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Boron +, Cesium +, Hydrogen +  and Lead +

Initiating Events +  and Mitigating Systems +

05000293  +, 00293  +, 00165  +  and 00175  +

ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +, ML110600910 +  and ML110600910 +

1.62037e-4 d (0.00389 hours, 2.314815e-5 weeks, 5.327e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +  and 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +

Am-241 +, Co-60 +, Cs-137 +, Sr-90 +, Y-90 +, Kr-85 +, Mo-99 +, Pu-238 +  and Pu-239 +

BECO-92-165, Forwards 1993 Environ Monitoring,Thermal Discharge Fish Surveillance & Dissolved Nitrogen Saturation Reduction Programs & Plans,Per NPDES Permit MA0003557 (Federal) & 359 (State) for Approval +, BECO-LTR-95-127, Forwards Response to NRC RAI Re Internal Event Analysis in Response to GL 88-20 +, BECO-LTR-94-108, Informs That Util Will Submit Listed Addl Info Re Pilgrim Core Shroud Assessment on 941014,in Response to NRC RAI During 941004 Meeting.Info Will Provide Further Support of Util Plans to Implement pre-emptive Repair in RFO 10 +  and ML20237H349 +

General Electric +  and Westinghouse +

NUREG-1742 +, NUREG/BR-0184 +, NUREG/CR-4551 +, NUREG/CR-5497 +, NUREG/BR-01 +, NUREG/CR-5124 +, NUREG-0498, Supp 2 DFC, (2.2) Pt 5 - End, Draft Final Environmental Statement, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG/CR-5474 +, NUREG/CR-5500, Discusses Issuance of Final Rept, Reliability Study Auxiliary Emergency Feedwater System 1987-1995, (NUREG/CR-5500,Vol 1).Summary of Comment Resolutions Encl +, NUREG-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 +  and NUREG/CR-1278, Official Exhibit - NRC098-00-BD01 - NUREG/CR-1278, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications - Final Report +

OSP-14 +, OSP-SBO +  and OSP-24 +

TAC:M77222 +  and TAC:M74451 +

5E-02 +, 95E-06 +  and 30E-04 +

Tennessee +, Massachusetts +, Arkansas +  and Rhode Island +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Primary containment +, Main Transformer +, Reactor Pressure Vessel +, Core Spray +, Standby Liquid Control +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +  and Control Rod +

High winds +, Mission time +, Internal Flooding +, Probabilistic Risk Assessment +, Seismically rugged +, Large early release frequency +, Loss of Offsite Power +, License Renewal +, Fatality +, GOTHIC +, Siren +, Failure to Scram +  and Leak Before Break +