Letter Sequence Meeting |
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Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: ML20129J487, ML20132B636, ML20133F596, ML20133F656, ML20133F674, ML20134A330, ML20134A495, ML20135B105
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MONTHYEARML20134A2221983-02-18018 February 1983 Submits Daily Highlights.Usgs & FEMA Transmitted Draft Rept Assessing Potential Hazard to Towns of Kelso & Longview, Wa from Breach of Spirit Lake Natural Dam on Mount St Helens Project stage: Draft Other ML20134A2441983-02-24024 February 1983 Informs of Acceptance of plant-specific Licensing Action Re Review of Draft Usgs/Fema Rept on Possible Hazards Posed by Failure of Spirit Lake Dam.Scheduled Target Date Is 830301.Supporting Documentation Encl ML20134A3301983-03-29029 March 1983 Advises That Charges to TAC 49636 Re Possible Hazards Posed by Failure of Spirit Lake Dam Valid.Tac Not Included in List of plant-specific Licensing Actions for FY83.Related Info Encl Project stage: Other ML20133F5421983-04-0101 April 1983 Notification of 830408 Meeting to View Slides of Spirit Lake & Area,To Learn Observations of Visited Areas & to Discuss Future NRC Action Project stage: Meeting ML20133F7861983-05-12012 May 1983 Summarizes 830511 Meeting at Corps of Engineers Ofc in Portland,Or Re Determination of Flood Elevations at Facility Resulting from Breach of Debris Barrier at Spirit Lake,Wa. Related Info Encl Project stage: Meeting ML20133F5961983-06-0101 June 1983 Certifies That Funds Authorized for Interagency Agreement NRC-03-83-109 Entitled, Analysis of Potential Flood Levels at Trojan Nuclear Power Plant. Estimates Completion of Phase 1 2 Wks After Initiation of Work Project stage: Other ML20132B6361983-09-15015 September 1983 Forwards Util 830902 Response to NRC Questions on Util 830701 Submittal Re Potential Mudflows from Assumed Failure of Spirit Lake Blockage.Util Consultant Final Rept Also Encl.W/O Rept Project stage: Other ML20133F6561983-12-0505 December 1983 Forwards Summary of Corp of Engineers Actions to Solve Spirit Lake Problem Project stage: Other ML20132B7591984-02-13013 February 1984 Forwards USGS Geologic Hazards Bulletins Describing Recent Mount St Helens Activity Through 840207 & USGS Review of Recent Corps of Engineers Rept Re Proposed long-term Engineered Solutions to Draining Spirit Lake Project stage: Approval ML20134A4831984-02-21021 February 1984 Informs of 840223 Meeting W/Usgs & Util to Discuss Analysis of Flooding Consequences of Breakout of Spirit Lake Blockage at Facility Project stage: Meeting ML20134A4951984-03-29029 March 1984 Accepts plant-specific Licensing Action Re Spirit Lake Blockage.Scheduled Target Date Is 840409 Project stage: Other ML20132C3611984-08-0808 August 1984 Requests Issuance of Final Safety Evaluation Re Refined Sediment Transport Routing Model to Study Impacts of Spirit Lake Breakout on Columbia River.Fema to Util Summarizing USGS Study Encl Project stage: Approval ML20133F6741984-12-31031 December 1984 Preliminary Estimate of Possible Flood Evaluation in Columbia River at Trojan Nuclear Power Plant Due to Failure of Debris Dam Blocking Spirit Lake,Wa Project stage: Other IR 05000344/19850131985-05-28028 May 1985 Insp Rept 50-344/85-13 on 850402-0513.No Violations Noted. Major Areas Inspected:Operational Safety Verification, Corrective Action,Maint,Surveillance,Followup on Previous Insps,Refueling Activities & Operation Project stage: Request ML20129H7091985-05-28028 May 1985 Forwards Request for Addl Info Re Response to Generic Ltr 83-28, Generic Implications of Salem ATWS Events, Concerning Position on post-maint Operability Testing of safety-related Components.Response Requested within 45 Days Project stage: RAI ML20128G3561985-06-26026 June 1985 Safety Evaluation Re Util 831104 Response to Generic Ltr 83-28,Item 1.1, Post-Trip Review. Subj to Successful Implementation of Listed recommendations,post-trip Review Program & Procedures Acceptable Project stage: Approval ML20128G3351985-06-26026 June 1985 Forwards Safety Evaluation Re 841104 Response to Generic Ltr 83-28,Item 1.1, Post-Trip Review. Post-trip Review Program Acceptable,Subj to Successful Resolution of Independent Assessment of Event Following Trip Project stage: Approval ML20132A4561985-07-11011 July 1985 Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Item 4.5.1 Re Reactor Trip Sys Reliability Based on Commitment to Modify Reactor Trip Breakers Project stage: Approval ML20132A4401985-07-11011 July 1985 Forwards Safety Evaluation Addressing Generic Ltr 83-28, Item 4.5.1 Re Reactor Trip Sys Reliability (Sys Functional Testing).Util Satisfactorily Completed Actions Required, Based on Commitment to Modify Reactor Trip Breakers Project stage: Approval ML20132D3111985-07-16016 July 1985 Safety Evaluation Concluding That Breakout of Spirit Lake Would Not Affect Safe Operation of Plant.Outlet Tunnel Reduces Threat of Breakout.Two Map Diagrams Encl Project stage: Approval ML20132D3041985-07-16016 July 1985 Forwards Safety Evaluation Concluding That Breakout of Spirit Lake Would Not Affect Safe Operation of Plant.Outlet Tunnel Constructed to Reduce Threat of Potential Debris Dam Failure & Breakout of Lake Project stage: Approval IR 05000344/19850161985-07-19019 July 1985 Insp Rept 50-344/85-16 on 850514-0701.Violation noted:4 of 12 Spent Fuel Pool Racks Not Verified by Signature as Having Second Set of Rack Feet Properly Installed Project stage: Request ML20129J4871985-07-19019 July 1985 Provides Addl Response to Generic Ltr 83-28 Re Required Actions Based on Generic Implications of Salem ATWS Events, in Response to NRC 850528 & 0626 Ltrs.Operating Experience Program Developed Per NUREG-0737,Item I.C.5 Project stage: Other ML20135B1051985-08-28028 August 1985 Discusses LER 84-021 Re Silt Accumulation on Svc Water Strainers on 841011 & 30.Util Solution to Change Strainer Mesh from 10 Mils to 20 Mils Acceptable.Issue Closed Project stage: Other ML20135H4821985-09-0505 September 1985 Safety Evaluation Supporting Util 850719 post-trip Review Program Description & Procedures,Per Item 1.1 of Generic Ltr 83-28 Project stage: Approval ML20135H4801985-09-0505 September 1985 Forwards Revised Safety Evaluation Re Util 850719 Responses to NRC 850626 Open Issues Concerning Generic Ltr 83-28,Item 1.1, Post-Trip Review. Program & Procedures Acceptable Project stage: Approval ML20133H7541985-10-10010 