Browse wiki

CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC

ANSI N13.1-1969 +  and ANSI N13.1 +

Iodine +, Hydrogen +, Radon +, Lead +, Aluminum +, Silicon +  and Tantalum +

10 CFR 50 +  and 10 CFR 50.4752 +

SECY-81-437 +  and L 10 +

05000266  +, 05000301  +, 00266  +  and 00301  +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

WEC Energy Group +  and Burstein S +

ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +, ML20010G951 +  and ML20010G951 +

Cs-137 +, Sr-90 +, Y-90 +  and I-131 +

IR 05000266/1981010 +, ML20009E222 +, IR 05000301/1981009 +, ML20004C797 +  and ML20037D689 +

Westinghouse +, Foxboro +  and Target Rock +

NRC Bulletin 80-11 +  and NRC Bulletin 79-18, Audibility Problems Encountered on Evacuation of Personnel from High-Noise Areas +

NUREG-0739, Forwards Analysis of Comments on 810326 Fr Notice, (46FR18827) & NUREG-0764, Toward Safety Goal:Discussion of Preliminary Policy Considerations +, NUREG-0778 +, NUREG-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, 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-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 +  and NUREG-0799, Guidelines for the Preparation of Emergency Operating Procedures.Resolution of Comments on NUREG-0799 +

ST +  and TP-F40SG +

5A-9 +, 0G-61 +, 0G-47 +, 0G-52 +, 0G-54 +, 0G-60 +, 10TCC-V47 +, 4s-es +  and 10S03-C07 +

DPR-24 +  and DPR-27 +

Texas +, Washington +, Michigan +  and Wisconsin +

Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Safety Parameter Display System +, Main Steam Line +  and Safety Relief Valve +

Office of Nuclear Reactor Regulation +  and Harold Denton +

Reactor Vessel Water Level +, Grab sample +, Shift Technical Advisor +  and Backfit +