ML20011D896

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Forwards Corrected LER 89-020-00,revising Event & Rept Date to 891012 & 1122,respectively
ML20011D896
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 12/11/1989
From: Morris K
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-89-1120, NUDOCS 9001020267
Download: ML20011D896 (2)


Text

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Omaha Public Power District  !

1623 Harney Omaha. Nebraska 68102 2247 402/536 4000 l

December 11, 1989 .

LIC-89-ll20  !

e U. S. Nuclear Regulatory Commission Attn: Document Control Desk  :

Mail Station PI-137 Washington, DC 20555

References:

1. Docket No. 50 286
2. Licensee Event Report 89 020, November 22, 1989 Gentlemen:

SUBJECT:

Licensee Event Report 89-020 for the Fort Calhoun Station My letter of November 22, 1989 submitted Licensee Event Report 89 020.

Typograiphical errors resulted in the incorrect Event Date and Report Date appearing in Section (5) of the NRC Form 366 (page 1 of the report). The actual report date was November 22, 1989 and as noted in the report text, the actual event date was October 12, 1989. Attached please find a corrected version of this page for inclusion in your copy of this report. Please note that all other information in the original su)mittal remains unchan9ed. We apologize for any confusion which may have resulted from this error, and will attempt in the future to better ensure accuracy in these submittals.

If you should have any questions, please contact me.

Sincerely, K .

'f rris Division Manager Nuclear Operations KJM/pjc Attachment c: R. D. Martin, NRC Regional Administrator A. Bournia, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector INPO Records Center American Nuclear Insurers e 9001020267 891211 ,

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On October 12,1989, at 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br /> Fort Calhoun Station Unit I was operating at 99% power in Mode 1. Operations personnel determined that 2 of 4 Component Cooling Water (CCW) heat exchangers were simultaneously inoperable for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in violation of Technical Specification 2.3. Investigation revealed that 'A' CCW heat exchanger was not completely returned to service on October 5, leaving the CCW inlet and outlet valves HCV-489A and B in an inoperable condition unknown to Operations. This was due to inadequate controls over proper return to service of equipment; these controls did not prevent or mitigate inappropriate actions by the Operations personnel involved. Immediate corrective action was to return the 'A' CCW heat exchanger to operability. The Operator training and qualification program will be enhanced. Appropriate equipment configuration administrative controls will be evaluated and improved as necessary. This report is made pursuant to 10 CFR 50.73(a)2(i)(B) and (v)(B).

Il NRC f.,in att .6491

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