October 1985 Forwards Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Item 4.1,concerning Reactor Trip Sys Reliability (vendor-related Mods).Actions Specified by Item 4.1 Satisfactorily Completed Project stage: Approval ML20133H7701985-10-10010 October 1985 Safety Evaluation Re Util Response to Generic Ltr 83-28, Item 4.1,concerning Reliability of Reactor Trip Sys.Actions Specified by Item 4.1 Satisfactorily Completed,Based on Licensee Review of Sources of vendor-recommended Mods Project stage: Approval ML20133H8401985-10-11011 October 1985 Forwards Safety Evaluation Re Util Response to Generic Ltr 83-28,Items 3.1.1 & 3.1.2 Concerning post-maint Testing to Verify Operability & Guidance for Reactor Trip Sys Components.Util Satisfied Actions Requested by Item 3.1.2 Project stage: Approval ML20133H8571985-10-11011 October 1985 Safety Evaluation Re Util Response to Generic Ltr 83-28, Items 3.1.1 & 3.1.2 Concerning post-maint Testing to Verify Operability & Guidance for Reactor Trip Sys Components. Licensee Acceptably Satisfied Actions Requested by Items Project stage: Approval ML20136C6401985-12-20020 December 1985 Forwards Draft SER Re Tech Spec Changes & Draft Transmittal Ltr to Licensee.Proposed Amend to License NPF-1 Approved. SALP Input Also Encl Project stage: Draft Approval ML20214C6381986-02-12012 February 1986 Safety Evaluation Re Util Submittals on Generic Implications of Salem ATWS Event (Generic Ltr 83-28),Items 3.2.1 & 3.2.2. Response Acceptable Project stage: Approval 1984-03-29
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217E9711999-10-13013 October 1999 Submits Notification of Major Changes to Trojan Liquid Radioactive Waste Treatment Sys,Iaw PGE-1201.Detailed Description of Change Provided ML20217C8171999-10-0606 October 1999 Forwards Notice of Receipt of Availability for Comment & Meeting to Discuss License Termination Plan,Per 990805 Application ML20216F7621999-09-23023 September 1999 Forwards Corrected Response to Request 2 Contained in NRC 990920 RAI Re Application of Pacificorp for Transfer of License NPF-1.Response 2 Should Have Stated That Na General Partnership Is Partnership Formed in Nv ML20216F2871999-09-20020 September 1999 Informs NRC of Developments That Have Occurred Since 990524 Application Was Filed Re Pacificorp Transfer of License of FOL NPF-1.NRC Is Urged to Act & Approve Transaction Expeditiously by 990930.Supporting Documentation Encl ML20211Q3281999-09-0909 September 1999 Forwards Insp Rept 50-344/99-06 on 990630-0701,21 & 0408-08. No Violations Noted.Insp Conducted to Review Decommissioning Activities Underway at Trojan Site & to Accompany Shipment of Reactor Vessel to Hanford,Washington for Burial ML20211J2101999-08-30030 August 1999 Forwards Request for Addl Info Re Application for Approval of Proposed Corporate Merger of Pacificorp & Scottishpower ML20211B6611999-08-16016 August 1999 Forwards fitness-for-duty Program Performance Data Rept for Period of 990101-0630,IAW 10CFR26.71(d) ML20211B4091999-08-16016 August 1999 Forwards Environ Assessment & Finding No Significant Impact to Application for an Exemption & License Amend Dated 980129.Proposed Exemption & License Amend Would Delete Security Plan Requirements of 10CFR50.54(p) & 10CFR73.55 ML20211A7131999-08-16016 August 1999 Forwards Environ Assessment & Finding of No Significant Impact to Application for Exemption & License Amend Dtd 980827.Proposed Exemption & License Amend Would Delete EP Requirements of 10CFR50.54(q),10CFR50.47(b) & 10CFR50,app E ML20210R7691999-08-11011 August 1999 Forwards Proposed Rev 23 to PGE-8010, Trojan Nuclear QAP, in Response to NRC 990708 RAI Re Relocation of TS ACs to Qap.Revised QAP Will Be Made Effective Concurrently with Implementation of License Change Application Lca 245 ML20210H5971999-07-27027 July 1999 Forwards Notice of Consideration of Approval of Application Re Merger & Opportunity for Hearing.Notice Being Forwarded to Ofc of Fr for Publication ML20216D6611999-07-23023 July 1999 Submits Summary of Proprietary Submittals for Transtor Part 71 & Part 72 & Trojan ISFSI Applications ML20210F8601999-07-22022 July 1999 Forwards Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar. Changes to Rept Contained in Rev 1 Received NRC Approval by Ltr ML20210A6401999-07-19019 July 1999 Corrects Ref in Item 4 of Which Constitutes Rev 2 of Authorization from Wf Kane, for Trojan Reactor Vessel Package as Approved Package for Shipment Under General License,Subj to Listed Conditions ML20210B4481999-07-12012 July 1999 Forwards Rept Describing Effects of Earthquake That Occurred on 990702 Near Satsop,Wa,Iaw Trojan Nuclear Plant Defueled Sar,Section 4.1.3.1 ML20209D6231999-07-0808 July 1999 Forwards RAI Re Licensee 980827 Request for Amend That Would Delete Number of License Conditions & TS Requirements That Would Be Implemented After All Sf Has Been Removed from 10CFR50 Licensed Area.Response Requested within 30 Days ML20209C6481999-07-0606 July 1999 Forwards Rev 8 to Defueled Sar,Including Changes Since Last Submittal.Attachment Includes Brief Description of Each Change Included in Rev ML20209B7821999-07-0101 July 1999 Responds to NRC 990609 RAI Re License Change Application 244 & Accompanying Request for Exemption.Detailed Info Supports Estimation of Remaining Radioactive Matl Previously Provided by Licensee ML20212J3281999-06-15015 June 1999 Forwards Amend 22 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, IAW 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities & Does Not Reduce Effectiveness of Fire Protection ML20195J0111999-06-0909 June 1999 Responds to Requesting License & Exemption Re Emergency Preparedness ML20207D3861999-06-0101 June 1999 Forwards Rev 1 to PGE-1077, Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20196L1251999-05-24024 May 1999 Forwards Application for Amend to License NPF-1 for Indirect Transfer of License,To Extent That Such Approval Required Solely to Reflect Change in Upstream Economic Ownership of Pacificorp ML20207A2751999-05-14014 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created.Organization Chart Encl ML20206N9411999-05-11011 May 1999 Forwards Revised Epips,Including Rev 7 to EPIP 3, Response Organization Checklists & Rev 9 to EPIP 5, Emergency Preparedness Test Propgram. Changes to EPIPs 3 & 5 Ref New Owners of on-site Railroad Line,Portland & Western Railroad ML20206J8681999-05-0707 May 1999 Forwards Insp Repts 