NRR RAI Answers Will Prevent Any SCE Restart At San Onofre
The NRC Office of Nuclear Reactor Regulation has requested from Edison in a letter dated December 26, 2012, the following additional information (RAI #32): “Please clarify how the information submitted by SCE demonstrates: NRRRAI#32(1) that the structural integrity performance criterion in TS 126.96.36.199.b.1 is met for operation within current licensed limits up to the licensed Rated Thermal Power (RTP or 100% Power), or NRRRAI#32(2) provide an operational assessment that includes an evaluation of steam generator Tube-to-Tube Wear (TTW) for operation up to the RTP.”
The DAB Safety Team’s Response:
Answer to NRRRAI#32(1): As shown in the linked Response to NRR RAI#32 - Technical, by operating the “Defectively Designed and Degraded” Unit 2 Replacement Steam Generators (RSGs), SCE CANNOT DEMONSTRATE [with all the World’s Expert’s Assistance - emphasis added] that ALL in-service RSGs tubes would retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, cool down and all anticipated transients included in the design specification) and design basis accidents in accordance with SONGS Unit 2 Technical Specifications structural integrity performance criterion in TS 188.8.131.52.b.1.
Answer to NRRRAI#32(2): As shown in the linked Response to NRR RAI#32 - Technical, SCE CANNOT PROVIDE AN ACCEPTABLE OPERATIONAL ASSESSMENT TO THE NRR, which demonstrates that steam generator Tube-to-Tube Wear (TTW) for operation up to the RTP would not cause a tube leak in order to comply with Code of Federal Regulations, 10 CFR Part 50 Appendix A, General Design Criteria 14, “Reactor Coolant Pressure Boundary—shall have “an extremely low probability of abnormal leakage…and gross rupture.”