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ML15117A551 +
10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 70 +, 10 CFR 50.36 +, 10 CFR 30 +, 10 CFR 50.59 +, 10 CFR 20.1001 +, 10 CFR 40 +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 140 +, 10 CFR 20.1302 +, 10 CFR 50.4 +, 10 CFR 50.62 +, 10 CFR 50.82 +, 10 CFR 50.83 +, 10 CFR 50.90 +, 10 CFR 50 Appendix H +, 10 CFR 50 Appendix I +, 10 CFR 54.3 +, 10 CFR 73.21 +, 10 CFR 50.36a +, 10 CFR 50.7l#e +, 10 CFR 50.51 +, 10 CFR 50.54#p +, 10 CFR 50.51#b +, 10 CFR 50.36#c2iiA +...
Regulatory Guide 1.183 +, ML003734190 +, ML14217A072 +, ML15117A551 +, ML14304A588 +, ML14227A912 +, RIS 2014-09, Maintaining the Effectiveness of License Renewal Aging Management +, ML13323A516 +, ML13323A518 +, ML041280490 +, ML14288A317 +, ML082330233 +, BVY 15-012, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 5 +, ML14231A017 +, BVY 15-001, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel +, BVY 14-049, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 3 +, BVY 14-037, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 2 +, BVY 14-030, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 1 +, BVY 14-010, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition +, BVY 13-096, Technical Specifications Proposed Change No. 307 Revision to Mitigation Strategy License Condition and Technical Specification Administrative Controls for Permanently Defueled Condition Vermont Yankee Nuclear Power Station + and BVY 13-079, Notification of Permanent Cessation of Power Operations +
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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) +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months) +, 0.00194 d (0.0467 hours, 2.777778e-4 weeks, 6.3924e-5 months) + and 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months) +
Tritium + and Iodine-131 +
October 7, 2015 +
ML041280490 +, BVY 15-012, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 5 +, BVY 14-010, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition +, BVY 13-097, Proposed Change 306, Areva Document No. 32-9145461-001, Vynpp - Re-analysis of Ast/Fha Radiological Consequences with Open Containment +, BVY 13-093, Request for Exemption from Specific Provisions in 10 CFR 73.55 +, BVY 13-079, Notification of Permanent Cessation of Power Operations +, BVY 11-026, Notification of Revised Regulatory Commitment +, CNRO-2006-00021, Entergy Operations, Inc., Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits +, BVY 04-115, Second Updated Submittal of Security Plan + and BVY 12-081, Flooding Walkdown Report - Entergys Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident +
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17:49:00, 10 January 2025 +
90 +
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CAC:MF3714 + and TAC:MF3714 +
Approval +
October 7, 2015 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Core Standby Cooling System +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray + and Low Pressure Coolant Injection +
Issuance of Amendment for Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition +
Safe Shutdown +, Time of Discovery +, Shutdown Margin +, Safety Limit Minimum Critical Power Ratio +, High Radiation Area +, Offsite Dose Calculation Manual +, Probabilistic Risk Assessment +, Cyber Security +, Aging Management +, Missed surveillance +, Scram Discharge Volume +, Annual Radiological Environmental Operating Report +, Process Control Program +, Loss of Offsite Power +, Safeguards Contingency Plan +, License Renewal +, Fuel cladding +, Fire Protection Program +, Power Uprate +, Water hammer +, Spent fuel rack + and Operational convenience +
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