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INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE

Nitrogen +, Lead +  and Tin +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 2 +, 10 CFR 2.201 +, 10 CFR 50.54 +, 10 CFR 50.73#a2v +, 10 CFR 50.73#a2iv +  and 10 CFR 50.72#b2 +

05000000  +, 05000277  +, 05000278  +, 00277  +  and 00278  +

48 FR 39039 +  and 49 FR 8583 +

NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) +  and Starostecki R +

ML20214T277 +, ML20214T277 +, ML20214T277 +, ML20214T277 +, ML20214T277 +, ML20214T277 +, ML20214T277 +, ML20214T277 +, ML20214T277 +, ML20214T277 +  and ML20214T277 +

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 0.00182 d (0.0436 hours, 2.595899e-4 weeks, 5.97385e-5 months)  +, 0.00162 d (0.0389 hours, 2.314815e-4 weeks, 5.327e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00664 d (0.159 hours, 9.490741e-4 weeks, 2.18407e-4 months)  +, 0.0146 d (0.349 hours, 0.00208 weeks, 4.78669e-4 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

General Electric +  and Target Rock +

Information Notice 85-80 +, Information Notice 85-27 +  and Information Notice 85-50 +

NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +, NUREG-0554, Responds to to Chairman Jackson Re Resolution of Berkeley Township Environ Commission. Forwards Reply to L Worrall Which Contains Directors Decision,Per 10CFR2.206 +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

ST +, CH +, RT +, CP +, SP-863 +, RT-1.8.1 +, RT-7.32 +, ST-13.32 +, ST.2.7 +, ST-13.9 +, ST-13.7A +, ST-4.9 +  and ST-10.4 +

50-276fDPR-56 +  and O1A-86-129 +

Peach Bottom +  and 05000000 +

Texas +, Ohio +, Pennsylvania +, Washington +, Arkansas +, Vermont +  and Maine +

Feedwater +, Secondary containment +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Auxiliary Feedwater +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Standby Gas Treatment System +, Automatic Depressurization System +, Intermediate Range Monitor +, Emergency Core Cooling System +, Safety Relief Valve +, Rod Worth Minimizer +, Rod Sequence Control System +, Control Rod +  and Main Steam +

TS-3.7 +, TS-2.2 +, TS-3.5.F +, TS-6.8.1 +, TS-6.5.1 +, TS-6.5.1.6 +, TS-6.8.3 +, TS-4.5.A +, TS-4.6.D +  and TS-4.6.0 +

Jordan E +  and NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) +

Safe Shutdown +, Unanalyzed Condition +, Reactor Vessel Water Level +, Fire Barrier +, Local Leak Rate Testing +, Notice of Violation +, Scram Discharge Volume +, Shift Technical Advisor +, Loss of Offsite Power +, Integrated leak rate test +, Fatality +, Overspeed +, Simmer margin +  and Water hammer +