ML20069K523
| ML20069K523 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/28/1983 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| REF-SSINS-6820 IEB-83-04, IEB-83-4, LIC-83-076, LIC-83-76, NUDOCS 8304260382 | |
| Download: ML20069K523 (4) | |
Text
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Omaha Public Power District 1623 HARNEY a OMAHA, NEBRASMA 68102 e TELEPHONE 536-4000 AREA CODE 402 March 28, 1983 LIC-83-076
[ h_ !~l1\\V/_[$3, Mr. J. T. Collins, Administrator
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U. S. Nuclear Regulatory Commission JFRI S83 "
Region IV j
611 Ryan Plaza Drive, Suite 1000 L
Arlington, Texas 76011
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Reference:
Docket No. 50-285
Dear Mr. Collins:
IE Bulletin 83-04 Failure of the Undervoltage Trip Function of Reactor Trip Breakers Attached is Omaha Public Power District's response to the five (5) items requested in IE Bulletin 83-04.
It should be noted that the Fort Calhoun Station automatic trip function from the RPS does not use circuit breakers as the trip mechanism, but rather uses contactors to interrupt power to the clutch power supplies.
The only functicn of the circuit breaker is to protect the wiring from overcurrent and pro-vide one of the two manual trips via the undervoltage trip units associated with each breaker.
Sinco ely,
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l W.
C.
ones Divis on Manager ProduEtion Operations l
l WCJ/TLP:jmm Attachment cc:
U.
S. Nuclear Regulatory Commission og OmA Document Control Desk No' Washington, D.C.
20555 88 mn LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
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ns Washington, D.C.
20036 L
oo Mr.
L.
A.
Yandell, NRC
$g Senior Resident Inspector go Mr.
E. G. Tourigny, NRC Project Manager
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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Omaha Public Power District
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Docket No. 50-285 (Fort Calhoun Station,
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Unit No. 1)
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. being duly sworn, hereby deposes and says that he is Division Manager - Production Operations of Omaha Public Power District; that he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached response to IE Bulletin 83-04; that he is familiar with the content thereof; and that.the matters set forth therein are true and correct to the best of his knowledge, information and belief.
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1 W. C.lJones Division Manager Production Operations STATE OP NEBRASKA)) ss COUNTY OF DOUGLAS) i Subscribed and sworn to before me, a Notary Public in and for the State of Nebraska on this SVra day of March,
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' Notary' Public
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J.T. GLEASON f
Mr Coma taa July 3,1906
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e Attachment RESPONSE TO IE BULLETIN 83-04 Item 1 Perform surveillance tests of undervoltage trip function independent of the shunt trip function within 5 days of receipt of IE Bulletin 83-04 unless equivalent testing has been performed within-10 days.
Those plants currently shutdown should complete this item before resuming operation or within 10 days, whichever is sooner.
Those plants for which on-line testability is not provided should complete this item at the next plant shutdown if currently operating.
Identify results of this testing.
Plants without on-line testability should report the date and results of the most recent test.
Response
The undervoltage trip function was tested per ST-RPS-10 on March 21, 1983, with satisfactory results.
Item 2 Review the maintenance program for conformance to the latest manufacturer's recommendation, including frequency and lubrication.
Verify actual implementation of the program.
If maintenance does not conform, initiate such naintenance within 5 days of receipt of IE Bulletin 83-04 or provide an alternate maintenance program.
Repeat the test required in Item 1 prior to declaring the breaker OPERABLE.
Identify conformance of the maintenance program to manu-facturer's recommendation and describe results of mainte-nance performed directly as a result of IB Bulletin 83-04 in response to Item 2.
Responso A maintenance procedure has been written which includes the manufacturer's recommendations for preventative maintenance on the clutch power supply circuit breakers.
This procedure will be performed prior to reactor start-up following the refueling outage presently in progress.
These circuit breakers will also be cycled several times on a periodic basis (each refueling) as recommended by the manufacturer by use of ST-RPS-10.
In addition, a maintenance procedure has been written and will be performed prior to reactor start-up on the "M" contactors which are in the reactor protective systen clutch power supply circuit.
. Item 3 Provide a statement that provisions are in place to notify licensed operators of the Salem and San Onofre events and bring to their attention appropriate failure-to-trip emergency procedures upon their arrival on-shift.-
Response
All licensed operators have been notified of the Salem and San Onofre events and have been given training on the appropriate failure-to-trip emergency procedures upon their arrival on-shift.
Item 4 Provide a description of all RPS breaker malfunctions not previously reported to the NRC.
Response
There are none.
Item 5 Verify that procurement, testing, and maintenance activities treat the RPS breaker and UV devices as safety related.
Report the results of this verification to the NRC.
Response
-The RPS breakers were purchased from Combustion Engineering as original equipment with the reactor protective system.
Since initial start-up, there have been no parts purchased for RPS breakers.
The entire system was purchased under standards that existed prior to 1973.
Procurement, testing, and naintenance activities treat the reactor protective system, up to and including the clutch power supplies, as safety related.