05000382/LER-1998-019, Forwards LER 98-019-01,IAW 10CFR50.73(a)(2)(ii). LER 98-019-00,discussed.Refs to Feedwater Valves Have Been Deleted in Revised LER

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Forwards LER 98-019-01,IAW 10CFR50.73(a)(2)(ii). LER 98-019-00,discussed.Refs to Feedwater Valves Have Been Deleted in Revised LER
ML20196J086
Person / Time
Site: Waterford Entergy icon.png
Issue date: 12/08/1998
From: Ewing E
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20196J089 List:
References
W3F1-98-0189, W3F1-98-189, NUDOCS 9812090258
Download: ML20196J086 (2)


LER-2098-019, Forwards LER 98-019-01,IAW 10CFR50.73(a)(2)(ii). LER 98-019-00,discussed.Refs to Feedwater Valves Have Been Deleted in Revised LER
Event date:
Report date:
3822098019R00 - NRC Website

text

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Ente gy Operatiero. inc. '

Killona. LA 70066 Tel 504 739 6242

- . Early C. Ewing, m Safety & Regulatory AHans Waterford 3 i W3F1-98-0189 l A4.05 PR l l

December 8,1998 j 4

U.S. Nuclear Regulatory Commission i Attn: Document Control Desk Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 i License No. NPF-38  !

Reporting of Licensee Event Report  ;

Gentlemen: l Entergy is hereby submitting revised Licensee Event Report (LER) 98-019-01 (attached) for Waterford Steam Electric Station Unit 3. In LER 98-019-00 dated October 20,1998, it was reported that specific Feedwater valves with ASCO  !

solenoids were continuously energized and susceptible to the same failure mode as the three Containment isolation valves that failed during testing. Based on this initial association, the corrective actions involving the failed solenoids also included the l Feedwater valve solenoids. Further review, however, determined that the solenoids i for the Feedwater valves are not continuously energized, and are not susceptible to I the same failure mode as the failed solenoids on the containment isolation valves. /

Therefore corrective action on the Feedwater valve solenoids are not necessary to prevent recurrence of the reportable event. References to the Feedwater valves / ,

J1}

have been deleted in the revised LER. This condition was reported pursuant to 10 CFR 50.73(a)(2)(ii).

Very truly yours,

(

l 9812090258 981200 E.C. Ewing PDR ADOCK 05000302 s N Director, Nuclear Safety & Regulatory Affairs

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ECE/ DAY /rtk Attachment

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. Reporting of Licensee Event Report W3F1-98-0189 - 1 Page 2  ;

December 8,1998. ,

cc: E.W. Merschoff (NRC Region IV) i C.P. Patel (NRC-NRR)  !

A.L. Garibaldi . i P. Lewis -INPO Records Center 3

J. Smith N.S. Reynolds NRC Resident inspectors Office Administrator - LRPD 1

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