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Title: Authorization Basis Safety Classification of Transfer Bay Bridge Crane at the 105-K Basins

Abstract

This supporting document provides the bases for the safety classification for the K Basin transfer bay bridge crane and the bases for the Structures, Systems, and Components (SSC) safety classification. A table is presented that delineates the safety significant components. This safety classification is based on a review of the Authorization Basis (AB). This Authorization Basis review was performed regarding AB and design baseline issues. The primary issues are: (1) What is the AB for the safety classification of the transfer bay bridge crane? (2) What does the SSC safety classification ''Safety Significant'' or ''Safety Significant for Design Only'' mean for design requirements and quality requirements for procurement, installation and maintenance (including replacement of parts) activities for the crane during its expected life time? The AB information on the crane was identified based on review of Department of Energy--Richland Office (RL) and Spent Nuclear Fuel (SNF) Project correspondence, K Basin Safety Analysis Report (SAR) and RL Safety Evaluation Reports (SERs) of SNF Project SAR submittals. The relevant correspondence, actions and activities taken and substantive directions or conclusions of these documents are provided in Appendix A.

Authors:
Publication Date:
Research Org.:
FFS (US)
Sponsoring Org.:
ENVIRONMENTAL MANAGEMENT (US)
OSTI Identifier:
803033
Report Number(s):
SNF-5848, Rev.0
EDT-601515; TRN: US0300221
DOE Contract Number:
AC06-96RL13200
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 6 Apr 2000
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CLASSIFICATION; DESIGN; EVALUATION; MAINTENANCE; NUCLEAR FUELS; PROCUREMENT; SAFETY; SAFETY ANALYSIS

Citation Formats

CHAFFEE, G.A. Authorization Basis Safety Classification of Transfer Bay Bridge Crane at the 105-K Basins. United States: N. p., 2000. Web. doi:10.2172/803033.
CHAFFEE, G.A. Authorization Basis Safety Classification of Transfer Bay Bridge Crane at the 105-K Basins. United States. doi:10.2172/803033.
CHAFFEE, G.A. Thu . "Authorization Basis Safety Classification of Transfer Bay Bridge Crane at the 105-K Basins". United States. doi:10.2172/803033. https://www.osti.gov/servlets/purl/803033.
@article{osti_803033,
title = {Authorization Basis Safety Classification of Transfer Bay Bridge Crane at the 105-K Basins},
author = {CHAFFEE, G.A.},
abstractNote = {This supporting document provides the bases for the safety classification for the K Basin transfer bay bridge crane and the bases for the Structures, Systems, and Components (SSC) safety classification. A table is presented that delineates the safety significant components. This safety classification is based on a review of the Authorization Basis (AB). This Authorization Basis review was performed regarding AB and design baseline issues. The primary issues are: (1) What is the AB for the safety classification of the transfer bay bridge crane? (2) What does the SSC safety classification ''Safety Significant'' or ''Safety Significant for Design Only'' mean for design requirements and quality requirements for procurement, installation and maintenance (including replacement of parts) activities for the crane during its expected life time? The AB information on the crane was identified based on review of Department of Energy--Richland Office (RL) and Spent Nuclear Fuel (SNF) Project correspondence, K Basin Safety Analysis Report (SAR) and RL Safety Evaluation Reports (SERs) of SNF Project SAR submittals. The relevant correspondence, actions and activities taken and substantive directions or conclusions of these documents are provided in Appendix A.},
doi = {10.2172/803033},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Apr 06 00:00:00 EDT 2000},
month = {Thu Apr 06 00:00:00 EDT 2000}
}

Technical Report:

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  • The purpose of this document is to outline the K Basins 30 ton crane qualification strategy for use in the Spent Nuclear Fuel Project fuel relocation campaign.
  • The Safeguards and Accountability database was used as the primary source document for exposure data for spent N Reactor fuel stored at the K-East and K-West basins. This database is a listing of all keys (ie., groups of fuel discharged from the reactor at the same time), and the exposure for that key, mass of uranium in the key, fuel type (whether Mark IV or Mark IA), and several other parameters. There are nearly five hundred records (keys) in this database. Figure 1 illustrates an N Reactor Mark IV fuel assembly. The axial length of the endcap is approximately 0.19more » inch. Mark IA and Mark IV fuel are low enriched zircalloy-2 clad metallic uranium tube-in-tube assemblies held together with spacers and clips. Unexposed Mark IV fuel assemblies have an enrichment of 0.947 wt% {sup 235}U in both inner and outer tubes. Unexposed Mark IA assemblies have an enrichment of 1.25 wt% {sup 235}U in the outer tube and 0.947 wt% {sup 235}U in the inner tube.« less
  • The PUREX Plant presently contains 2.9 metric tons of an aluminum clad Single Pass Reactor (SPR) fuel which is stored under water in four open top buckets in the PUREX slug storage basin. The PUREX dissolver cells contain approximately 0.5 metric tons of zirconium clad N Reactor fuel which was inadvertently placed into the process cell during charging operations. The dissolver N reactor elements will be recovered from the process floors using new crane operated tools. When the fuel shipment(s) is scheduled, the cask cars will be positioned into the PUREX rail tunnel and the overhead door will be opened.more » All the SPR fuel will be loaded into two cask rail cars inside four casks. The N Reactor fuel will be loaded into a separate rail car inside two or three casks. The car loading is initiated by opening the rail car lid and removing the cask lids. Prior to loading the canisters of N Reactor fuel, the canisters will be refilled with water (as needed) and a lid will be installed. The baskets of SPR fuel or canisters of N Reactor fuel will then be loaded into the casks. The lids to the casks will then be reinstalled and the car lids closed. The rail cars will then be decontaminated as necessary. The cask cars will be shipped either in two shipments or a combined single shipment using the rail route between PUREX and the K Basins. At the basin, the cask car will be positioned in the loadout area. The cask car lid will be opened and a single cask moved into the loadout pit, which is a lowered section of the basin. The cask lid is removed while the cask is lower into the pit. The fuel is then removed from the cask and stored in the basin. The cask is then removed, the lid reinstalled during removal, and the cask replaced into the cask car. This document identifies the hazard classification of the Fuel Transfer from the PUREX facility to K-Basins.« less
  • A nuclear criticality safety analysis was carried out for storing 1450 tons of irradiated Mark-IV fuel assemblies in KE irradiated fuel storage basin using unirradiated fuel critical mass parameters. Calculations in support of the safety analysis considered an alternate to the 1450 ton fuel storage configurations. The alternate storage scheme would utilize all available storage space and increase the capacity of the basin to 1900 tons of fuel. Although the calculations indicated a full utilization of the basin floor space would present no nuclear criticality problems, the acceptance of the 1900 ton storage configuration would be dependent on a seriesmore » of experimental critical mass measurements. The subcritical mass test results are incorporated in the nuclear criticality safety analyses for storing up to 1900 tons of Mark-IV irradiated fuel assemblies in each of the K-Reactor fuel storage basins.« less
  • This document provides the unit dose calculations for a mixture of isotopes.