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Removal plan for Shippingport pressurized water reactor core 2 blanket fuel assemblies form T plant to the canister storage building
| 题名： | Removal plan for Shippingport pressurized water reactor core 2 blanket fuel assemblies form T plant to the canister storage building |
| 作者： | Lata; |
| 关键词： | 05 NUCLEAR FUELS; CONTAINERS; SPENT FUELS; PWR TYPE REACTORS; RADIOACTIVE MATERIALS; STORAGE; TRANSPORT; BUILDINGS |
| 摘要： | This document presents the current strategy and path forward for removal of the Shippingport Pressurized Water Reactor Core 2 blanket fuel assemblies from their existing storage configuration (wet storage within the T Plant canyon) and transport to the Canister Storage Building (designed and managed by the Spent Nuclear Fuel. Division). The removal plan identifies all processes, equipment, facility interfaces, and documentation (safety, permitting, procedures, etc.) required to facilitate the PWR Core 2 assembly removal (from T Plant), transport (to the Canister storage Building), and storage to the Canister Storage Building. The plan also provides schedules, associated milestones, and cost estimates for all handling activities. |
| 总页数： | 286p |
| 报告类型： | 科技报告 |
相关文献
- Performance Specification Fuel Drying and Canister Inerting System for Shippingport Pressurized Water Reactor (PWR) Core 2 Blanket Fuel Assemblies Stored Within Shippingport Spent Fuel Canisters
- Thermal assessment of Shipping port pressurized water reactor blanket fuel assemblies within a multi-canister overpack within the canister storage building
- Performance Spec. for Fuel Drying and Canister Inerting System for PWR Core 2 Blanket Fuel Assemblies Stored within Shipping Port Spent Fuel Canisters
- ALARA Analysis for Shippingport Pressurized Water Reactor Core 2 Fuel Storage in the Canister Storage Building
- Shippingport Spent Fuel Canister Design Report Project W-518
- CSER 00-007 Addendum 1: Criticality Safety Evaluation of the Shippingport PWR Core 2 Blanket
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