50-344/99-05 & 72-0017/99-04 on 990419-22.No Violations Noted.Insp Observed Work Activities Associated with Lifting of Reactor Vessel in Preparation for Removal & Shipment to Hanford Reservation for Burial ML20206J7931999-05-0707 May 1999 Forwards Insp Repts 50-344/99-04 & 72-0017/99-02 on 990322- 25 & 29-0408.One Violations Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20206H4331999-05-0505 May 1999 Forwards Amend 201 to License NPF-1 & Se.Amend Revises PDTSs by Deleting ISFSI Area,Revises Subsection 4.1.1,replaces Figure 4.1-1 with New Figure 4.1-1 & Adds New Page to Figure 4.1-1 to Reflect Access Control (ISFSI) Area ML20206N1571999-05-0404 May 1999 Forwards Util Quarterly Decommissioning Status Rept for First Quarter of 1999,IAW State of or Energy Facility Siting Council Order Approving Trojan Decommissioning Plan, ML20206E1731999-04-29029 April 1999 Informs That NRC Staff Has Performed an Acceptance Review of Trojan Nuclear Plant License Termination Plan,Submitted by ,To Determine Whether LTP Provides Adequate Info to Allow Staff to Conduct Detailed Review ML20206E0211999-04-28028 April 1999 Forwards Copy of Environ Assessment & Finding of No Significant Impact Re 970212 Application for Amend.Proposed Amend Would Revise Trojan Permanently Defueled TS to Delete ISFSI Area ML20206C9591999-04-23023 April 1999 Forwards Amend 200 to License NPF-1 & Safety Evaluation. Amend Changes License NPF-1 by Revising License Condition 2.C.(10), Loading of Fuel Into Casks in Fuel Building ML20206C9221999-04-23023 April 1999 Forwards Amend 199 to License NPF-1 & Safety Evaluation. Amend Changes License NPF-1 by Adding New License Condition Entitled, Loading of Fuel Into Casks in Fuel Building ML20205S9761999-04-21021 April 1999 Forwards Trojan Nuclear Plant,Radiological Environ Monitoring Rept for CY98. Rept Submitted in Accordance with Trojan Permanently Defueled TS 5.8.1.2 & Sections IV.B.2, IV.B.3 & Iv.C of App I to Title 10CFR50 ML20205T5471999-04-20020 April 1999 Forwards Insp Repts 50-344/99-03 & 72-0017/99-03 on 990301-04,15-18 & 22-25.No Violations Noted ML20205N9061999-04-13013 April 1999 Forwards Insp Rept 50-344/99-02 on 990329-0401.No Violations Noted.Inspectors Examined Portions of Physical Security, Access Authorization & FFD Programs ML20205P7301999-04-0808 April 1999 Forwards PGE-1009-98, Operational Ecological Monitoring Program for TNP,Jan-Dec 1998, Including All Existing non-radiological Effluents ML20205B3661999-03-25025 March 1999 Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.2 ML20204G1781999-03-18018 March 1999 Forwards Rev 4 to PGE-1063, Suppl to Applicants Environ Rept - Post Operating License Stage ML20204B7551999-03-18018 March 1999 Forwards Updated TS 5.6 Re High Radiation Area,Per Telcons with Nrc.Justification for TS Was Provided Previously with Util Ltr Dtd 990317,but Has Been Updated & Is Included as Encl 2 ML20204C5151999-03-17017 March 1999 Forwards Licensee Comments on NRC Preliminary SER & License Re Trojan Isfsi.Encl Includes Justification for Inclusion in ISFSI TS of Alternative Method to 10CFR20.1601(c) for Controlling Access to High Radiation Areas ML20207J3721999-03-10010 March 1999 Forwards License Amend Application 247 Requesting Amend to License NPF-1 to Add License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan, Also Encl.With Certificate of Svc ML20207L0011999-03-0808 March 1999 Transmits Tnp co-owners Annual Rept of Status of Decommissioning Funding for Tnp.Rept Is Based on Most Recent Analysis of Tnp Decommissioning Estimate & Funding Plan,Per Rev 6 to Pge, Tnp Decommissioning Plan ML20207G9691999-03-0303 March 1999 Forwards Rev 6 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Summary of Changes,Attached.Revised Portions Denoted by Side Bars ML20207D7751999-03-0202 March 1999 Forwards Amend 21 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Per 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities ML20207B0441999-02-24024 February 1999 Forwards Endorsements 139 to Nelia Policy NF-0225 & 2 to Nelia Policy NW-0602 ML20207J0701999-02-11011 February 1999 Forwards Proposed Ts,Update to ISFSI SAR & Revised Calculation,Per Application for Trojan ISFSI License ML20202G4291999-02-0202 February 1999 Forwards Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar. Approval,With Certain Conditions,For one-time Shipment of Trojan Reactor Vessel Package Granted by Commission Via Ltr ML20202G0931999-01-26026 January 1999 Submits Following Info That Will Be Needed for NRC Staff to Complete Review & Issue Trojan ISFSI License,As Result of 990121 Meeting with NRC Following Insp & Observation of ISFSI Preoperational Testing During Wk of 990118 ML20202F2551999-01-25025 January 1999 Forwards Fitness for Duty Program Performance Data Rept for July-Dec 1998 ML20202C1621999-01-21021 January 1999 Forwards Insp Repts 50-344/98-04 & 72-0017/98-01 & NOV Re Inadequate Actions Taken by Radiation Protection Technician to Ensure That Radiological Conditions Safe Prior to Removing Warning Signs for Airborne Radioactivity Area 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217E9711999-10-13013 October 1999 Submits Notification of Major Changes to Trojan Liquid Radioactive Waste Treatment Sys,Iaw PGE-1201.Detailed Description of Change Provided ML20216F7621999-09-23023 September 1999 Forwards Corrected Response to Request 2 Contained in NRC 990920 RAI Re Application of Pacificorp for Transfer of License NPF-1.Response 2 Should Have Stated That Na General Partnership Is Partnership Formed in Nv ML20216F2871999-09-20020 September 1999 Informs NRC of Developments That Have Occurred Since 990524 Application Was Filed Re Pacificorp Transfer of License of FOL NPF-1.NRC Is Urged to Act & Approve Transaction Expeditiously by 990930.Supporting Documentation Encl ML20211B6611999-08-16016 August 1999 Forwards fitness-for-duty Program Performance Data Rept for Period of 990101-0630,IAW 10CFR26.71(d) ML20210R7691999-08-11011 August 1999 Forwards Proposed Rev 23 to PGE-8010, Trojan Nuclear QAP, in Response to NRC 990708 RAI Re Relocation of TS ACs to Qap.Revised QAP Will Be Made Effective Concurrently with Implementation of License Change Application Lca 245 ML20216D6611999-07-23023 July 1999 Submits Summary of Proprietary Submittals for Transtor Part 71 & Part 72 & Trojan ISFSI Applications ML20210F8601999-07-22022 July 1999 Forwards Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar. Changes