ML20198G411

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Provides Supplemental Response to GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations. Revised Schedule to Complete Detailed Insp Plans Will Be Provided by Nuclear Energy Inst
ML20198G411
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 01/02/1998
From: Woodard J
SOUTHERN NUCLEAR OPERATING CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-97-01, GL-97-1, LCV-1015-B, NUDOCS 9801130028
Download: ML20198G411 (2)


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VOGTLE ELECTRIC GENERATin J PLANT SUPPLEMChrrAL RESPONSE TO GENERIC LETTER 97 01 DEGRADATION OF CONTROL ROD DRIVE MECllANISM NOZZLE AND OTilER VESSELCLOSUREllEAD PENETRATIONS 1hc NRC issued Generic letter (GL) 97 01, Degradation of Control Rod Drive Mechanism Nouk and other Vessel Closure ficad Penetrations, dated April 1, 5497. By letters dated April 28,1997, and July 24,1997, Southem Nuclear Operating Company (SNC) prosided the Vogtle Electric donerating Plant (VEGP) 30 day a.d 120 day responses, respectively, O GL97 01.

As stated in the 1204ay response to GL97-01, SNC is pursuing a solution to the ViiP issue in cordunction with the Nuclear Energy Institute (NEI), the PWR owners groups, and the Electric Power Renarch Institute (EPRI) who are compiling information on the estimated cperating time from January 1,1997, needed to initiate and propagate a crack 75% through wall in a vessel pcoctratior, for all operating PWRs in the United States. Although originr411y scheduled to be completed by the end of 1997, NEl has advised that the detailed inspection plans for the industry will not be completed as originally scheduled. A revised schodule wi'.1 be presided by NEl.

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