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TEXT-SAFETY REPORT  and REFERENCE SAFETY ANALYSIS REPORT & AMENDMENTS (RSAR)

ANSI N18.2-1973 +  and ANSI N41.14 +

ASME Section XI +  and ASME Section III +

Boron +, Iodine +, Uranium +, Copper +, Carbon +, Hydrogen +, Chloride +  and Lead +

10 CFR 21 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 51 +, 10 CFR 60 +, 10 CFR 50.13 +, 10 CFR 50.82 +, 10 CFR 50 Appendix I +, 10 CFR 73.55 +, 10 CFR 50.33#f +  and 10 CFR 73.55#e +

Emergency Preparedness +, Physical Protection +  and Occupational Radiation Safety +

SECY-82-367 +  and NRC 15 +

05000601  +  and 00601  +

Turbine Trip +  and Reactor Trip +

WESTINGHOUSE ELECTRIC COMPANY +  and DIV OF CBS CORP. +

SC-708-4 +  and SC-521-4 +

GDC 31 +, GDC 32 +, GDC 52 +, GDC 53 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +  and GDC 3, Fire protection +

NRC Generic Letter 81-28, Steam Generator Overfill +  and NRC Generic Letter 81-21, Natural Circulation Cooldown +

ML20084P676 +, ML20084P676 +, ML20084P676 +, ML20084P676 +, ML20084P676 +, ML20084P676 +, ML20084P676 +, ML20084P676 +, ML20084P676 +  and ML20084P676 +

IEEE 384 +  and IEEE 317 +

Westinghouse +  and Target Rock +

NUREG-0705 +, NUREG-0733 +, NUREG-0858 +, NUREG-0693 +, NUREG-0691 +, NUREG/CR-2189 +, NUREG/CR-2425 +, NUREG/CR-2749 +, NUREG/CR-2750 +, NUREG/CR-2136 +, NUREG/CR-2963 +, NUREG/CR-0022 +, NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, NUREG-0961 +, NUREG/CR-1915 +, NUREG-0942 +, NUREG-0333 +, 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-0471, Responds to 781113 Request & Encl Generic Task Problem Descriptions(NUREG-0471)& NRC Prog for Resolution of Generic Issues Related to Nuc Pwr Plants(NUREG-0410). W/O Encl +, NUREG/CR-0672, Forwards NUREG/CR-0672,Addendum 3, Technology,Safety & Costs of Decommissioning Ref BWR Power Station, Estimating Decommission Costs for Plant,Per 880706 Meeting.W/O NUREG/CR-0672,Addendum 3 +, NUREG-0586, Forwards NUREG-0586, Final Generic Environ Impact Statement on Decommissioning of Nuclear Facilities, W/Re to 971113 Request for Info Pertaining to Expected Occupational Doses Associated w/long-term Storage.W/O Encl +, 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-0440, Forwards Class 9 Liquid Pathway Assessment Input to Chapter 6.1 of Des +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, NUREG-0138, Exemption from GDC 17 Requirements Re LPCI Swing Bus Design +, NUREG-0305, Forwards NUREG-0305,technical Rept on Dc Power Supplies in Nuclear Power Plants.W/O Encl +, NUREG/CR-0130, Responds to Encl to President Carter Re Nuclear Power Plants.Presidential 791207 Statement on Kemeny Commission Rept on TMI-2 & Excerpts from NUREG-0662 & NUREG/CR-0130 Encl +, NUREG/CR-0660, Forwards Sample Ltr to Applicants,Cp Holders & Licensees of LWRs Transmitting NUREG/CR-0660 Enhancement of Onsite Emergency Diesel Generator Reliability +...

Regulatory Guide 1.97 +, Regulatory Guide 1.75 +, Regulatory Guide 1.63 +, Regulatory Guide 1.52 +, Regulatory Guide 1.108 +, Regulatory Guide 1.105 +, Regulatory Guide 1.109 +, Regulatory Guide 4.1 +, Regulatory Guide 4.8 +, Regulatory Guide 8.8 +, Regulatory Guide 1.29 +, Regulatory Guide 1.102 +, Regulatory Guide 1.12 +, Regulatory Guide 1.91 +, Regulatory Guide 1.140 +, Regulatory Guide 1.133 +, Regulatory Guide 1.89 +, Regulatory Guide 1.20 +, Regulatory Guide 1.115 +, Regulatory Guide 1.35 +, Regulatory Guide 1.46 +, Regulatory Guide 4.2 +  and Regulatory Guide 1.150 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Spray Pond +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Tornado Missile +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, Nondestructive Examination +, Squib +, Scram Discharge Volume +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Control of Heavy Loads +, Power-Operated Valves +, Power Operated Valves +, Turbine Missile +, Fuel cladding +, Backfit +, Overspeed +, Thermal fatigue +, Water hammer +  and Control Room Habitability +

WCAP-9207 +  and WCAP-8163 +

WCAP-9207 +  and WCAP-8163 +