05000302/LER-1997-028, Forwards LER 97-028-00,discussing Potential for Nuclear Svcs Closed CCW & Decay Heat Closed Cycle Cooling Sys Flow Element Accuracy Uncertainty to Be Greater than Assumed Due to Design Error

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Forwards LER 97-028-00,discussing Potential for Nuclear Svcs Closed CCW & Decay Heat Closed Cycle Cooling Sys Flow Element Accuracy Uncertainty to Be Greater than Assumed Due to Design Error
ML20211H153
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 10/02/1997
From: Rencheck M
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20211H160 List:
References
3F1097-10, NUDOCS 9710060263
Download: ML20211H153 (1)


LER-2097-028, Forwards LER 97-028-00,discussing Potential for Nuclear Svcs Closed CCW & Decay Heat Closed Cycle Cooling Sys Flow Element Accuracy Uncertainty to Be Greater than Assumed Due to Design Error
Event date:
Report date:
3022097028R00 - NRC Website

text

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October 2 --, 1997 - ,

,g; 3F1097-10 U.S. Nuclear Regulatory Commission

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Subject:

LICENSEE EVENT REPORT (LER)_50-302/97-028 00 Dear Sir.

Please find the encbsea Licensee Event Report (LER) 50-302/97-028-00. This LER discusses _ the potential for Nuclear Services Closed Cycle Cooling Water and Decay Heat Closed Cycle Cooling Systems flow element accuracy uncertainty to be greater than assumed due to a design error, This report is submitted pursuant to 10 CFR 50,73.

Sincerely, M. W, kb encheck1

-._ Director -

, Nuclear Engineering and Projects.

MWR/pmp Enclosures

'xc; Regional Administrator, Region 11

' Senior Resident inspector NPR Project Manager gp 9710060263 971002 ra ao" o'o sga" It!smultillglili  ;

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