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Response to Request for Additional Information (RAI)  and Letter type:CNL

10 CFR 50 Appendix A +, 10 CFR 50.2 +, 10 CFR 50.55 +, 10 CFR 50.90 +, 10 CFR 50.54 +, 10 CFR 50.55a +, 10 CFR 50.36#c3 +, 10 CFR 50.36#c2ii +, 10 CFR 50.55a#g +, 10 CFR 50.55a#f +  and 10 CFR 50.55a#c +

05000327  +, 05000328  +, 00327  +  and 00328  +

CNL-21-026, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03) +, ML19323E667 +, NUREG-1431 Volume 1, Rev. 5, Standard Technical Specifications Westinghouse Plants: Specifications +, CNL-22-024, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 +, ML22304A186 +, ML22167A167 +, CNL-24-071, Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the (SQN-TS-24-04) +, ML24317A001 +, ML25024A017 +, ML17026A091 +  and ML25028A375 +

Tennessee Valley Authority +  and Hulvey K +

CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +, CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +  and CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit +

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

NUREG-1431 +, NUREG-0677 +  and NUREG-0667, 06-10-80 Report on NUREG-0667 Transient Response of Babcock - Wilcox-Designed Reactors +

EPID:L-2022-LLR-0072 +  and EPID:L-2024-LLA-0156 +

Regulatory Guide 1.200 +  and Regulatory Guide 1.192 +

SR-3.4.13.1 +  and SR-3.4.14.1 +

Tennessee +, Washington +  and New York +

Reactor Coolant System +, Shutdown Cooling +  and Residual Heat Removal +

TS-3.4.14 +, TS-3.4.13 +  and TS-3.4.14.1 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Internal Flooding +, Probabilistic Risk Assessment +, Incorporated by reference +, Surveillance Frequency Control Program +, Large early release frequency +, Operational leakage +  and Pre-submittal +