MONTHYEARML20134K3131997-02-11011 February 1997
Forwards RAI Re Revised SG Tube Rupture Analysis for Mentioned Plants
ML20141H3531997-05-20020 May 1997
Forwards RAI Re Revised Steam Generator Tube Rupture Analysis for Byron Station,Units 1 & 2 & Braidwood Station Units 1 & 2
ML20141H3991997-07-18018 July 1997
Forwards RAI Re Revised SG Tube Rupture Analysis for Plants, Units 1 & 2
ML20217B3901997-09-23023 September 1997
Forwards Questions Re Ceco Submittal of Revised SG Tube Rupture Analysis for Byron,Unit 1 & Braidwood,Unit 1
ML20217G5091997-10-0303 October 1997
Forwards RAI Re Revised SG Tube Rupture Analysis Removal of SG Repair Methodologies & Restoration of Previous Dose Equivalent Iodine Limits for Mentioned Plants
ML20199G2061998-01-28028 January 1998
Forwards Safety Evaluation Re Revised SG Tube Rupture Analysis
ML20216C6001998-03-11011 March 1998
Forwards Corrected Pages Re SG Tube Rupture Analysis,To Be Inserted Into SE
ML20216B6481998-05-12012 May 1998
Requests Addl Info Re Revised Steam Generator Tube Rupture Analysis for Byron & Braidwood Stations,Units 1 & 2.Response Requested within 30 Days of Date of Ltr
ML20207B6361999-05-25025 May 1999
Forwards SE Accepting Revised SG Tube Rupture (SGTR) Analysis for Bryon & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station
ML0212100692002-04-18018 April 2002
Duke Energy Corp. (DEC) McGuire Nuclear Station Units 1 & 2, Proposed Technical Specification on (TS) Amendments TS 3.7.15 - Spent Fuel Assembly Storage, TS 4.3 - Fuel Storage
1997-09-23
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