The Wolsong Nuclear Power Plant (NPP) operates an on-site spent fuel dry storage facility using concrete silo and vertical module systems. This facility must be safely maintained until the spent nuclear fuel (SNF) is transferred to an external interim or final disposal facility, aligning with national policies on spent nuclear fuel management. The concrete silo system, operational since 1992, requires an aging management review for its long-term operation and potential license renewal. This involves comparing aging management programs of different dry storage systems against the U.S. NRC’s guidelines for license renewal of spent nuclear fuel dry storage facilities and the U.S. DOE’s program for long-term storage. Based on this comparison, a specific aging management program for the silo system was developed. Furthermore, the facility’s current practices—periodic checks of surface dose rate, contamination, weld integrity, leakage, surface and groundwater, cumulative dose, and concrete structure—were evaluated for their suitability in managing the silo system’s aging. Based on this review, several improvements were proposed.

1. Introduction
2. License Renewal Guidance for DryStorage Systems
3. Aging Management Programs for DryStorage Systems
4. AMP Analysis Applicable to Silo DryStorage Systems
    4.1 Monitoring Concrete Structures (S1)
    4.2 Monitoring of Protective Coating onCarbon Steel Structures (S2)
    4.3 Monitoring the Outer Surface of Basket(M1) and the Leakage of Basket Welds (M3)
    4.4 Monitoring the Structural/FunctionalIntegrity of Internal Structures (M5)
5. Review of Aging Management for theSilo Dry Storage System
    5.1 Surface Dose Rate Measurement
    5.2 Measurement of Contamination
    5.3 Inspection of Shielding Plug Welds
    5.4 Containment Boundary LeakageInspection
    5.5 Surface Water and GroundwaterInspections
    5.6 Cumulative Dose Assessment
    5.7 Concrete Integrity Inspection
6. Conclusion
Conflict of Interest
Acknowledgements

• Donghee Lee(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
• Sunghwan Chung(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
• Yongdeog Kim(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
• Taehyung Na(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea) Corresponding author