ML20079J378

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Provides Status of NUREG-0737,Item II.B.3, Post-Accident Sampling Sys. Schedule Revised to Factor in Need for RCS Operation.New Schedule for Operation Projected 3 Months Following End of Refueling Outage
ML20079J378
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 12/17/1982
From: William Jones
OMAHA PUBLIC POWER DISTRICT
To: Clark R
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM NUDOCS 8212280197
Download: ML20079J378 (2)


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4 Omaha Public Power District 1623 HARNEY a OMAHA, NEBRASKA 68102 s TELEPHONE 536 4000 AREA CODE 402 Deemnber 17, 1982 LiC-82-407 Mr. Robert A. Clark, Chief U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch No. 3 Washington, D.C.

20555

Reference:

Docket No. 50-285

Dear Mr. Clark:

Status of NUREG-0737, Item II.B.3 Post Accident Sampling System Omaha Public Power District's letter dated December 1,1982 indi-cated that the District expected the subject system to be operational by the end of the present refueling outage.

Delays in placing the system in o,neration had occurred as the result of problems that were identified

.7 the system during the final testing phase.

At the time the December 1, 1982 letter was written, the main concern was a potential problem with the software that automatically operates the system. Upon solving the software problem, the District again attempted to draw and analyze a sample, at which time the system still exhibited a problem in drawing a representative sample.

It appears that the problem is related to the driving head created by the differential pressure between the post accident sampling system and the volume control tank.

However, before verifying the actual problem, the Fort Calhoun Station tripped as a result of turbine problems and has subsequently commenced its refueling outage approximately one month earlier than originally planned.

In order to complete troubleshooting of the system. the reactor coolant system must be at normal operating pressure. Accordingly, the District is revising its schedule for placing the system in operation to factor in the need for reactor coolant system operation.

We will be unable to recommence our troubleshooting on the system until after the refueling outage is completed.

Therefore, our new projected schedule for placing the system in operation is three months following the end of the refueling outage presently in progress.

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Mr. R:bert A. Clark LIC-82-407 Page Two The District will also continue to resolve equipment problems that have been identified in calibrating the on-line pH meter and operational problems with the ionchromatograph, which is to be used for on-line boron and chloride analyses.

Sincerely, W. C. / Cones Divisl6nManager Production Operations WCJ/TLP:jmm cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.

Washington, D.C.

20036 1

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