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Results
Other: ML20082E320, ML20093M745, ML20093M749, ML20094A277, ML20100C247, ML20101C284, ML20116G049, ML20198A027, ML20204E694, ML20204E706, ML20205B056, ML20205B071, ML20214R856, ML20214R871, ML20235Z262, ML20236H257, ML20262E589, ML20262E593, ML20262E597, ML20262E601, ML20262E606, ML20262E611, ML20262E615, ML20262E619, ML20262E624, ML20262E629, ML20266F484, ML20266F489, ML20266F494, ML20266F498
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MONTHYEARML20266F4841983-04-28028 April 1983 Ft St Vrain 2500 Kva Xfmr Foundations & Details. Sheet 1 of 2.No Rev Date Project stage: Other ML20266F4891983-05-0202 May 1983 Ft St Vrain 2500 Kva Xfmr Foundations & Details. Sheet 2 of 2 Project stage: Other ML20266F4981983-06-17017 June 1983 480V Transformer Fire Protection Sys Project stage: Other ML20082E3201983-11-0909 November 1983 Responds to Notice of Deviation Noted in IE Insp on 830801-31.Corrective Actions:Concrete Samples Taken at End of Concrete Pump Discharge Line,Addl Lighting Installed & Number of Concrete Vibrators Increased Project stage: Other ML20262E6111984-01-0404 January 1984 Building 10 Concrete Sections & Details, as-built.Sheet 3 Project stage: Other ML20262E6151984-01-0404 January 1984 Building 10 Steel Framing Plans, as-built Project stage: Other ML20262E6191984-01-0404 January 1984 Building 10 Walk-Thru Structure Floor Plans, as-built Project stage: Other ML20262E6241984-01-0404 January 1984 Building 10 Walk-Over Structure Roof Plan & Details, as-built Project stage: Other ML20262E6291984-01-0404 January 1984 Building 10 Walkover Structure Steel Elevation, as-built Project stage: Other ML20262E5971984-01-0505 January 1984 Building 10 Architectural Elevations & Details, as-built Project stage: Other ML20262E6011984-01-0505 January 1984 Building 10 Concrete Floor Plans, as-built Project stage: Other ML20093M7491984-01-22022 January 1984 Rept of Changes,Test & Experiments Not Requiring Prior Commission Approval Per 10CFR50.59(a) for 840101-22 Project stage: Other ML20093M7451984-07-20020 July 1984 Forwards Rept of Changes,Tests & Experiments Not Requiring Prior Commission Approval for 840101-22.Anniversary Date of Rept Changed to Correspond W/Submittal of Annual Update to Fsar.Future Annual Repts Will Cover Jan 23 - Jan 22 Project stage: Other ML20094A2771984-07-25025 July 1984 Responds to NRC 840625 Concerns Re Bldg 10 Const.Concept of Bldg 10 Finalized to Relieve Crowding Conditions & to Accommodate Equipment Replacements Being Planned.Bldg 10 Constitutes Mod Not Requiring Amend to OL Project stage: Other ML20262E5931984-09-21021 September 1984 Building 10 Site Plan & Caisson Details Project stage: Other ML20262E6061984-09-27027 September 1984 Building 10 Concrete Sections & Details, as-built.Sheet 1 Project stage: Other ML20101C2841984-11-29029 November 1984 Forwards Hl Brey for Redistribution Due to Error in Ltr Date.Correct Date Should Be 831101 Project stage: Other ML20100C2471985-03-11011 March 1985 Advises That Attachments A,B,C & D Re Diesel Generator Loading,Battery Sizing,Listing of Encl Drawings & Partial one-line Diagram Forwarded to J Miller,Per 850227 Telcon Request Project stage: Other ML20116G0491985-04-12012 April 1985 Informs That Listed Electrical Sys Drawings Sent to J Miller of NRR for Review,Per 840410 & 12 Requests.Copy of Logic Diagrams Being Prepared by I Ahmed Requested Project stage: Other ML20133A4141985-07-23023 July 1985 Forwards Request for Addl Info Re Const of Bldg 10 & Associated Walkover Structure,Including Engineering Drawings,Walkover Structure Layout & Spatial Relationship W/Surrounding Bldgs Project stage: RAI ML20262E5891985-08-0808 August 1985 Ft St Vrain Plot Plan. Sheet 1 of 1.Drawing Consists of Two Aperture Cards Project stage: Other ML20137C4011985-11-21021 November 1985 Requests Addl Info Re Bldg 10,including CN-1255 & CN-1332 for Sys 92 & CN-1294 for Sys 92/45.For Each Cn,Safety Evaluation & Design Criteria & Analysis Required.Info Requested within 30 Days of Ltr Receipt Project stage: Approval ML20138P0791985-12-17017 December 1985 Forwards Legible Copy of Safety Evaluation Design Criteria & Design Analysis for Change Notices CN-1255,CN-1332, CN-1294 & CN-1391,per