05000265/LER-1980-037-03, /03L-0:on 801207,RHR 2D Pump Inoperable Due to Excessive Leakage of Mechanical Seal.Caused by Normal Wear of O-ring Sealing Surface.Mechanical Seal Replaced.Pump Returned to Svc & Satisfactorily Tested

/03L-0:on 801207,RHR 2D Pump Inoperable Due to Excessive Leakage of Mechanical Seal.Caused by Normal Wear of O-ring Sealing Surface.Mechanical Seal Replaced.Pump Returned to Svc & Satisfactorily Tested

ML19351F631
Person / Time
Site:	Quad Cities
Issue date:	12/29/1980
From:	Mendenhall E COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19351F628	List: 05000265/LER-1980-037, Forwards LER 80-037/03L-0 05000265/LER-1980-037-03, /03L-0:on 801207,RHR 2D Pump Inoperable Due to Excessive Leakage of Mechanical Seal.Caused by Normal Wear of O-ring Sealing Surface.Mechanical Seal Replaced.Pump Returned to Svc & Satisfactorily Tested
References
LER-80-037-03L-03, LER-80-37-3L-3, NUDOCS 8101130605
Download: ML19351F631 (2)

LER-1980-037, /03L-0:on 801207,RHR 2D Pump Inoperable Due to Excessive Leakage of Mechanical Seal.Caused by Normal Wear of O-ring Sealing Surface.Mechanical Seal Replaced.Pump Returned to Svc & Satisfactorily Tested

Event date:
Report date:
2651980037R03 - NRC Website

text

NRC FORL' 366 U.& NUCLEAR REGULATo3Y CoMM1551oM um T

LICENSEE EVENT REPORT

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EVENT DESCRIPTION AND PROSA8LE CONSEQUENCES h I'o'TF1 1 2D RHR pumo was Inoperable due to excessive leakage of the mechanical seal. As I

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The mechanical seal was replaced. The 20 RHR pump was returned to service and i

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LER NUMBER: 80-37/03L-0 11.

LICENSEE NAME: Commonwealth Edison Company Quad-Cities Nuclear Power Station Ill. FACILITY NAME: Unit Two I V'.

DOCKET NUMBER:

050-265 V.

EVENT DESCRIPTION

On December 7, 1980, at 0530, during a routine startup an alarm was received in the Control Room for excessive seal leakage on the 2D RHR pump. The reactor was critical at 1900 and the 20 RHR pump was taken out of service at 2125 to replace the pump's mechanical seal, which was leaking.

VI.

PROBABLE CONSEQUENCES OF THE OCCURRENCE:

Per Technical Specification 3 5.A.4. reactor operation is permissible for 30 days following the date that one RHR pump is made or found inoperable, provided that during the 30 days the remaining active components of the LPCI mode of RHR and containment cooling mode of RHR, all active components of both core spray subsystems, and the Diesel Generator required for operation of such components if no external source of power were available shall all be operable. Action was taken af ter the first Indication of seal failure in the 2D RHR pump to verify that these conditions were satisfied by the performance of procedures QOS 1000-2, 3, 4, 5, QOS 1400-2, 3, and 40S 6600-1. The RHR pumps are sized on the basis of the flow requirements for operation in the LPCI mode, where maximum flow is required. Redundancy is provided in that only three of the four system pumps are required to deliver full capacity LPCI flow. This cor.tinued availability of LPCI and the containment cooling mode of RHR, the availability of normal feedwater, core spray, and the emergency diesel generators for backup to normal auxillary power minimized the safety implications of this equipment failure. The 2D RHR pump was returned to service on December 8, 1980, and verified operable at 2120.

Vll. CAUSE:

The RHR system pumps are equipped with a mechanical, spring loaded compression unit for a shaf t seal. The unit is a type "PT0" DuraSeal manufactured by Durametallic Corporation for Bingham Pump Company.

Excessive leakage resulted from normal wear of the 0-Ring sealing sur-faces. No prev!ous instances of seal failure have been noted for quad-Cities Unit Two.

Vill. CORRECTIVE ACTION:

The mechanical seal was replaced with a new cartridge seal unit of the same type. The pump was back in service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of being taken out of service and was tested satisfactorily.