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TEXT-SAFETY REPORT  and NRC TECHNICAL REPORT

Iron +, Hydrogen +  and Lead +

BWRVIP-27 +, BWRVIP-25 +, BWRVIP-03 +, BWRVIP-26 +, BWRVIP-62 +, BWRVIP-05 +, BWRVIP-16 +, BWRVIP-06 +, BWRVIP-17 +, BWRVIP-50 +, BWRVIP-51 +, BWRVIP-57 +, BWRVIP-58 +, BWRVIP-07 +, BWRVIP-28 +, BWRVIP-59 +, BWRVIP-60 +, BWRVIP-53 +, BWRVIP-52 +, BWRVIP-56 +, BWRVIP-08 +, BWRVIP-46 +, BWRVIP-34 +  and BWRVIP-55 +

10 CFR 21 +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 54 +, 10 CFR 54.21 +, 10 CFR 100 Appendix A +, 10 CFR 00 Appendix J +, 10 CFR 50.55a +, 10 CFR 50.54#f +, 10 CFR 50.47#b4 +, 10 CFR 50.55a#a3 +  and 10 CFR 50.55a#g6iiA +

ASME Code Case N-578 +, ASME Code Case N-577 +  and ASME Code Case N-560 +

SECY-98-154 +, SECY-95-059 +, SECY-88-147 +, SECY-98-248 +, SECY-89-012 +, SECY 95-059 +, SECY 99-063 +, SECY-98-067 +, COMSECY-97-013 +, SECY-96-242 +, SECY-95-079 +, SECY 96-088 +, SECY-97-077 +, SECY-95-131 +, SECY-98-158 +, SECY 97-190 +, SECY 98-248 +, SECY 97-229 +, SECY-97 229 +, SECY 98-067 +, SECY 96-139 +  and SECY-88147 +

S.4(p) +  and P.9(a) +

NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage +, NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +, NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +, NRC Generic Letter 98-05, Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds +, NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +, NRC Generic Letter 98-02, Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

ML20216F016 +, ML20216F016 +, ML20216F016 +, ML20216F016 +, ML20216F016 +  and ML20216F016 +

General Electric +  and Westinghouse +

NRC Bulletin 96-03 +, NRC Bulletin 93-02 +, NRC Bulletin 95-02 +  and NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment +

Information Notice 99-13 +, Information Notice 97-17 +, Information Notice 97-02 +, Information Notice 95-03 +, Information Notice 97-63 +  and Information Notice 98-44 +

NUREG-1544 +, NUREG-0555, For Comment Notice of Issuance & Availability of Proposed NUREG-0555,ESRP Section 7.1.1, Environ Impacts of Postulated Accidents Involving Radioactive Matls - Releases to Groundwater +, NUREG-4674 +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG-45 +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0897, Forwards Susceptibility of ERCO-SIL 36S Insulation Pillows to Debris Formation Under Exposure to Energetic Jet Flows & Bouyancy,Transport & Head Loss Characteristics of ERCO-SIL 36S Insulation Pillows for Nuclear.. +, NUREG-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl +, NUREG-1555, Supplement 1, Revision 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants Supplement 1: Operating License Renewal Final Report +, NUREG-1410, Discusses NRC Concerns Re Operator Diligence While in Shutdown Conditions & Requests Quick & Appropriate Mgt Reactions to Generic Ltr 88-17.Supporting Documentation Encl +, 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 +, NUREG/CR-6224, Requests That Encl Documents Be Available Through NRC PDR & Central Files.Documents Provided Background or Ref Info for Resolution of BWR Strainer Blockage Issue,As Ref by Draft NUREG/CR-6224, Parametric Study of Potential for Bwr.. +  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 +

Amy Cubbage +, Kerri Kavanagh +, Ralph Beedle +, Shirley Ann Jackson +  and Ted Sullivan +

MP +  and Emergency Plan +

TAC:MA3695 +, TAC:MA0837 +, TAC:MA0626 +, TAC:M94975 +, TAC:M91429 +, TAC:M95125 +, TAC:M66278 +  and TAC:M88885 +

Regulatory Guide 1.1 +, Regulatory Guide 1.147 +, Regulatory Guide 1.160 +, Regulatory Guide 1.82 +, Regulatory Guide 1.101 +, Regulatory Guide 1.54 +, Regulatory Guide 4.2 +, Regulatory Guide 1.178 +  and Regulatory Guide 1.176 +

SECY-98-154 +, SECY-95-059 +, SECY-88-147 +, SECY-98-248 +, SECY-89-012 +, SECY 95-059 +, SECY 99-063 +, SECY-98-067 +, SECY-96-242 +, SECY-95-079 +, SECY 96-088 +, SECY-97-077 +, SECY-95-131 +, SECY-98-158 +, SECY 97-190 +, SECY 98-248 +, SECY 97-229 +, SECY-97 229 +, SECY 98-067 +, SECY 96-139 +  and SECY-88147 +

Texas +, Tennessee +, Georgia +, Maryland +, Washington +, Virginia +, South Carolina +, Nebraska +  and Vermont +

Steam Generator +, Reactor Coolant System +, Service water +, Main Steam Isolation Valve +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Emergency Core Cooling System +, Safety Relief Valve +, Control Rod +  and Containment Spray +

Safe Shutdown +, Safe Shutdown Earthquake +, Weld Overlay +, Probabilistic Risk Assessment +, Coatings +, Significance Determination Process +, Foreign Material Exclusion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Severe Accident Management Guideline +, License Renewal +, Commercial Grade +, Environmental Justice +, Backfit +, Reactive Inspection +  and Leak-Before-Break +