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Letter, Technical Specification  and Bases Change

Iodine +, Lead +, Aluminum +  and Sulfur +

10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50.59 +, 10 CFR 50.4 +, 10 CFR 72.48 +, 10 CFR 50.36#c2ii +, 10 CFR 50.59#d2 +, 10 CFR 26.205#c +, 10 CFR 72.48#d2 +  and 10 CFR 50.71#e4 +

NOC-AE-14003189, Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights-from the Fukushima Dai-ichi Accident - Phase 2 Staffing Assessment +, NOC-AE-13002989, Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - Phase 1 Staffing Assessment +, NOC-AE-10002558, Response to Licensee Commitment Regarding a Request for Exemption from Certain Requirements of the Fitness for Duty Rule for Managing Fatigue +  and NOC-AE-23003972 +

05000498  +, 05000499  +, 07201041  +, 00498  +  and 00499  +

South Texas +  and Richards A +

NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +  and NRC Generic Letter 94-01, Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators +

ML23177A252 +, ML23177A252 +, ML23177A252 +, ML23177A252 +, ML23177A252 +, ML23177A252 +, ML23177A252 +, ML23177A252 +, ML23177A252 +, ML23177A252 +, ML23177A252 +, ML23177A252 +, ML23177A252 +  and ML23177A252 +

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 0.0231 d (0.556 hours, 0.00331 weeks, 7.61e-4 months)  +

NEI 97-06, Steam Generator Conditioning Monitoring Report +, NEI 12-01, Response to March 12, 2012, Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency +  and NEI 99-04, Guideline for Managing NRC Commitment Changes +

Regulatory Guide 1.137 +  and Regulatory Guide 1.108 +

SR-4.8.1.1.2 +, SR-4.8.1.1.1 +  and SR-4.4.6.2.1 +

South Texas +  and 07201041 +

Texas +  and Washington +

Steam Generator +, Reactor Coolant System +, Residual Heat Removal +, Main Steam Safety Valve +  and Decay Heat Removal +

TS-3.4.5 +, TS-3.4.6.1 +  and TS-6.8.3.m +

Office of Nuclear Material Safety and Safeguards +, Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Internal Flooding +, Temporary Modification +, Aging Management +, Surveillance Frequency Control Program +, Loss of Offsite Power +, License Renewal +, Exemption Request +, Pressure Boundary Leakage +, Offsite Circuit +, Unidentified leakage +, Overspeed trip +, Overspeed +  and Operational leakage +