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Letter type:RS, Technical Specification  and Amendment

Iodine +, Lead +  and Tin +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50 Appendix J +, 10 CFR 50.12 +, 10 CFR 50.65 +, 10 CFR 50.90 +, 10 CFR 50.55a +, 10 CFR 50.54#o +, 10 CFR 50.55a#b2ixE +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +, 10 CFR 36#c5 +  and 10 CFR 50.92#c +

05000373  +, 05000374  +, 00373  +, 00374  +  and 00278  +

Jury K +  and Exelon +

NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +  and NRC Generic Letter 83-33, NRC Positions on Certain Requirements of Appendix R to 10 CFR 50 +

RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +, RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +, RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +, RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +, RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +, RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +, RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +, RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +, RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +, RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +, RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +, RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +, RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +  and RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +  and 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +

NUREG-1493 +, NUREG/CR-4550 +, NUREG/CR-4840 +, NUREG/CR-2300 +, NUREG/CR-4551 +, NUREG/CR-3539 +, NUREG/CR-4220 +, NUREG-1273 +, NUREG/CR-4330 +, NUREG/CR-5042 +, NUREG/CR-5250 +, NUREG/CR-5305 +, NUREG/CR-2015 +, NUREG/CR-4885 +, NUREG/CR-4586 +, NUREG/CR-2462 +, NUREG/CR-2405 +, NUREG/CR-2320 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 +, NUREG-1488, Notice of Draft NUREG 1488, Revised Livermore Seismic Hazard Estimates for 69 Nuclear Power Plant Sites East of Rocky Mountains +, NUREG/CR-4832, Forwards Unpublished Documents Used as Ref in Rept (NUREG/CR-4832) for Deposit in PDR +  and NUREG/CR-5088, Discusses Proposed Actions Re SECY-89-170, Fire Risk Scoping Study:Summary of Results & Proposed Staff Actions, (NUREG/CR-5088).Need for Addl Research Will Be Considered Following Final Definition of fire-related Parts +

SP +  and Emergency Plan +

Regulatory Guide 1.163 +  and Regulatory Guide 1.174 +

2E-02 +, 1E-8 +, 1E-5 +, 1E-4 +, 1E-3 +, 1E-7 +, 2E-2 +, 3E-8 +, 8E-3 +, 2E-4 +, 1E-1 +, 5E-3 +, 3E-2 +, 4E-2 +, 7E-3 +, 9E-1 +, 235X-2 +, 4E4-1 +, 2E-1 +, 87E-07 +, 70E-08 +, 49E-07 +, 26E-09 +, 39E-07 +, 70E-02 +, 70E-03 +, 81E-07 +, 7a-7d +, 605E-13 +, 68E-08 +...

Peach Bottom +, LaSalle +  and Trojan +

Illinois +, Washington +, Florida +  and Iowa +

Feedwater +, Service water +, Emergency Diesel Generator +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Remote shutdown +, Decay Heat Removal +, Main Steam +  and Containment Spray +

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, High winds +, Fire Barrier +, Tornado Missile +, Internal Flooding +, Probabilistic Risk Assessment +, Coatings +, Tornado-Generated Missile +, Tornado Generated Missile +, Local Leak Rate Testing +, Large early release frequency +, Loss of Offsite Power +, Integrated leak rate test +, Earthquake +, Maintenance Rule Program +, Turbine Missile +, Power Uprate +  and Affidavit +