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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20012E9151990-03-15015 March 1990 Ro:On 900118,Unit 2 Experienced Unanticipated ECCS Actuation During Testing Activities.Caused by 2 of 3 Channel Coincidence of Low Steam Line Pressure Due to One Channel in Test & Second Channel Spiking Low.W/O Stated LER 90-001 1990-03-15
[Table view] Category:LER)
MONTHYEARML20012E9151990-03-15015 March 1990 Ro:On 900118,Unit 2 Experienced Unanticipated ECCS Actuation During Testing Activities.Caused by 2 of 3 Channel Coincidence of Low Steam Line Pressure Due to One Channel in Test & Second Channel Spiking Low.W/O Stated LER 90-001 1990-03-15
[Table view] Category:TEXT-SAFETY REPORT
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m em n 1/ ' Bcron Nuclear Station' D(L9 l I
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i j March 15, 1990-4l 4' i j
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[ LTR BYRON 90-0282 ,
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FILE: 2.7.400 ]
1 Mr. A. Bert Davis 3, U. S. Nuclear Regulatory Commission {
! Regional Administrator l I' Region III
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, 799 Roosevelt Road i Glen Ellyn, IL 60137 :
SUBJECT Dyron Unit 2, ECCS Actuation Report
- i. .
Dear Mr. Davist -
L This letter is submitted to document the circumstances of a recent Emergency Core. Cooling System (ECCS) actuation at Byron Station Unit 2. r On January 10, 1990,'Dyron Unit 2 experienced an unanticipated ECCS actuation during testing' activities. The actuation was initiated by a 2 of L 3 channel I coincidence of low steam line pressure due to one channel in test and a second {
channel spiking low. At no time did conditions in the plant exist.which would t require mitigation by the ECCS. At the time of the event, the unit was in !
Mode 1, Power Operation, at 99% reactor power. The attached report, LER [
90-001,' describes the circumstances of the ECCS actuation in detail.
- l To dat.e, Byron Unit 2 has experienced four (4) unplenned injections by the ECCS. ..In this occurrence, it is estimated that 3150 gallons of borated water ,
were injected into the. Reactor Coolant System through the cold leg injection :
flowpath of the Charging / Safety injection Pumps. Given a design parameter of '
110 actuation cycles for life-of-plant, Dyron Unit 2 is well below the ;
y report.able nozzle usage factor of 0.70. .;
This report is submitted in accordance with Technical Specifications 6.9.2 and j 3.5.2. ,
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( f(xA.- --v R. Plenlewics
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Byron Nuclear Power Station HP/SM/bf' ,
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