Browse wiki

Inspection Report, TEXT-INSPECTION & AUDIT & I&E CIRCULARS  and NRC-GENERATED

ANSI B31.1 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +

ASME Section XI +, ASME Section III +  and ASME Section IX +

Lead +  and Carbon +

10 CFR 50 Appendix R +, 10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 50.59 +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.59#a2 +  and 10 CFR 50.55a#g +

L-900 +  and NRC 10 +

05000245  +, 05000336  +, 05000423  +, 00245  +  and 00423  +

Doerflein L +  and NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) +

NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 81-14, Seismic Qualifications for Auxiliary Feedwater Systems +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +, IR 05000245/1993024 +...

0.00188 d (0.045 hours, 2.678571e-4 weeks, 6.1641e-5 months)  +, 4.282407e-4 d (0.0103 hours, 6.117725e-5 weeks, 1.40785e-5 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +

IP 40500 +, IP 71707 +, IP 37700 +  and IP 62703 +

Westinghouse +, Limitorque +  and Nuclear Measurements +

NRC Bulletin 79-14 +, NRC Bulletin 90-01 +  and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +

SP +, Emergency Operating Procedure +, Emergency Plan +, MP-92-106 +  and SP-3451-R01 +

07-87-004 +, 93A-1 +, 07-92-096 +  and 1SEG-like +

DPR-21 +  and Millstone +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Water Cleanup +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Auxiliary Feed Water +  and Main Steam +

TS-3.0.3 +, TS-3.9.9 +, TS-3.8.2.1 +, TS-3.7.1.2 +, TS-4.0.3 +, TS-4.0.5 +, TS-3.9.4 +, TS-6.6 +, TS-3.7.1.3 +  and TS-4.1.1 +

Hot Short +, Safe Shutdown +, High Radiation Area +, Stroke time +, Safe Shutdown Earthquake +, Hydrostatic +, Enforcement Discretion +, Reserve Station Service Transformer +, Nondestructive Examination +, Temporary Modification +, Locked High Radiation Area +, High Energy Line Break +, Intergranular Stress Corrosion Cracking +, Loss of Offsite Power +, Eddy Current Testing +, Operability Determination +, Earthquake +, Liquid penetrant +, Downpower +, Weak link +, Unidentified leakage +, Thermal fatigue +  and Overthrust +