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TEXT-SAFETY REPORT, NUREG REPORTS  and SAFETY EVALUATION REPORT--FACILITY

IWB-2500 +, IWC-1220 +, IWB-2600 +, IWC-2520 +, IWC-2600 +, IWA-2220 +, IWA-4000 +, IWA-2230 +  and IWA-7000 +

Boron +, Iron +, Copper +, Nitrogen +, Hydrogen +, Lead +  and Aluminum +

10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 73 +, 10 CFR 50.49 +, 10 CFR 73 Appendix B +, 10 CFR 73 Appendix C +, 10 CFR 20.408 +, 10 CFR 70.24 +, 10 CFR 50.47#c1 +, 10 CFR 50.47#b12 +, 10 CFR 50.57#a1 +, 10 CFR 50.55a#g +, 10 CFR 50.55a#g5 +, 10 CFR 50.55a#a3 +, 10 CFR 50.55a#g4 +, 10 CFR 50.55a#b +, 10 CFR 50.55a#g6i +, 10 CFR 50.55a#g5iv +, 10 CFR 50.55a#g1 +, 10 CFR 50.55a#g3v +, 10 CFR 50.55a#b2iv +, 10 CFR 50.55a#g3 +, 10 CFR 73.55#f +, 10 CFR 73.55#e +, 10 CFR 73.55#b +, 10 CFR 73.55#a +, 10 CFR 73.55#d +, 10 CFR 73.55#g +...

Emergency Preparedness +  and Physical Protection +

00413  +, 00414  +, 05000413  +, 05000414  +, 00458  +, 00315  +, 00316  +, 00369  +, 00370  +, 00328  +  and 00327  +

Turbine Trip +  and Reactor Trip +

50 FR 50764 +, 50 FR 3498 +, 50 FR 20892 +  and 50 FR 3502 +

GDC 16 +, GDC 32 +, GDC 36 +, GDC 17, Electric power systems +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +

NRC Generic Letter 83-37, NUREG-0737 Technical Specifications +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 83-23, Safety Evaluation of "Emergency Procedure Guidelines" +, NRC Generic Letter 83-22, Safety Evaluation of "Emergency Response Guidelines" +, NRC Generic Letter 83-12, Issuance of NRC FORM 398 - Personal Qualifications Statement - Licensee +, NRC Generic Letter 84-24, Certification of Compliance to 10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants +, NRC Generic Letter 84-16, Adequacy of On-Shift Operating Experience for Near Term Operating License Applicants +, NRC Generic Letter 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage +, NRC Generic Letter 85-18, Operator Licensing Examinations +, NRC Generic Letter 85-17, Availability of Supplements 2 and 3 to NUREG-0933, "A Prioritization of Generic Safety Issues" +, NRC Generic Letter 85-16, High Boron Concentrations +, NRC Generic Letter 85-15, Information on Deadlines for 10CFR50.49, "Environmental Qualification of Electric Equipment Important to Safety at Nuclear Power Plants" +, NRC Generic Letter 85-14, Commercial Storage at Power Reactor Sites of Low Level Radioactive Waste Not Generated by The Utility +, NRC Generic Letter 85-13, Transmittal of NUREG-1154 Regarding The Davis-Besse Loss of Main And Auxiliary Feedwater Event +, NRC Generic Letter 85-12, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps +, NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +, NRC Generic Letter 85-09, Technical Specifications for Generic Letter 83-28, Item 4.3 +, NRC Generic Letter 85-08, 10 CFR 20.408 Termination Reports - Format +, NRC Generic Letter 85-07, Implementation of Integrated Schedules for Plant Modifications +, NRC Generic Letter 85-06, Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related +, NRC Generic Letter 85-05, Inadvertent Boron Dilution Events +, NRC Generic Letter 85-04, Operating Licensing Examinations +, NRC Generic Letter 85-02, Staff Recommended Actions ... Regarding Steam Generator Tube Integrity +  and NRC Generic Letter 85-01, Fire Protection Policy Steering Committee Report +

ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +, ML20154M443 +...