to Rept Contained in Rev 1 Received NRC Approval by Ltr ML20210B4481999-07-12012 July 1999 Forwards Rept Describing Effects of Earthquake That Occurred on 990702 Near Satsop,Wa,Iaw Trojan Nuclear Plant Defueled Sar,Section 4.1.3.1 ML20209C6481999-07-0606 July 1999 Forwards Rev 8 to Defueled Sar,Including Changes Since Last Submittal.Attachment Includes Brief Description of Each Change Included in Rev ML20209B7821999-07-0101 July 1999 Responds to NRC 990609 RAI Re License Change Application 244 & Accompanying Request for Exemption.Detailed Info Supports Estimation of Remaining Radioactive Matl Previously Provided by Licensee ML20212J3281999-06-15015 June 1999 Forwards Amend 22 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, IAW 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities & Does Not Reduce Effectiveness of Fire Protection ML20207D3861999-06-0101 June 1999 Forwards Rev 1 to PGE-1077, Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20196L1251999-05-24024 May 1999 Forwards Application for Amend to License NPF-1 for Indirect Transfer of License,To Extent That Such Approval Required Solely to Reflect Change in Upstream Economic Ownership of Pacificorp ML20206N9411999-05-11011 May 1999 Forwards Revised Epips,Including Rev 7 to EPIP 3, Response Organization Checklists & Rev 9 to EPIP 5, Emergency Preparedness Test Propgram. Changes to EPIPs 3 & 5 Ref New Owners of on-site Railroad Line,Portland & Western Railroad ML20205S9761999-04-21021 April 1999 Forwards Trojan Nuclear Plant,Radiological Environ Monitoring Rept for CY98. Rept Submitted in Accordance with Trojan Permanently Defueled TS 5.8.1.2 & Sections IV.B.2, IV.B.3 & Iv.C of App I to Title 10CFR50 ML20205P7301999-04-0808 April 1999 Forwards PGE-1009-98, Operational Ecological Monitoring Program for TNP,Jan-Dec 1998, Including All Existing non-radiological Effluents ML20205B3661999-03-25025 March 1999 Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.2 ML20204G1781999-03-18018 March 1999 Forwards Rev 4 to PGE-1063, Suppl to Applicants Environ Rept - Post Operating License Stage ML20204B7551999-03-18018 March 1999 Forwards Updated TS 5.6 Re High Radiation Area,Per Telcons with Nrc.Justification for TS Was Provided Previously with Util Ltr Dtd 990317,but Has Been Updated & Is Included as Encl 2 ML20204C5151999-03-17017 March 1999 Forwards Licensee Comments on NRC Preliminary SER & License Re Trojan Isfsi.Encl Includes Justification for Inclusion in ISFSI TS of Alternative Method to 10CFR20.1601(c) for Controlling Access to High Radiation Areas ML20207J3721999-03-10010 March 1999 Forwards License Amend Application 247 Requesting Amend to License NPF-1 to Add License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan, Also Encl.With Certificate of Svc ML20207L0011999-03-0808 March 1999 Transmits Tnp co-owners Annual Rept of Status of Decommissioning Funding for Tnp.Rept Is Based on Most Recent Analysis of Tnp Decommissioning Estimate & Funding Plan,Per Rev 6 to Pge, Tnp Decommissioning Plan ML20207G9691999-03-0303 March 1999 Forwards Rev 6 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Summary of Changes,Attached.Revised Portions Denoted by Side Bars ML20207D7751999-03-0202 March 1999 Forwards Amend 21 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Per 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities ML20207B0441999-02-24024 February 1999 Forwards Endorsements 139 to Nelia Policy NF-0225 & 2 to Nelia Policy NW-0602 ML20207J0701999-02-11011 February 1999 Forwards Proposed Ts,Update to ISFSI SAR & Revised Calculation,Per Application for Trojan ISFSI License ML20202G4291999-02-0202 February 1999 Forwards Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar. Approval,With Certain Conditions,For one-time Shipment of Trojan Reactor Vessel Package Granted by Commission Via Ltr ML20202G0931999-01-26026 January 1999 Submits Following Info That Will Be Needed for NRC Staff to Complete Review & Issue Trojan ISFSI License,As Result of 990121 Meeting with NRC Following Insp & Observation of ISFSI Preoperational Testing During Wk of 990118 ML20202F2551999-01-25025 January 1999 Forwards Fitness for Duty Program Performance Data Rept for July-Dec 1998 ML20199J1661999-01-14014 January 1999 Submits Summary of ISFSI Lid Welding Demonstration to Be Held 990118-25.Dates & Days Are Tentative & Can Be Adjusted as Necesssary or as Required ML20199J0801999-01-12012 January 1999 Forwards Schedule for Trojan Nuclear Plant ISFSI pre-op Test,Per Request ML20206Q0121999-01-0808 January 1999 Forwards Rev 1 to PGE-1073 Tnp ISFSI Security Plan,As Result of 981208 Telcon with Nrc.Encl Withheld,Per 10CFR73.21 ML20206P5991999-01-0404 January 1999 Requests That Svc List for Delivery of Documents from NRC Be Updated,Per 981230 Telcon.Substitute for Listings of HR Pate & J Westvold,Submitted ML20198T1651999-01-0404 January 1999 Forwards Rev 5 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Table 2.2-5 Is Revised to Depict Major Components Removed from Plant During 1998.Revs Are Denoted by Side Bars ML20198E3981998-12-17017 December 1998 Forwards Updated ISFSI Emergency Plan,Per 981123 & Discussion in Meeting with NRC on 981119.Description of Changes Encl ML20196E2851998-11-25025 November 1998 Forwards Final Rept of Matl Properties of Neutron Shielding Matl to Be Used in Trojan ISFSI & Test Repts That Verified Matl Properties ML20196D9831998-11-24024 November 1998 Forwards Listed ISFSI Calculation Refs,Per 981110 Telcon ML20196B2321998-11-23023 November 1998 Informs That,Per Commitments Made in 981119 Meeting with Nrc,Rev to PGE-1075 Will Be Submitted No Later than 981218 ML20195J2321998-11-17017 November 1998 Forwards Rev 7 to Trojan Nuclear Plant Defueled Sar. Attachment to Ltr Includes Brief Description of Each Change Included in Rev ML20195E4811998-11-10010 November 1998 Forwards Rev 51 to Trojan Nuclear Plant Security Plan.Rev Withheld,Per 10CFR73.21 ML20155E0331998-10-27027 October 1998 Forwards Amend 7 to PGE-1052, Quality-Related List Classification for Tnp. Amend Removes Ref to Several Clean Up Sys,Deletes Exemptions Allowed by Reg Guide 1.143 & Deletes Figures No Longer Required to Support Discussion ML20154M4151998-10-14014 October 1998 Requests That Further Review of License Change Application LCA-238 Be Suspended as Result of Progress Made in Decommissioning,Installation of Natural Gas Pipe Line ML20154A4751998-09-28028 