05000382/LER-1997-016, Forwards LER 97-016-01 Which Repts Similar Potential as That Contained in LER 97-016-00,that Existed for SG Differential Pressure Instrumentation Associated W/Efas

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Forwards LER 97-016-01 Which Repts Similar Potential as That Contained in LER 97-016-00,that Existed for SG Differential Pressure Instrumentation Associated W/Efas
ML20211P034
Person / Time
Site: Waterford Entergy icon.png
Issue date: 10/16/1997
From: Ewing E
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20211P039 List:
References
W3F1-97-0243, W3F1-97-243, NUDOCS 9710200036
Download: ML20211P034 (2)


LER-2097-016, Forwards LER 97-016-01 Which Repts Similar Potential as That Contained in LER 97-016-00,that Existed for SG Differential Pressure Instrumentation Associated W/Efas
Event date:
Report date:
3822097016R00 - NRC Website

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a;eu s newas was W3F1-97-0243 A4.05 PR October 16,1997 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 4

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 Reporting of Licensee Event Report Gentlemen:

Attached is Licensee Event Report (LER) Number 97-016-01 for Waterford 3 Steam Electric Station. On June 16,1997, Waterford 3 reported in LER 97-016-00 by Letter W3F1-97-0135 a condition involving the potential for premature initiation of the Recirculation Actuation Signalif a Loss of Coolant Accident had occurred coincidental with one channel of Refueling Water Storage Pool (RWSP) level instrumentation in the tripped condition, with failure of another channel of RWSP levelinstrumentation.

This revision of the LER reports a similar potential that existed for Steam Generator Differential Pressure Instrumentation (SGPDI) associated with the Emergency Feedwater Actuation Signal. This circumstance was discovered during a subsequent review of generic implications of the aforementioned condition.

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Reporting of Licensee Event Report (LER 97-016-01)

W3F1-97-0243 Page 2 October 16,1997 With one channel in a tripped condition, combined with a failure of another channel of SGDPI and a Main Steam Line Break or Feedwater Line Break, the automatic isolation of a faulted steam generator from emergency feedwater would not have occurred as assumed by the Waterford 3 safety analysis. This condition is being repor1ed in accordance with 10CFR50.73(a)(2)(li)(B).

Very truly yours, E. . Ewin Director, Nuclear Safety & Regulatory Affairs ECE/ PRS /ssf

Attachment:

LER-97-016-01 cc: E.W. Merschoff, NRC Region IV C.P. Patel, NRC-NRR A.L. Garibaldi J.T. Wheelock - INPO Records Center J. Smith N.S. Reynolds NRC Resident Inspectors Office Administrator - LRPD

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