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.• Appendix J- Applicable or Relevant and• ^•••' DOSlRlr2oaI-t t' Appropriate Requirements Rev.4 1 Man BA Redline/S(ri{.eout r_^' approxitnately 3 x 10'+risk)' g leatiup level is applied during remedial actions aetiv+ties to achieve the CERCLA risk range. Standards for maximum contaminant levels for certain radionuclides, based on an annual dose limit, are provided in 40 CFR 141. The following information provides an analysis ofhow each alternative is anticipated to comply with the ARARs and TBCs for soil cleanup and protection of groundwater and the Columbia River. J.2.1 Full Removal and Disposal Alternative (Alternative 1) Removal and subsequent treatment and disposal of the 221-U Facility and underlying contaminated soils will provide compliance with all soil and groundwater/river cleanup standards associated with an industrial land use at the 221-U Facility. J.2.2 Containment Alternatives (Alternatives 3,4, and 6) Containment will provide compliance with all soil and groundwater/river cleanup standards for both nonradioactive and radioactive constituents by preventing exposure to centaminated wastecontaminants and ensuring that funher mobilization of contaminants to groundwater and to the river is prevented. J.3 WASTE MANAGEMENT STANDARDS The Resource Conservation and RecoveryAct of1976 (RCRA) regulates the generation, transportation, storage, treatment, and disposal of solid and hazardous waste. Authority to implement much of RCRA has been delegated to the state and is implemented via WAC 173-303 (for dangerous waste) and WAC 173-304 ( for solid nondangerous waste). Authority for land disposal restrictions (LDRs) has been delegated to the state of R'ashin¢ton. which administers all federal LDRs thfo%&hbv reference to a 0 CFR 26g. in addition.Washinaton ndministcrc,-atitzr-tltaa state-only LDRs throueh WAC 173-303-140 . The Atomic EnergyAct oj1954 (AEA) establishes standards for the management of radioactive wastes. Regulations pertaining to the management and land disposal of low-level radioactive waste at NRC-licensed facilities are contained in 10 CFR 61. These regulations include barrier design requirements that include protection of humans from inadvertent contact with waste above acceptable levels at any time after the loss of active institutional controls. The Toxic Substances Control Act of1976 (fSCA) and its implementing regulations (40 CFR 761) govern the storage, treatment, and disposal of extwiais-eeatainint polychlorinated biphenyls (PCBs) ^,•aste . The 1002 amenchu remediation wastes=Oiat ,Lchich does not depend on the current concentration of PCBs in the ^-, waste for it4-spilis that occurred (1) after Apri11978 and the original source contained PCBs at 500 ppm or greater, or, (2) after July 1979 and the original source contained PCBs at 50 ppm or greater. Risk-based determinations can be made for PCB rcmediation waste under th s- FGwl Fearlb!lity Studyfor the Canyon Disposition !nltWtive (SZI-U Faelliry) girl awt.%0 340 !September 2002 • J-3
t^ ^ Appendix J-Applicable or Relevant and,- • DoFJRL2001t 1' ^ •Appropriate Requirements Rev.4 1 Draft Ba. ^ =•, Redline/Strikeout Alternatives that involve facility demolition or the removal of waste or contaminated media or ex situ treatment may generate solid, dangerous, or radioactive waste. The RCRA requirements are applicable to those alternatives that margenerate, treat, store, or dispose of solid or dangerous waste. The substantive requirements of 10 CFR 61 are potentiall^• relevant and appropriate to those alternatives that g0liffater}reat-Pr-dispose of radioactive waste in situ .-,44 Waste would be disposed to the Environmental Restoration Disposal Facility (ERDF), which is designed to meet the requirements of RCRA. TSCA, and 8>zlow-Ievel radioactive waste standards. For alternatives that involve leaving solid or dangerous waste in place, RCRA performance standards for landfill covers are relevant and appropriate and will be incorporated into the design. Cover performance standards contained in 10 CFR 61 are potentiallv relevant and appropriate to the in-place disposal of radioactive waste. The following information provides an analysis of how each alternative is anticipated to comply with the ARARs and TBCs for waste management. J3.1 Full Removal and Disposal Alternative (Alternative 1) Large quantities of soil and debris (e.g., piping, structures, and cleanup materials) will be generated under this alternative. Some of these wastes may require treatment or a waiver from LDRs i+:oi•.kr-to be disposed at the ERDF or offsite waste disposal facility. It is anticipated that compliance with waste management standards will be achievable for the types of waste and contaminants that may Ae-required to he treatmented andtor disposed. Due to the potential for much greater quantities of waste to be generated from this alternative, waste management ARAR/1BC compliance will be more complex for this alternative rslati+e te than for the disposal alternatives. Treatment actions may generate treatment residuals that potentially could require treatment prior to disposal at the ERDF or another disposal unit to comply with applicable requirements . J3.2 Containment Alternatives (Alternatives 3,4, and 6) collection m•stems willwakt be souehlrrwsired hecauso the huttom containment scstem (the floor Flrtal Feasibility Studyfor the Canyon Disposition In(t(atfve (111-U PacUtry) 9 ipl iaAos '100 FSeptember ^0" _ .14
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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 (0-^, (^N 1 2 3 r• • .`•
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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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I f^ ^ DOE!RL-2001-29 Ikaft D Redli
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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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^ ^ 1 2 DOFJRL-2001-11 Rev.A 1 Dra(
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. . .,.. Appendix C - Risk Modeling
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t^ Appendix C - Risk Modeling of an
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(_^% ^ ^ 11 Appendix C - Risk Model
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(0"% t^ DOFJRL-2001-1 l Rev. N 1 Dr
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1 ' ^ ^ DOEJRL-2001-1 t Rev.H1 nraf
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Appendix D- Slope Stability Analysi
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Appendix D - Slope Stability Analys
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(^N Appendix D- Slope Stability Ana
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• Appendix D-Slope Stability Anal
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^• r^, r^ 2 3 4 5 6 7 Appendix D-
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^ Appendix D-- Slope Stability Anal
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^ (00h^' ^ 2 DOFIRI^2001-I I Rev. J
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t^` ^ ^ 1 2 DOFJRL-2001-11 Rev. JDr
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Appendix E - Detailed Description o
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Appendix E- Detaiied Description of
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t^' Appendix E -Detailed Descriptio
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f,^N Appendix E - Detailed Descript
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Appendix F - Detailed Description o
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Appendix F -Detailed Description of
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Appendix T- Detailed Description of
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Appendix F -Detailed Description of
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(O^N Appendix F - Detailed Descript
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Appendix E- Detailed Description of
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..^•. , Appendix F- Detailed Desc
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(^, Appendix F - Detailed Descripti
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Appendix F-Detailerl Description of
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^`} Appendix F - Detailed Descripti
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^ (10^' (^N DOF/RL-2001-11 Rev. AjD
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^N r^ 1 n DOF/RLr2061-1 l ' Rev. I
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1 ^ (^N ^ DoFJRL-M-t t ^ Rev. I Dnf
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Appendix G -Detailed Description of
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Appendix G - Detailed Description o
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Appendix G- Detailed Description of
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o"^, Appendix G - Detailed Descript
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Appendix G- Detailed Description of
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^• ^ Appendix G - Detailed Descri
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^ ^ t"'^N 1 2 DOElRL-2001-I1 Rev. 9
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t^N (M"N Final Feasibifity Stady ja
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