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NUREG REPORTS, SAFETY EVALUATION REPORT--FACILITY  and TEXT-SAFETY REPORT

ASME Section IX +  and ASME Section XI +

Uranium +, Lead +, Helium +  and Tin +

10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.55a +  and 10 CFR 50.55a#g4 +

00275  +, 00323  +, 05000275  +  and 05000323  +

GDC 10 +, GDC 31 +, GDC 51 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +  and GDC 3, Fire protection +

ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +, ML16341B590 +  and ML16341B590 +

IEEE 323-1974 +, IEEE-450 +  and IEEE 535 +

ML19340D259 +, ML20037C726 +, ML16341C685 +, ML16340B476 +, ML17083A807 +, ML16340A935 +, ML19210D808 +  and ML19210D761 +

NUREG-675 +, NUREG-0675, Forwards Decision DD-86-12 in Response to Petition & Suppls Re Licensing Actions Based on Allegations.Nrc Evaluation of Allegation & Basis for Conclusions in Decision DD-86-12 Contained in Sser 33 to NUREG-0675,transmitted on 860527 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, 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-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +, NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

OP-38 +  and OP-15 +

CP +  and ES +

Regulatory Guide 1.74 +, Regulatory Guide 1.58 +, Regulatory Guide 1.99 +, Regulatory Guide 1.30 +, Regulatory Guide 1.144 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +

Tennessee +, Washington +  and California +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Emergency Core Cooling System +, Main Steam Line +  and Control Rod +

Safe Shutdown +, Fire Barrier +, Hydrostatic +, Emergency Lighting +, Earthquake +, Fire Protection Program +  and Overspeed +