error | /03L-0:on 800111,while Performing Suppression Chamber to Drywell Pressure Separation Test,Differential Pressure Transmitter 1-8741-51 Was Not Indicating Properly. 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