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CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE

10 CFR 73.55 +  and 10 CFR 50 +

05000320  +  and 00320  +

Snyder B +  and Office of Nuclear Reactor Regulation +

ML20003J254 +, ML20003J254 +, ML20003J254 +, ML20003J254 +, ML20003J254 +, ML20003J254 +, ML20003J254 +, ML20003J254 +, ML20003J254 +, ML20003J254 +, ML20003J254 +  and ML20003J254 +

Westinghouse +  and Target Rock +

NRC Bulletin 80-04 +, NRC Bulletin 80-24 +, NRC Bulletin 80-14 +, NRC Bulletin 80-10 +, NRC Bulletin 80-11 +, NRC Bulletin 80-13 +, NRC Bulletin 80-07 +, NRC Bulletin 80-20 +, NRC Bulletin 80-25 +, NRC Bulletin 80-01 +, NRC Bulletin 80-15 +, NRC Bulletin 80-18 +, NRC Bulletin 80-21 +, NRC Bulletin 80-12 +, NRC Bulletin 80-17 +, NRC Bulletin 80-03 +, NRC Bulletin 80-09 +, NRC Bulletin 80-02 +, NRC Bulletin 80-23 +, NRC Bulletin 80-08 +, NRC Bulletin 80-19 +, NRC Bulletin 80-16 +, NRC Bulletin 80-05 +, NRC Bulletin 79-06 +, NRC Bulletin 80-86 +  and NRC Bulletin 79-08, Events Relevant to Boiling Water Power Reactors Identified During Three Mile Island Incident +

NUREG/CR-0727 +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0473, Forwards Draft,Rev 3 to NUREG-0472, Std Radiological Effluent Controls for Pwrs, Containing Draft Guidance for Radiological Effluent Tech Specs/Odcm Commitments,Per Generic Ltr 89-01 +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0626, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +, NUREG-0645, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +, NUREG/CR-0660, Forwards Sample Ltr to Applicants,Cp Holders & Licensees of LWRs Transmitting NUREG/CR-0660 Enhancement of Onsite Emergency Diesel Generator Reliability +, NUREG-0576, Forwards NUREG-0576, Nuclear Power Reactor Security Personnel Training & Qualification Plan Reviewer Workbook +  and NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +

Pennsylvania +  and Arkansas +

Feedwater +, Emergency Diesel Generator +, Auxiliary Feedwater +, Core Spray +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +  and Control Rod +

Hovey G +  and FirstEnergy +

Scram Discharge Volume +, Loss of Offsite Power +, Control of Heavy Loads +, Fuel cladding +  and Fire Protection Program +