ML19351F383

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LER 80-032/03L-0:on 801210,primary Heat Tracing Circuits Associated W/Piping Between Boric Acid Pump Discharge & MCV-268 Found Inoperable.Caused by Blown Power Supply Fuses. Fuses Replaced
ML19351F383
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 12/17/1980
From: Mueller B
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19351F348 List:
References
LER-80-032-03L, LER-80-32-3L, NUDOCS 8101120348
Download: ML19351F383 (4)


Text

NRC FOZ1366 U. S. NUCLE AR REGULATORY COMMISSION (7 794 .

LICENSEE EVENT REPORT s /

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7 8 60 61 DOCKET NUM6; R 68 69 EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBA8LE CONSEO JENCES h lo l2l l On 12/10/80, while operating at approximately 75% power, the primary heat tracing l 10 l a I i circuits associated with the piping located between the Boric Acid Pump (Cil-4A) dis- l l o 14 l l charge and one of the isolation valves (IICV-268) to the charging pump suction l log3; l header were found to be inoperable. During the time of the failure, the secondary l lo ls l l heat tracing circuits associated with the aforementioned piping were operable. In l l0 l7l l addition, there were at least two remaining operable flow paths from the concentratedl boric acid tanks to the reactor coolant system as well as a flow path from the SIRWT lO1sl l to the charging pumps as required by Technical Specification 2.2. l SYSTE M CAUSE CAUSE COMP, VALVE CODE CODE SUSCODE COMPON ENT CODE SUSCODE SUSCODE I.O_L9_l l P l C lh [h kj h l C l K l T l B l K l R lh Wh (,zj h 9 10 12 13 18 19 20 7 8 11 SEQUENTIAL OCCURRENCE R E POR'. REVISION EVENT YE -3 REPORT NO. CODE TYPE NO.

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33 34 35 36 37 40 41 42 43 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h g l The failure of the primary heat tracine circuits was caused by blown nower zumiv l

il3, l fuses. The secondary heat tracing circuitry was operable during the time of the i

, , l failure per Technical Specification 2.2(3). The blown fuses were replaced and I gl the primary heat tracing circuits were restored to operability. l l

li 141 l 80 7 8 9 STA S  % POWER OTHER STATUS DIS O Y DISCOVERY DESCRIPTION s

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NAME OF PREPARER

LER No.80-032 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT N0. 1 Safety Analysis During the time in which the piping extending from the Boric Acid Pump (CH-4A) discharge to the isolation valve of one of the two charging pump suction headers, HCV-268, was declared inoperable, at least two redundant flow paths were still operable and capable of supplying re-quired borated water to the reator if necessary. Several alternate and redundant flow paths consisted of 1) the charging pumps taking suction from the Boric Acid tanks via gravity feed, 2) the charging pumps taking suction from the SIRWT (Safety Injection Refueling Water Tank), and 3) the safety injection pumps taking suction from the SIRWT and lastly the flow path from the redundant Boric Acid pump CH-48 to the charging pump suction.

The lowest temperature recorded on the piping was above the temp-erature at which the required concentration of Boric Aicd would have solidified. This temperature was held for only a minimal time as the entire system returned to normal temperature within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of repair.

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.P g LER No.80-032 Omaha Public Power District Fort Calhoun Station Unit No. 1 Docket No. 05000285 ATTACHMENT NO. 2 Corrective Action Upon discovery of de-energized primary heat tracing circuits per-taining to the piping in question, the blown fuses were replaced and the system was returned to normal temperature within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

At the time of the heat tracing circuit failures, circuits P-69, P-28, P-33, S-33, and P-48 were found to be drawing higher-than-normal amperage. It is postulated that the excessive current draw was due to wet pipe insulation coupled with SCR potentiometers operating slightly out of adjustment. All applicable heat tracing circuits were re-adjusted to attain desired current ead verify proper operability. The heat tracing system will contir.ue to be visually monitored by the Operations staff in order to more closely moni".or the operability of the system.

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4 LER No.80-032 i' Omaha Public Power District Fort Calhoun Station Unit No.1 j Docket No. 05000285 i

ATTACHMENT N0. 3 j

< Failure Data l This is the first failure of this type at the Fort Calhoun Station.

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