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^ Appendix F - Detailed Description of Alternative 3: DOEfRL-2001-1t I Entombment with Internal Waste Disposal Rev. eJ_P_raft n Rcdlinc/Strikcout 1 F.1 PREPARE EXISTING COMPLEX 2 3 This function provides for the necessary physical modifications to the existing 221-U complex, 4 including related programs, administrative and physical controls, safeguards, and infrastructure 5 to prepare the complex for the subsequent operating and closing functions. The purpose of these 6 activities would be to establish a complex-wide configuration designed to support waste 7 processing, decontamination, demolition, and closure. 8 9 F.1.1 Control Hazards 10 I,1 Preparing for Alternative 3 would include controlling hazards at the site. This control would 12 begin with preparation of a decommissioning plan. The plan would include, but not be limited 13 to, such things as readiness evaluations, hazard classifications, waste designation, a waste 14 profile. a health and safety plan, and site-specific waste management instructions. This planning 15 would be followed by hazardous material and radioactivity surveys. 16 17 F.1.1.1 Establish Hazards Protection. The potential personnel and environmental hazards 18 associated with this alternative are a combination of high hazards normally encountered during 19 routine operations and those hazards involving the nonroutine activities of large-scale demolition 20 operations. SpeciBcally, they are industrial and radiological in nature. Hazard mitigation would (0^'21 involve the implementation of engineering and adminisuative controls that address both 22 personnel and environmental protection. 23 24 F.l.1.1.1 Control Health and Safety Hazards. Personnel would encounter industrial hazards 25 during site preparation, facility operation, and site closure. These hazards would be similar to 26 those that are encountered on any large-scale construction and demolition project, including 27 unique hazards associated with demolition operations that include crane operation, concrete 28 sawing, and excavator operation. Typical hazards would include such things as moving 29 machinery, falling, tripping, cutting, sound exposure, and dust inhalation. The risk of injury due 30 to these hazards is addressed in national Occupational Safety and Health Administration (OSHA) 31 and Washington Industrial Safety and Health Administration safety regulations, as well as the 32 <strong>Hanford</strong> <strong>Site</strong>-specific procedures that implement the codes. Compliance with the applicable 33 safety codes, regulations, and procedures would mitigate the risk posed by industrial hazards. 34 35 Physical and administrative controls would be implemented to control industrial hazards. 36 Personnel access control to the complex would be established by installing a perimeter exclusion 37 fence. Access to the local work site would be controlled and maintained with barriers and signs 38 warning personnel of the specific work site hazards. Heavy equipment would use audible 39 warning signals when backing up. Personnel would wear hard hats, safety glasses, and safety 40 shoes, as a minimum, and any additional safety equipment as required by job-specifc 41 requirements. Administrative controls would include the implementation of programmatic plans, 42 procedures, job safety analyses, and applicable work permits to operate hazardous equipment and ("%43 enter hazardous areas. 44 Final Feasibitiry Stady for the Canyon Disposition Initiative (221-U Facility) ivnc :2o: F-5
Appendix T- Detailed Description of Alternative 3: DOEIRI^2001-1 t Entombment with Internal Waste Disposal Rev. al nrafi n r., R dline)Strikeout I High radiation arcas and very high radiation areas would be encountered and would primarily be 2 a concern during equipment removal. For example, approximately 25% of the cells have 3 equipment and materials that have high radiation levels that exceed 1,000 mremJhr. The 4 maximum gamma dose rate in cell 30 was 190,000 mrem/hr (BHI 2001a). Also, the most 5 significant radiological hazard anticipated during operational activities would be the generation 6 of airborne contamination. Mitigation of airborne contamination would be accomplished with 7 local exhaust ventilation of the decontamination equipment, personal protective equipment, 8 existing facility exhaust system, and administrative controls and physical controls. 9 Decontamination or fixing of loose or stnearable contamination would be performed prior to any 10 removal/demolition activities. Radiological limits for worker protection are provided in 10 Code I1 of Federal Regulations (CFR) 835. 12 13 Nonroutine activities would require special procedures and equipment so that the risk of 14 exposure is properly mitigated. Safety criteria would be determined on a case-by-case basis; 15 however, criteria would require that exposures be as low as reasonably achievable (ALARA). 16 17 Administrative controls include radiation work permits, exposure limits, and escort requirements. 18 Physical controls include barriers, postings, and personnel surveys. In accordance with site 19 procedures, administrative and physical controls applicable to this project would be defined in e,,20 job-specific work plans and procedures. Compliance with the job-specific work practices and >_I procedures would ensure that personnel exposures do not exceed allowable limits. 22 23 Installing a perimeter fence and implementing a site-entry procedure would control access to the 24 work site. The procedure would require either training or escorts for site visitors. Additionally, 25 operating methods that depend primarily on equipment would be used, and the number of 26 operating personnel would be minimized to the extent practicable. 27 28 F1.1.1.2 Control Envtronmental Hazards. The potential dispersion/migration of dangerous 29 and)or radioactive waste would be an inherent risk of Alternative 3. Wind is the principal cause 30 of dispersion, and water is the main transport mechanism for migration. Dangerous/radioactive 31 contaminants could also migrate through the inadvertent contamination of vehicles and personnel 32 leaving the project site. Radiological limits for exposure to the public are provided by 33 DOE Order 5400.5, Radiation Protection ofthe Public and the Environment. 34 35 Implementing a combination of procedural and physical controls would mitigate wind dispersion 36 of contaminants. Procedural controls typically consist of wind-speed restrictions on work 37 activities. Physical controls include spray fixatives ( i.e., water sprays and chemical coagulants). 38 minimizing the size of the work area, pressurized application of concrete slurries through a hose 39 and nozzle (guniting), clean fill, and/or containerization. Radiation air monitoring would be 40 performed on the work site perimeter to confirm the effectiveness of airborne contamination 41 control. 42 1'43 The potential for water migration would also be mitigated by implementing a combination of 44 procedural and physical controls. Procedural controls would consist of work restrictions during 45 precipitation events if the potential for contaminant migration exists. Physical controls would Final Feasibility Studyfor the Canyon Disparftion initiative (221•U FacRity) nc 1 00 1 F-6
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AR TARGET SHEET The following docum
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(^N r^ r Proposed Plan for the Cany
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^ (^N t^ the steHitFths+amedielaeti
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o"N DOF/RIr2001-29 Draft D Redline/
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(^N i0,"% / ' DOF/RL-2001-29 Draft
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! ' t^ Project Prepare the existing
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f ' ^ rN 100 I Noise, Visual, and A
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^ POINTS OF CONTA CP ^ U.S. Drnartm
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f^ n DOF/RL-2001-29 Draft D Redlinc
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noFIRL-2001-11 Rev. p 1 1)raft P ^
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. . .,.. Appendix C - Risk Modeling
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t^ Appendix C - Risk Modeling of an
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1 ' ^ ^ DOEJRL-2001-1 t Rev.H1 nraf
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t^N (M"N Final Feasibifity Stady ja
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,.r.. . Appendix H - Detailed Descr
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^ DOF/RL-2001-11 I Appendix I - Dec
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^ r^, TABLES DOFJRIr2001-11 • Rev
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^ Appendix J- Applicable or Relevan
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^ Appendia J- Applicable or Relevan
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