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Pages with broken file links, SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES  and TEXT-SAFETY REPORT

Boron +, Iodine +, Carbon +, Hydrogen +, Lead +  and Tin +

10 CFR 50.72 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 50 Appendix G +, 10 CFR 51.21 +, 10 CFR 50.59b +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 51.22#c +

05000213  +  and 00213  +

NRC Generic Letter 83-37, NUREG-0737 Technical Specifications +, NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +, NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +, NRC Generic Letter 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications +, NRC Generic Letter 89-14, Line-Item Improvements in Technical Specifications - Removal of 3.25 Limit on Extending Surveillance Intervals +  and NRC Generic Letter 90-02, Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications +

ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +, ML20034C577 +...

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +  and 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +

ML20235E472 +, B13375, Responds to Request for Addl Info Re Electrical Distribution Sys Design Associated W/New Switchgear Bldg.New Switchgear Bldg Provides Opportunity to Minimize Dependence on Motor Control Ctr 5 & Further Reduce Level of Risk +, A07974, Advises That No Agreements Restricting Employees to Inform NRC of Potential Safety Issues Exist,Per V Stello +, B13292, Proposed Tech Specs,Supporting Cycle 16 +, A06850, Forwards Addl Info Re Miscellaneous Amends/Search Requirements for Amend to Physical Security Plan,Per NRC 871005 Request.Encl Withheld (Ref 10CFR2.790) +, B11594, Revised Application for Amend to License DPR-61,correcting Typos,Adding Figure & Revising Definitions Section of Tech Specs Submitted w/850529 Application +, B12999, Provides NRC W/Preliminary Info Re Nuclear Instrumentation Sys Mods & Phase II of Reactor Protection Sys (RPS) Upgrades.Attachment I Contains Conceptual Project Description & Safety Evaluation Re RPS Upgrades +, A04948, Forwards Clarifications of Rev 11 to Modified Amended Security Plan,Per 850612 & 19 Commitments.Clarifications Withheld (Ref 10CFR73.21 & 2.790) +, A01460, Submits Schedule for Emergency Preparedness Exercises Per NRC .Dates Acceptable by State of CT & Fema. Requests Info Re NRC Personnel Attending,Social Security Numbers,Security Clearance & Vital Areas to Be Accessed +  and ML20024D309 +

Westinghouse +, Foxboro +  and Mercoid +

NUREG-0452 +, 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 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

CH-MOV-257 +, CH-MOV-257B +, CH-MOV-2578 +, CH-50V-2428 +  and CH-50V +

Regulatory Guide 1.25 +, Regulatory Guide 1.137 +, Regulatory Guide 1.52 +, Regulatory Guide 1.108 +  and Regulatory Guide 1.93 +

05000454/SR-4.1.3.2 +, 05000454/SR-4.1.3.5 +, 05000454/SR-4.01 +, 05000454/SR-4.3.H +, 05000454/SR-4.4 +, 05000454/SR-4.2.1.3 +, 05000454/SR-4.2.5.1.c +  and 05000454/SR-4.2.5.2 +

Washington +  and Connecticut +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Residual Heat Removal +, Emergency Core Cooling System +, Control Rod +  and Containment Spray +

05000454/TS-3.8.1.1 +, 05000454/TS-4.8.1.1 +, 05000454/TS-3.0.4 +, 05000454/TS-4.2 +, 05000454/TS-6.9.2 +, 05000454/TS-3.1.2 +, 05000454/TS-3.4.9 +, 05000454/TS-3.7.1.2 +, 05000454/TS-5.3.1 +, 05000454/TS-3.3.4.2 +, 05000454/TS-3.9.11 +, 05000454/TS-3.1.2.2 +, 05000454/TS-3.1.2.6 +, 05000454/TS-3.6.1.5 +, 05000454/TS-4.4.5.4 +, 05000454/TS-3.3.3.2 +, 05000454/TS-3.9.C +, 05000454/TS-3.11.E +, 05000454/TS-3.13.A +, 05000454/TS-3.13 +, 05000454/TS-3.13.F +, 05000454/TS-3.13.H +, 05000454/TS-3.22 +, 05000454/TS-6.6.1 +, 05000454/TS-4.5 +, 05000454/TS-4.0.2 +, 05000454/TS-4.3.B +, 05000454/TS-4.4 +, 05000454/TS-4.7.4.c +, 05000454/TS-4.5.1.a +...

Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Fire Barrier +, Hydrostatic +, Loss of Offsite Power +, Integrated leak rate test +, Control of Heavy Loads +, Pressure Boundary Leakage +, Offsite Circuit +, Fire Watch +, Unidentified leakage +  and Manual Operator Action +