September 1998 Forwards Amend 20 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Reflecting Revisions to Fire Protection Program Made During Decommissioning Activities ML20153D3021998-09-21021 September 1998 Forwards Rev 0 to PGE-1077, Tnp Reactor Vessel & Internals Removal Project Transportation Safety Plan, Per Request That Util Submit Description of Measures to Be Taken to Ensure Safe Transport of Tnp Rv & Internals Package ML20151X7171998-09-10010 September 1998 Forwards Rev 3 to PGE-1063, Trojan Nuclear Power Station, Suppl to Applicant Environ Rept. Section 4.5 Revised to Delete Ref to Selected Room Coolers ML20151X8571998-09-10010 September 1998 Provides Rev 2 to Poge, Trojan NPP Permanently Defueled TS Bases. Changes Identified in Revised Text by Side Bars ML20153B0001998-09-0909 September 1998 Forwards Figures & Tables Identifying Nodes Assigned for Trojan ISFSI Transfer Station Analysis,TI-056,Rev 1 ML20237E9421998-08-27027 August 1998 Requests Exemption of Emergency Plan Requirements of 10CFR50.54(q),10CFR50.47(b) & 10CFR50,App E Following Transfer of Spent Nuclear Fuel to ISFSI ML20237E1811998-08-25025 August 1998 Forwards Description of Review Methodology & Summary of Results,Including List of Identified Variations from Guidance Contained in Std Review Plan,Per NUREG-1536 ML20151W5381998-08-25025 August 1998 Forwards Rev 22 to PGE-8010, Poge Nuclear QA Program for Trojan Nuclear Plant. Rev Reflects Administrative Changes That Continue to Meet Requirements of 10CFR50,App B 1999-09-23
[Table view] Category:OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT TO NRC
MONTHYEARML20058M8921990-07-31031 July 1990 Forwards Draft Remedial Drill Rept, for Review & Comments ML20206J0731988-11-16016 November 1988 Forwards Final Rept for 871014 Exercise of Offsite Radiological Emergency Response Plans for Plant.Nineteen Deficiencies Observed in Exercise.Fema Reserves Right to Invoke 44CFR350.13 Pending Results of 881116 Exercise ML20151A0081988-06-21021 June 1988 Discusses Current Actions Re Facility & Northwest Earthquake Potential.Util Responsive to Earthquake Issues.Doe Cannot Conclude That Study Findings Indicate Hazards Greater than Facility Can Withstand ML20206J0931988-04-19019 April 1988 Forwards Memo Re Status of Corrective Actions for 871014 Exercise of Offsite Plans & Preparedness for Plant ML20236R6841987-11-16016 November 1987 Forwards Preliminary Addendum Summarizing 19 Deficiencies Observed at 871014 Joint Exercise of Offsite Radiological Emergency Preparedness Plans Involving State of Wa & Cowlitz County & State of or & Columbia County ML20207G6081986-07-14014 July 1986 Forwards Trojan Nuclear Power Plant,Ingestion Pathway Zone Exercise, of 860311-12 Exercise.Exercise Evaluated Protective Measures,Means & Capabilities of States of or & Wa.Four Deficiencies Observed ML20137M2251986-01-22022 January 1986 Forwards Exercise Rept of 851016 Exercise of Offsite Radiological Emergency Plans for Trojan Nuclear Power Plant. State Preparing Corrective Actions for Two Deficiencies & Inadequacies Noted During Exercise ML20138D6491985-10-25025 October 1985 Forwards Trojan Nuclear Plant Site-Specific Offsite Radiological Emergency Preparedness Alert..., Summarizing Design Review & Telephone Survey After 840922 Notification Sys Demonstration ML20133F7301984-04-0505 April 1984 Forwards Comparison of Two Analyses of Potential Mudflow Flood Resulting from Failure of Debris Dam in Front of Spirit Lake Near Mount St Helens.Usgs Results Higher than Expected.Simons & Li Values Too Low.W/O Encl ML20133F7431984-03-12012 March 1984 Forwards Transparency Matls Presented at 840223 Meeting Re Facility ML20133F8471983-06-20020 June 1983 Forwards Brief Summary of Preliminary Findings on Impact of Mudflow from Spirit Lake Near Mount St Helens.Findings Provisional & Subj to Review & Approval of Director of USGS ML20132B5871983-06-20020 June 1983 Provides Preliminary Findings on Potential Spirit Lake Mudflow Impact on Columbia River & Facility.Lwa to Evaluate Assumptions in Original Mudflow Analysis Recommended ML20133F7861983-05-12012 May 1983 Summarizes 830511 Meeting at Corps of Engineers Ofc in Portland,Or Re Determination of Flood Elevations at Facility Resulting from Breach of Debris Barrier at Spirit Lake,Wa. Related Info Encl ML20055A3461982-07-0606 July 1982 Forwards FEMA Region X Evaluation of Potential Effects Upon Response Capabilities W/Respect to Volcanic Activity Such as Ashfall Mudflow,Floods,Landslides,Earthquakes & Future Eruptions ML20147D3261978-09-27027 September 1978 Responding to Bd Order of 780825,ST of or Will Serve Prepared Testimony on 781006 & Can Begin Hearings on Interim Oper on 781018 ML20062B3831977-09-14014 September 1977 Advises That State of or Did Not Attempt to Misrepresent Info Re Contamination of Spent Fuel Storage Pool.Order Should Not Be Rescinded.Benefits Gained from Changing Spent Fuel Storage Racks Lessened 1990-07-31
[Table view] |
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. . .@. .-, DEPARTb4ENT OF THE IN TERIOR
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.a M ter Resources Division 1201 Pacific Avenue - Suite 600 -
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f office of Mtclear Reactor Regulation q5 U.S Nuclear Regulatory Co==mi ssion M Wshington, D.C. 20555
.....y DarW. Ballards j k 8W Reference our meeting of May 11, 1983, at the Corps of Engineers of fice y!". '
in Portland, Oregon relative to determination of flood elevations at .
l ME the Trojan Nuclear Powerplant resulting from a breach of the debris barrier at Spiri t Iake, washington. The principal a ttendees at that h{2 ""i" meeting were Bill Mayer, Pederal Emergency knages ent Agency; colonel ,%,.
Priedenwald, U.S. Army Corps of Engineers; leslie B. Iaird and Eth*ard $* J.
Bolke, U.S. Geological Surveys a nd non Dallard, Hoclear. Tegula tory Cocsission. W Q[Q-m
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As r equ~s ted by the Nuclear Regulatory Cbwmission, the U.S. mological Survey is prepared to cond uc t a two-phase analysis of flood lev-la occurring at the Trojan plant due to the nodflow as 6. ascribe d in our 1 previous analysis for the rederal rwrgency Kinagement Agency. The -
nudflow is described in U.S. Geological Survey Investigationst. 92-4125 enti tled, "Mtdflow nszards Along the Toutle and Cowlitz Ri mr s ' f tc= a l nypothetical railure of Spirit Lake Blockage.* i .
