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Pages with broken file links, CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and RESEARCH INSTITUTION/LABORATORY TO NRC

Strontium +, Cesium +, Uranium +, Gadolinium +, Nitrogen +, Oxygen +, Hydrogen +, Zirconium +, Lead +, Helium +, Ruthenium +, Tellurium +  and Barium +

10 CFR 100 +  and 10 CFR 50#s +

H.6(u) +  and S.9(r) +

05000271  +, 00213  +, 00247  +, 00244  +, 00325  +, 00271  +, 00344  +  and 00327  +

Brookhaven National Laboratory +  and Perkins K +

ML17347B682 +, ML17347B682 +, ML17347B682 +, ML17347B682 +, ML17347B682 +, ML17347B682 +, ML17347B682 +, ML17347B682 +, ML17347B682 +, ML17347B682 +, ML17347B682 +, ML17347B682 +, ML17347B682 +  and ML17347B682 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

Am-241 +, Co-60 +, Cs-137 +, U-235 +, Sr-90 +, Fe-55 +, Y-90 +, I-131 +, C-14 +, H-3 +, Mo-99 +  and Pu-239 +

NUREG/CR-1577 +, NUREG/CR-0649, Opposition to M & R Framson 790803 Suppl to 790413 contentions.NUREG/CR-0649 Re Spent Fuel Heatup Following Loss of Water During Storage,Provides No Basis for Possibility of Spent Fuel Meltdown.Certificate of Svc Encl +, NUREG/CR-2326 +, NUREG/CR-3558 +, NUREG/CR-3756 +, NUREG-0824, Safety Evaluation Concluding Util 831228,840111 & 0202 Responses to NUREG-0824,Section 4.12 Re Design Codes,Design Criteria & Loading Combinations Complete Except for Listed Issues Requiring Resolution +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG/CR-2815, Discusses PRA Guidance Documents NUREG/CR-2815 & NUREG/CR-3485.Recasting of Documents in SRP or Reg Guide Formats Recommended Upon Receipt of Public Comments If Documents Reflect Agency Views +, NUREG/CR-1582, Forwards Aug 1980 NUREG/CR-1582,Vols 2 & 3, Seismic Hazard Analysis,Solicitation of Expert Opinion, Prepared by Tera Corp.W/O Encl +, NUREG-0020, Responds to Encl Re Spent Fuel Storage Capacity at Plant.Spent Fuel Pool at Plant Has Sufficient Space to Accommodate Addl Fuel Storage Racks of Current Design +, NUREG-0227, Partial Draft of Nuclear Power Plant Operating Experience - 1978, Section 3.0, Plant Outages. Portions of NUREG-0483, NUREG-0366 & NUREG-0227 (Plant Operating Experience for 1977,1976 & 1974-75,respectively) Encl +, 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 +  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 +, RT +  and CP +

2E-3 +, 9E-1 +, 5x10-z +, 40E-3 +, 3x10-s +, 36E-2 +, 4E-1 +, 05E-2 +, 73E-3 +, 49E-2 +, 89E-1 +, 90E-2 +, 78E-3 +, 85E-l +, 39E-l +, 80E-I +, 5urry-1 +, 3x10-e +, 8a6E-I +, 3o84E-2 +, O49E-2 +, 45E-3 +, 69E-l +, O74E-2 +, 735K-2 +, 36K-2 +, 3i84E-2 +, E37E-2 +, O90E-I +, 5e77E-3 +...

Texas +, Utah +, Colorado +, Washington +, South Carolina +, New York +, Arkansas +  and Vermont +

Primary containment +  and Residual Heat Removal +

Office of Nuclear Reactor Regulation +  and Throm E +

Safe Shutdown +, Boric Acid +, Tornado Missile +, Safe Shutdown Earthquake +, Hydrostatic +, Probabilistic Risk Assessment +, Design basis earthquake +, Earthquake +, Turbine Missile +, Fuel cladding +  and Spent fuel rack +