3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 0.00208 d (0.05 hours, 2.97619e-4 weeks, 6.849e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.0072 d (0.173 hours, 0.00103 weeks, 2.36671e-4 months)  +, 0.0104 d (0.25 hours, 0.00149 weeks, 3.4245e-4 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 0.00109 d (0.0261 hours, 1.554233e-4 weeks, 3.5767e-5 months)  +

ML20087M617 +, ML20084K895 +, ML20084G877 +, ML20080N927 +, ML20078R818 +, ML20101T501 +, ML20101P655 +, ML20101C757 +, ML20100G320 +, ML20099M465 +, ML20099L529 +, ML20099L057 +, ML20099C388 +, ML20094N206 +, ML20093M658 +, ML20093F649 +, ML20092P162 +, ML20115E023 +, ML20112C955 +, ML20112A979 +, ML20137S424 +, ML20137M916 +, ML20137A935 +, ML20140A591 +, IR 05000413/1985043 +, ML20138L775 +, ML20138F157 +, ML20134H257 +, IR 05000414/1985026 +, ML20133C656 +...

Westinghouse +, Honeywell +  and Worthington +

NUREG-0452 +, NUREG-06 +, NUREG-0693 +, NUREG/CR-3912 +, NUREG-1014, Forwards Generic Evaluation (NUREG-1014) of Mod to Westinghouse Steam Generators D4/D5/E.Mod Acceptable. Modified Steam Generators Can Be Operated at 100% Design Capacity,Pending plant-specific Verification.W/O Encl +, NUREG-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, NUREG-954 +, NUREG-0954, Advises That 860619 Submittal Summarizing Results of Survey Quantifying Insulation in Containment by Type & Location Complies W/Guidance in Generic Ltr 85-22 & Sser 2 (NUREG-0954) +, NUREG-0484, Forwards SER Suppl Info on Applicant 830203 Submittal Re Applicability of Square Root of Sum of Squares Combination of Dynamic Responses.Method Applicable & Complies w/NUREG-0484 +, NUREG-0989, Safety Evaluation Supporting Proposed Turbine Maint Program. Proposal Satisfies Licensee Commitment Prescribed in Sser 5. Commitment Acceptable Resolution of Turbine Maint Issue +, 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-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/CR-3954, Forwards NUREG/CR-3954, Hectr Analysis of Equipment Temp Responses to Selected Hydrogen Burns in Ice Condenser Containment. Comments Requested within 45 Days of Ltr Date.W/O Encl +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0422, Requests Comments on Review of Encl marked-up Tech Spec Concerns Resulting from Differing Prof Opinion.Some Concerns Should Be Resolved on plant-specific Basis.Proposed Amend Requests & Reply Needed within 90 Days +, 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 +  and NUREG-1000 +

Regulatory Guide 1.97 +, Regulatory Guide 1.147 +  and Regulatory Guide 1.83 +

6B-1 +, 05RV-16 +, 1NB-378 +  and 1NB-395 +

Cook +, NPF-35 +, NPF-31 +  and NPF-48 +

Texas +, Tennessee +, Maryland +, North Carolina +, Washington +, Alabama +, South Carolina +, Idaho +, New York +, Michigan +  and Indiana +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Safety Parameter Display System +, HVAC +, Residual Heat Removal +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Boric Acid +, Hydrostatic +, Nondestructive Examination +, Incorporated by reference +, Local Leak Rate Testing +, Notice of Violation +, Feedwater Heater +, Shift Technical Advisor +, Intergranular Stress Corrosion Cracking +, Loss of Offsite Power +, Integrated leak rate test +, Safeguards Contingency Plan +, Breakaway torque +, Control of Heavy Loads +, Fuel cladding +, Liquid penetrant +, Fire Protection Program +, Core Exit Thermocouple +, Siren +, Overexposure +, Overspeed +, Eddy Current Test +  and Leak-Before-Break +