The first phase of this' study will ass one that the discharge of the m
', Cowlitz River is clear water. A kinematic model will be uned to @M route this flow effect upctream past the Trnjan ! plant. The sedi_ ment W.
[ content of the ups treas flow will then be es tima ted and the model
- b prograrm-d to deposit the sediment in time-incres>-ntal steps. If the f flood elevation at the plant is equal to or less than 45 feet, the l L.
analysis will be considered complete . If the flood elevation e xcw.d s ,
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I the 45-foot level, the second phase of the study will be i rti ti a ted . '-.3 . ..
g, l During the second phase, the major asstaptions inade for the utd flow f
and Coltnbia River routing models will be reviewed fer reasonableness. Q ..
pnevaluation of the flood level will then be made progre ssively, as 2'.*
l appropriate. M1 i j
i The analysis will be completed six veeks or less after ini ti ation of ,- -
the a ttdy . T:=nults of the sttdy will be published in a brief report l
which will not be r elear.ed until approved by our Dir ector . Ps hope to l
I cbtain that approval wi thin the given tir.e f r as.e s .
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the end o f. Pha s e I, the cost will be appreciably less.
Wr will intitiate the Phase I s tudy as soon as we receive wri tten authori-zation f rom the Ntricar kgulatory Cbumission. If a uthoriza tion doe w n_ts
, are processed by the National neadquarters of fice, please pr ovide us a copy ,
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DEPARTMENT OF THE ARMY PoRTLANo olSTRICT. CORPS OF ENGINEERS
- e. O.mox aves l,*'7-PORTLAND, OntGON 97300 JUN 0 51984 Planning Division (PL-NR-EQ) -
e To All Interested Parties:
Enclosed for your information is a copy of the Record of Decision (ROD) for a permanent outlet for Spirit Lake, near Mount St. Helens, Washington. The ROD has been prepared pursuant to Council on Environmental Quality Regulations for implementing the procedural provisions of the National Environmental Policy Act (40 CFR 1505.2).
Copies of the ROD are being provided to concerned agencies, organizations, and members of the public known to have an .
interest in the project.
Sincerely. -
Y ,sTC R. L. Fr edenwald Colonel, Corps of Engineers District Engineer Enclosure Copies to: Messrs. Steele, Orser, Yundt, Trammell, TNP: GEN ENGR 7:FSAR Section 2.4 b
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- s j JtICORD OF DECISION SPIRIT LAKE PERMANENT OUTLET l SPAMANIA COUNTY, WASHINGTON I have reviewed and evaluated, considering the overall public interest, the Corps of Engineers alternative strategies for a pemanent outlet for Spirit Lake, near Mount St. Helens, Wnhington. The environmental effects of the alternative outlets have been identified and described in a Final Environmental Impact Statement (EIS), prepared in compliance with the National Environmental Policy Act. .The views of interested agencies and the concerned public have been obtained through public meetings held in the affected consnunities and through public review of the Draft and Final EIS.
The Corps of Engineers has detemi.ned that the outlet to Spirit Lake should consist of a tunnel through rock to South Coldwater Creek, which drains into the North Fork Toutle River through Coldwater Lake. This detemination is based on considerations of engineering, geology, cost and environmental factors, and public concerns and preferences.
Project Description The Spirit Lake tunnel will be 8,463 feet long, between 11 and 14 feet in diameter, and either circular or horseshoe shaped, depending upon whether construction is accomplished by drill and blast or by tunnel boring machin'e.
The excavated material consisting of finely broken basalt and tuff rock will ,
be placed in a disposal site along the south side of South Coldwater Valley and underwater in Spirit Lake. The quantity of material to be excavated is approximately 73,500 cubic yards. The tunnel inlet will be a 100-foot long, ;,
50-foot wide channel cut in hard rock. The tunnel outlet will direct the outflow directly into the creek channel. Channel stablilization in the fom of revetment or groins will be required at the junction of the South Coldwate;-
Creek with the North Fork Toutle Valley. This is to direct the flow into Coldwater Lake, from which it will flow out through the Coldwater Lake rock cut outlet channel into the North Fork Toutle River.
Eackground o The May 18,-1980 eruption of Mount St. Helens caused a landslide which Jl, blocked the natural outlet of Spirit Lake, located about 4 miles northeast of y the volcano. With no outlet, the water level in the lake will rise until the blockage is breached by seepage or overtopping. A breach will cause severe damage from mudflow and fic9 ding in downstream cont; unities on the lower Toutle and Cowlitz Rivers, w 'h a high potential for loss of human life.
As a temporary measure to preve t the water from rising to dangerous levels,
.A pumps have been installed at Spirit Lake to stabilize the water level.
These pumps, however, cre not capable of lowering the lake surface to an ,
elevation which could assere long tam safety. A pemanent outlet for Spirit Lake is needed through which the water level can be lowered and maintained pemanently at a safe elevation.
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To detemine a permanent safe lake elevation a number of factors were
- considered. The effects of erosion, blockage stability, piping potential (internal erosion of material due to seepage), downstream flood hazards posed by different lake water levels, impact on water surfact levels from -
flood events, and impacts of volcanic and earthquake < vents were evaluated.
j Based on these studies, the safe lake level was detemined to be elevation
'4 3,440 feet, which allows for temporary raises in lake level due to volcanic
'? and flood events.
1 Alternatives Considered ,
A number of alternatives were evaluated for establishing a pemanent outlet for Shirit Lake. Each of these alternatives, except the "no action" alternative, would be capable of maintaining Spirit Lake at elevation 3440.
These alternatives are:
- 1. No action
- 2. A buried conduit in the debris blockage
- 3. An open channel excavated through the debris blockage
- 4. A tunnel through rock to Smith Creek, in the Lewis River drainage (Alinement 81 ) -
- 5. A tunnel through rock to the North Fork Toutle River (Alinement G)
- 6. A tunnel through rock to South Coldwater Creek, which drains into the North Fork Toutle River through Coldwater Lake (Alinement F) -
- 7. A pemanent pumping facility on Spirit Lake Comparison of Alternatives These alternatives were analyzed and compared considering several major factors: cost, risk, impact on the National Volcanic Monument, and impact on downstream areas. The conclusions of these analyses were:
- Cost: Estimated total initial costs ranged from $10.2 million
, (tunneTWinement 1B ) to $17.8 million (tunnel Alinemutt 5).
- Risk: Tunnel Alinement 81 would have the least. risk because both the inlet and outlet would be sheltered from the volcano. Tunnel alinement F would have somewhat more risk because its inlet would be more exposed to potential volcanic events. Tunnel alinement G would have greater risk with its outlet adjacent to the debris blockage. The buried conduit, open channel and pemanent pumping facilities would have the highest risk because each ,
is located within the debris blockage which may be in the path of future mudflows or pyroclastic flows caused by volcanic events.
