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TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

Iodine +, Nitrogen +, Carbon +, Lead +, Helium +  and Sulfur +

10 CFR 50 +  and 10 CFR 50 Appendix A +

Initiating Events +  and Mitigating Systems +

SECY-82-465 +, SECY-83-288 +, SECY-83-443 +, NRC 1984 +, RS 270 +  and RS 325 266 +

SE-6 +, SE-2 +, SE-4 +, SE-8 +, SE-07 +, SE-5 +, SE-7 +  and SE-03 +

Office of Nuclear Reactor Regulation +, Riggs R +  and Sege G +

GDC 34 +, GDC 50 +, GDC 16 +  and GDC 31 +

ML20128F330 +, ML20128F330 +, ML20128F330 +, ML20128F330 +, ML20128F330 +, ML20128F330 +, ML20128F330 +, ML20128F330 +  and ML20128F330 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 0.00231 d (0.0556 hours, 3.306878e-4 weeks, 7.61e-5 months)  +  and 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +

Westinghouse +  and General Electric +

Information Notice 82-45 +  and Information Notice 82-17 +

NUREG/BR-0058 +, NUREG-0692 +, NUREG/CR-3568 +, NUREG/CR-3770 +, NUREG/CR-2800 +, NUREG/CR-0058 +, NUREG/CR-2787 +, NUREG/CR-1925 +, NUREG/CR-1870 +, NUREG/CR-1595 +, NUREG-0886, Responds to Expressing Concern Re Manner in Which NRC Deals W/Problem of Steam Generator Tube Integrity.Nrc Is Adequately Addressing Problem.Steam Generator Insp History,Abstract of NUREG-0886 & NRR Budget Analysis Encl +, NUREG/CR-2096 +, NUREG/CR-2458 +, NUREG/CR-3299 +, NUREG/CR-2239, Forwards Slides/Handout Used at 821110 Presentation of NUREG/CR-2239 Re Sandia Siting or Consequences Study. Transcript of Meeting in PDR Did Not Include Slides +, NUREG/CR-2153 +, NUREG-1128 +, NUREG/CR-1490 +, NUREG/CR-2219 +, NUREG/CR-2248 +, NUREG/CR-2322 +, NUREG/CR-3532 +, NUREG/CR-0651 +, NUREG-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, NUREG-0880, Transcript of 860619 Commission Meeting in Washington,Dc Re Safety Goals.Pp 1-58.Related Info Encl +, NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, 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/CR-1659, Forwards Reactor Safety Study Methodology Applications Program Rept for plant,NUREG/CR-1659.Safety Evaluation Based on Rept & Other Info to Be Prepared by Nrc.Util Views Requested.W/O Encl +...

RS 270 +  and RS 325 266 +

Regulatory Guide 1.45 +, Regulatory Guide 1.121 +  and Regulatory Guide 1.83 +

SECY-82-465 +, SECY-83-288 +  and SECY-83-443 +

7E-12 +, 2E-02 +, 1E-6 +, 1E-8 +, 1E-5 +, 1E-4 +, 1E-3 +, 1E-7 +, 1E-9 +, 1E-06 +, 1E-07 +, 2E-2 +, 1E-08 +, 3E-5 +, 2E-7 +, 2E-5 +, 2E-8 +, 2E-11 +, 2E-07 +, 7E-7 +, 4E-7 +, 2E-09 +, 2E-6 +, 1E-02 +, 7E-6 +, 1E-05 +, 4E-06 +, 5E-8 +, 2E-4 +, 1E-2 +...

Illinois +, Maryland +, Washington +, California +, Massachusetts +, New York +, Arkansas +  and New Mexico +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +  and Emergency Feedwater System +

Boric Acid +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, Loss of Offsite Power +, Eddy Current Testing +, Earthquake +, Power change +, Fatality +, Water hammer +, Leak-Before-Break +  and Leak Before Break +