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CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE

10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.44 +, 10 CFR 50.62 +  and 10 CFR 50.54#f +

SECY 88-272 +, SECY 88-260 +, SECY 82-465 +, SECY 81-687 +, SECY 84-119 +, SECY 89-172 +, SECY 96-97 +, SECY 86-07 +, SECY 08-260 +, TXX-88306 +, TXX-89200 +, TXX-89134 +, TXX-6161 +, TXX 89169 +, TXX-4494, Forwards Response to Generic Ltr 85-02, Staff Recommended Actions Stemming from NRC Integrated Program for Resolution of Unresolved Safety Issues Re Steam Generator Tube Integrity +, TXX-4303, Informs That Comparison Demonstrating Applicability of Diablo Canyon Natural Circulation/Boron Mixing Prototype Test Results to Facility Will Be Provided.Test Will Be Performed If Results Unsatisfactory +, TXX-4275, Informs That Steam Generator Tube Rupture Reevaluation Will Include Calculations to Determine Margin to Overfill & Equilibrium Breakflow Showing Time to Overfill Is Greater than Time to Equalization,Per NRC 840409 Request +, TXX-4118, Requests Exemption from Provisions of GDC 4 Requiring Protection of Structure,Sys & Components Against Certain Dynamic Effects Associated W/Postulated Breaks in RCS Primary Loop,Per Generic Ltr 84-04 +, TXX 4426 +, TXX-89813 +, TXX 4046 +, TXX 4069 +, TXX 4158 +, TXX 4159 +, TXX 4197 +, TXX 4515 +, TXX 6086 +, TXX 6162 +, TXX 3072 +, TXX 3364 +...

05000445  +, 05000446  +, 00445  +  and 00446  +

Luminant +, William Cahill +  and Beck J +

NRC Generic Letter 83-42, Clarification to GL 81-07 Regarding Response to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants" +, NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +, NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants" +, NRC Generic Letter 95-02, Use of Numarc/epri Report TR-102348, "Guideline on Licensing Digital Upgrades," in Determining the Acceptability of Performing Analog-to-Digital Replacements under 10 CFR 50.59 +, NRC Generic Letter 05-02 +  and NRC Generic Letter 85-82 +

ML19332D383 +, ML19332D383 +, ML19332D383 +, ML19332D383 +, ML19332D383 +, ML19332D383 +, ML19332D383 +, ML19332D383 +, ML19332D383 +, ML19332D383 +  and ML19332D383 +

SAP +, CP +  and OSP-NRC +

SECY 88-272 +, SECY 88-260 +, SECY 82-465 +, SECY 81-687 +, SECY 84-119 +, SECY 89-172 +, SECY 96-97 +, SECY 86-07 +  and SECY 08-260 +

44W-PWR +, 8EG-0588 +  and 8I-03 +

Washington +  and Texas +

TXX-88306 +, TXX-89200 +, TXX-89134 +, TXX-6161 +, TXX 89169 +, TXX-4494, Forwards Response to Generic Ltr 85-02, Staff Recommended Actions Stemming from NRC Integrated Program for Resolution of Unresolved Safety Issues Re Steam Generator Tube Integrity +, TXX-4303, Informs That Comparison Demonstrating Applicability of Diablo Canyon Natural Circulation/Boron Mixing Prototype Test Results to Facility Will Be Provided.Test Will Be Performed If Results Unsatisfactory +, TXX-4275, Informs That Steam Generator Tube Rupture Reevaluation Will Include Calculations to Determine Margin to Overfill & Equilibrium Breakflow Showing Time to Overfill Is Greater than Time to Equalization,Per NRC 840409 Request +, TXX-4118, Requests Exemption from Provisions of GDC 4 Requiring Protection of Structure,Sys & Components Against Certain Dynamic Effects Associated W/Postulated Breaks in RCS Primary Loop,Per Generic Ltr 84-04 +, TXX 4426 +, TXX-89813 +, TXX 4046 +, TXX 4069 +, TXX 4158 +, TXX 4159 +, TXX 4197 +, TXX 4515 +, TXX 6086 +, TXX 6162 +, TXX 3072 +, TXX 3364 +, TXX 3367 +, TXX 3490 +, TXX 3684 +, TXX 3685 +, TXX 4010 +, TXX 4032 +, TXX 4036 +, TXX 88341 +, TXX 88756 +...