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- Impacts on the National Volcanic Monument (NVM): Each of the alternative outlets would be constructed within the NVM and would disturb a portion of this protected area. Spirit Lake itself would be reduced in size frcnu 2,860 surface acres to 2,580 acres. Construction of the buried -
conduit or open channel would require excavation in the dehris avalanche.
The pennanent pumping facility would also require excavation, as well as construction of an overhead powerline and electrical substation. The tunnel alternatives would require construction of intake and outlet
. portals but would have the least effect on the NVM. Each alternative would require disposal of excavated materials, with the open channel producing
. the largest quantity of material. All of these features would have negative visual effects for visitors to the NVM and would detract from recreational and interpretive uses. Scientific research within the NVM could be adversely affected by increased streamflows, erosion, and lake
. drawdown.
- Impacts on Downstream Areas: All of the potential alinements were studied to detennine impacts to receiving watersheds from the Spirit Lake outflow. Erosion downstream of the outflow would be caused by the increased a flow and resulting increase in sediment transport capability of the affected stream. For each alinement, the effects of the outflow are greatest in the vicinity of the outfall and diminish in the downstream direction as the Spirit Lake contribution to total watershed discharge lessens proportionally.
For each alinement, downstream impacts are increased by project outflow and lessened by minimizing peak outflows from the Spirit Lake watershed. ' -
The alinements with outflows down the debris avalanche would produce the most erosion. Of these, the F alinement through South Coldwater Creek would cause the least erosion on the North Fork Toutle River. After passing -
through Coldwater Lake, which would act as a sink for suspended sediment, Spirit Lake flows would enter the North Fork Toutle approximately five miles downstream of the outlets for tunnel G and the alternatives crossing the debris blockage.
The B1 alinement through Smith Creek into the Lewis River drainage would cause no erosion of the debris avalanche. However, Spirit Lake outflows would increase the sediment yields from Smith Creek into the Muddy River, Lewis River, and Swif t Reservoir.
- Other factors considered were the effects of the alternatives on fish and wildlife, water quality, social and economic factors, cultural resources and geologic conditions.
- Fisheries in the receiving waters could be temporarily adversely affected by increased turbidity levels during initial drawdown of the lake.
Outlet alternatives which would release water into the North Fork Toutle River
.vould benefit fish habitat in that stream, which is slowly recovering from the destruction caused by the eruption. Diversion of Spirit Lake water into ,
Smith Creek would deprive the Toutle fishery of that water source. If no action were taken, the lake would breach the avalanche and massive mudflows would inundate newly recovering fish habitat in the Toutle River, block 3
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the Cawlitz River migration channel, and adversely affect aquatic resources in the Columbia River by high turbidity and habitat loss.
- Wildlife habitat could be adversely affected by erosion of those downstream riparian areas which were affected by the eruption and are now slowly recovering. If. no action were taken, mudflows 'would destroy wildlife habitat along the rivers. Dredging to reestablish channel capacity in the Columbia River would result in the significant loss of riparian and upland wildlife habitat in areas used for dredged material disposal.
- Water quality in Spirit Lake has improved since the post-eruption conditions observed in 1980. The release of Spirit Lake water is not expected to create a health hazard if discharged to either the Toutle or Lewis River Systems.
- Social and economic systems in the lower Toutle and Cowlitz valleys would benefit from any alternative which would reduce the threat of a catastrophic release of Spirit Lake.
- Cultural resources would not be affected by the alternatives considered.
There are no known historical or archeological sites in the areas which would be affected by any of the alternative outlets. -
- Geologic conditions favored tunneling and portal construction according to the following priority; a tunnel to Smith Creek, a tunnel to South' Coldwater Creek and a tunnel to th - North Fork of the Toutle River.
Compliance with Environmental Reouirements A Section 404 water quality evaluation for the recommended plan has been prepared and a water quality certification has been issued by Washington Department of Ecology in compliance with the Clean Water Act. Coordination has been compitted with the U. S. Fish and Wildlife Service, the State Historic Preservation Officer, and Federal, state, and local agencies, and interested individuals and organizations. The recommended plan is in compliance with the requirements of the Endangered Species Act of 1973, as amended.
All practicable means to avoid or minimize environmental harm from the recommended plan have been adopted. The U. S. Forest Service has been
- i. > consulted for advice on minimizing adverse effects on the National Volcanic Monument, and this coordination will continue through project construction.
The Fcrest Service has assisted the Corps of Engineers in locating sites for disposal of excavated material and construction of access roads and staging areas which will cause the least damage to the NVM. Erosion control work to protect the Coldwater Lake blockage has been included in the recommended plan.
During lake drawdown rel$ase flows will be monitored to minimize downstream erosion and to observe water quality effects in the receiving waters.
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Conclusion In conclusion I find that the selection of the recomended plan to -
construct an outlet to Spirit Lake by tunneling through rock to South Coldwater Creek is based on a thorough analysis and evaluation e
of various factors of public interest, that reasonable alternatives have been discussed, that the work will comply with established Federal, state, and local laws, regulations and codes, and that all practicable
' means have been incorporated into the project plans to avoid or minimize
, environmental ham.
Date: 30 M ES W. VAN LO N SELS
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[ / rigadier Gene 1. U. S. Army Division Engineer e
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DEPARTMENT OF THE INTERIOR
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h February 27, 1984 Msmorandum i
To: The record From: Bill Sikonia, USGS, WRD, Tacoma, WA
Subject:
Meeting with Nuclear Regulatory Commission, Simons and Li Associates, and Portland General Electric regarding the impact of a potential Spirit Lake outburst on the Trojan Nuclear Plant.
. The following is intended to distinguish some of the differences in
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assumptions between the USGS reports on the subject (Swift and Kresch, Kresch and Laenen, and Kresch), and that of Simons and Li.
The main differences are that Simons and Li assumed that less cediment would be entrained in a smaller total volume of water during a hypothetical outburst, and that deposition along the North Fork Toutle, Toutle, and ,Cowlitz Rivers would reduce the total volume of csdiment transported to the Columbia River.
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It._is a little difficult to make a direct comparison without some careful reading of the papers, so in the interests of having everyone comparing the same quantities, the following sediment and water volumes may be helpful. To clarify the conversion of in-situ volumes -
to flow volumes at the debris dam, we have *hc following comparison: .
USGS (Debris porosity = 32%, and degree of saturation = 50%).
Bulk debris 2.4 bcy x (1. - O.32) = 1.63 bcy solids from debris 2.4 bcy x 0.32 x 0.50 = 0.38 bey water from debris 2.4 bey x 0.32 x 0.50 = O.38 bcy air from debris O.51 bcy water from Spirit Lake 2.52 bcy total sediment plus water The sediment concentration at the debris avalanche is 65% by volume.
Simons & Li (Debris porosity = 31%, and degree of saturation
= 30%, approximately).
Bulk debris O.45 to 1.28 bcy x (1. - O.31) = 0.31 to O.88 bey solids from debris O.45 to 1.28 bey x 0.31 x O.30 = 0.04 to 0.12 bcy water from debris
- O.45 to 1.28 bey x O.31 x O.70 = 0.10 to O.28 bey air from debris
- O.50 bey water from Spirit Lake O.81 to 1.38 bcy total sediment .
plus water
- Water in the debris was actually ignored. The Simons and Li analysis proposed that incomplete draining of Spirit Lake would keep water from that source to less than 0.50 bcy, perhaps by 0.04 to 0.12 bcy, so that the total water, volume.from lake and debris would_be O.50 bcy. The initial sediment concentrations at the debris
- avalanche, under this assumption of total water volume restricted to 0.50 bcy, range from 38% to 64% by volume.
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The corresponding volumes at'the confluence of the Cowlitz and Columbia Rivers were as follows: ,
USGS e Full sediment and water hydrographs were routed from the cebris dam.
The volume.
flow into.the Columbia war, assumed to still be 65% sediment by i
1.63 bey solids 0.38 + 0.51 = O.89 bey water 2.52 bcy total sediment plus water Peak discharge was obtainec by routing a e'narply peaked hydrograph with 65 percent sediment by volume fres Camp Baker.
705,000 cfs sediment 385,000 cfs water 1,090,000 cfs total Simons and Li .
L O.12 to O.40 bcy solids (0.19 to 0.48 bcy having been deposited in the .
Toutle and Cowlitz Rivers) 0.50 bey water O.62 to O.90 bcy total. sediment plus water Peak discharge was obtained by assuming triangular water and sediment hydrographs of duration 35.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and peaks so that the assumed total volumes are obtained, which yields 53,000 to 173,900 cfs sediment 212,100 cfs water 265,100 to 386,000 cfs total Deposition of larger sized sediment particles was assumed to occur
- before arrival of the flood at the Columbia. The resulting sediment concentrations ranged from 19% to 44%. '
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The routing of the sediment size distribution from the debris avalanche to the lower Columbia river proceeded as follows:
~USGS Gravel and Cobbles (>5 mm) -- on to Columbia River, 40% of debris 40% deposited at confluence
. Sands (0.0625 to 5 mm) -- on to Columbia River, 40% of debris 30% deposited at confluence 10% carried beyond confluence Silt and Clay (<O.0625 mm) -- on to Columbia River, 20% of debris 20% carried beyond confluence The total bulked volume of the sediment deposit at the confluence of the Columbia River and the Cowlitz la -
2.4 bcy x (0.40 + 0.30) = 1.68 bcy -- O.50 bcy upstream (30%)
1.18 bey downstream (70%)
Simons & Li Gravel and cobbles (>5 mm) -- 40% deposited in Toutle 40% of debris ,
Sands (0.0625 to 5 mm) -- 22 to 15% deposited in Cowlitz -
40% of debris' 18 to 25% deposited at confluence * **
Silt and clay (<O.0625 mm) -- 20% carried beyond confluence 20% of debris
- Table 3.6 has a slight variation in percentage deposited in the Cowlit=, but a 50%/50% split sand / silt-clay was actually used in the computer runs of appendix B.
- The computer runs of , appendix B show about 98% (minimun 944) of the sand load entering the confluence is[ deposited there.
The bulked volume of the sediment deposit at the confluence of the Columbia River and Cowlit= river is C(0.45 x 0.18) to (1.28 x 0.25)J x O.98
= 0.08 to O.31 bcy -- O.06 to 0.25 bcy upstream (80%) ***
O.02 to 0.06 bcy downstream (20%) s
- The upstream / downstream split was estimated by scaling profiles in figure 3.5.
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Other assumptions about the physical processes involved are as follows:
! 1. With regard to the material subject to entrainment at the debris dam, Simons and Li restricted the volume below the breach elevation of 3475 feet to something less than 1.28 bcy, whereas the USGS said that the volume available is as much as 2.6 bey. -
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- 2. With regard to the sediment deposit in the Columbia River at the confluence of the Cowlitz, Simons and Li used a slope on the upstream side of the deposit of about 7 feet per mile, whereas the USGS used 2.5 feet per mile. The different upstream slopes resulted from interpretation of different streambed profiles for the May 1980 deposit in the Columbia River, one profile from USGS and the other, used by Simons and Li, from the Corps of Engineers.
Simons and Li had roughly 80% of the eventually deposited material upstream of the confluence, whereas the USGS had 30% upstream under minimum (10,000 cfs) flow conditions on the Columbia River. Neither USGS nor Simons and Li analyzed the deposit on the basis of the physical processes that govern the shape, upstream slope, height, and location of the deposit.
- 3. The Simons and Li analysis did not include pore water from the debris, about 0.04 to 0.12 bey assuming 30%
degree of saturation. The USGS analysis assumed a degree of saturation of 50%, for a pore water volume of 0.38 bcy, a'n d included this volume in the analysis. Recent measur,ements made since both the Simons and Li, and USGS .
reports were published indicate the water level in wells on the debris avalanche is at 82% of the thickness; that is, 82% of the thickness is saturated. Assuming 50%
saturation above the water table, this gives an average degree of saturation of 91% at present. For a bulked debris volume of 2.4 bcy at 32% porosity, this represents O.70 bcy of water, or 140% of the water volume in Spirit Lake.
- 4. Simons and Li assumed deposition of sediment in the Toutle and Cowlitz rivers that would reduce the sediment concentration from an initial 38% to 64% by volume on the debris avalanche to 19% to 44% at the Columbia River. The
. USGS assumed a full 65% by volume concentration for the
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entire routing. The Simons and Li analysis envisions that that a hyperconcentrated sediment-in-water flow (lower sediment concentrations than in a mudflow) will start developing in the Toutle and Cowlit: rivers, with ,
associated deposition of larger grain sizes. The USGS, while admitting that deposition should be considered along these rivers, envisions a flow that may still be a mudflow, with higher sediment concentrations and poor ,
sorting by size, lower in the Toutle and Cowlit: valleys. -
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References ll Krench, D. L., Analysis of a hypothetical failure of Spirit Lake blockage and resultant mudflow along the Toutle and Cowlitz Rivers,. Washington, U.S. Geological Survey Professional
. Paper ____, (in preparation). .
Kresch, D. L. and Laenen, Ante .ius, Preliminary estimate of possible flood elevations in the Columbia River at Trojan nuclear power plant due to failure of debris dam blocking Spirit Lake, Washington, U.S. Geological Survey Water-Resources Investiga-tions Report 83-4197, 11 p.
Simons and Li Associates, Inc., 1983, Analysis of flood level at Trojan nuclear power plant associated with hypothetical. failure of ,
Spirit Lake blockage, 48 p.
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