NRC 851121 Request for Addl Info. Future Changes to CN-1391 Cover nonsafety-related Battery Project stage: Request ML20205B0711985-12-31031 December 1985 Rev 0 to Evaluation of Structure-Soil-Structure Interaction Effect Between Bldg 10/Walkover Structure & Main Plant Project stage: Other ML20153H0571986-02-19019 February 1986 Forwards Safety Evaluation Re 850828 Submittal Concerning Bldg 10 & Walkover Structure.Designs Acceptable,Per FSAR Requirements for Category 1 Bldgs.Confirmatory Analysis, Addressing Lack of Clearance Between Structures,Requested Project stage: Approval ML20153H0731986-02-19019 February 1986 Safety Evaluation Supporting Bldg 10 & Walkover Structure Design,Per FSAR Requirements for Category 1 Bldgs.Lack of Clearance Between Structures Should Be Addressed by Util Project stage: Approval ML20266F4941986-03-15015 March 1986 Bus Duct Layout and Location of Bus Duct Supports Project stage: Other ML20204A2161986-05-0101 May 1986 Forwards Request for Addl Info Re Bldg 10 Electrical Mods, Including Confirmation That All Class 1E Power,Control & Instrumentation Cables in Bldg 10 Qualified for Environ of 120 F Project stage: RAI ML20197F6541986-05-0707 May 1986 Summary of 860423-24 Meetings W/Util,Ga Technologies & S&W at Site Re Fuel Block Cracking,Bldg 10 Const,Seismic Instrumentation,Pcrv Tendons & Integrated Leak Rate Testing. Attendance List & Viewgraphs Encl Project stage: Meeting ML20198A0271986-05-12012 May 1986 Responds to NRC 860219 Questions Re Bldg 10 & Walkover Structure.Walkover Structure & Bldg 10 Designed Such That Structural Elements Will Not Impact on Adjacent Bldgs During Seismic Event Project stage: Other ML20204E7061986-06-19019 June 1986 Forwards Addl Info Re Bldg 10 Electrical Mods & Essential Power Bus Upgrades,Per NRC 860501 Request Project stage: Other ML20199J0261986-06-25025 June 1986 Requests Addl Info Re Structural Evaluation of Bldg 10 & Walkover Structure,Discussed at 860423 & 24 Meetings.Ltr Inadequately Addressed NRC Concerns Project stage: Meeting ML20204E6941986-07-25025 July 1986 Forwards Resubmittal of Addl Info Re Bldg 10 Electrical Mods & Essential Power Bus Upgrades to Include Attachments Not Received by NRC Project stage: Other ML20205B0561986-07-28028 July 1986 Forwards Addl Info Re Structural Analysis of Bldg 10 & Walkover Structure,Per 860625 Request,Including Seismic Model Used for Bldg & Rev 0 to SAD-481, Evaluation of Structure-Soil-Structure.. Project stage: Other ML20214R8561987-03-0606 March 1987 Forwards EGG-NTA-7607, Technical Evaluation Rept Evaluation of Bldg 10 Electrical Mods Fort St Vrain Nuclear Generating Station, Informal Rept Project stage: Other ML20205R1561987-03-31031 March 1987 Forwards Request for Addl Info Re Seismic Design of Bldg 10, for Nrc/Bnl Review.Site Visit to Review Response to Encl Questions,To Insp Bldg 10 & to Audit Supporting Structural Matl Recommended within 60 Days of Ltr Receipt Project stage: RAI ML20214R8711987-03-31031 March 1987 Technical Evaluation Rept Evaluation of Bldg 10 Electrical Mods Fort St Vrain Nuclear Generating Station, Informal Rept Project stage: Other ML20215F9631987-05-29029 May 1987 Forwards Response to NRC 870331 Request for Addl Info Re Bldg 10,per 870527 Telcon.Supporting Matl for Bldg 10 Structural Analyses Available in Util Ofc for Review Project stage: Request ML20235Z2621987-07-0808 July 1987 Requests Addl Info from Util Re Bldg 10 Seismic Design, Including Descriptive Matl for PILAY2 Computer Code & Sketches or Drawings Showing Caisson/Slab/Wall Configurations Project stage: Other ML20236H2571987-07-28028 July 1987 Requests Addl Info Re Seismic Design of Bldg 10,based on Util 870529 Submittal.Response Requested within 45 Days of Ltr Date Project stage: Other ML20234D8091987-09-0909 September 1987 Responds to NRC 870728 Request for Addl Info Re Bldg 10, Including Descriptive Matl for PILAY2 Computer Code & Sketches or Drawings of Caisson/Slab/Wall Configurations. Sketch of Configuration & Wall Stiffness Calculation Encl Project stage: Request ML20150C4441988-03-10010 March 1988 Forwards Safety Evaluation Re Seismic Analysis of Bldg 10 & Walkover Structure.Seismic Analysis Methods Used Conservative Relative to FSAR & Acceptable Project stage: Approval ML20150C4541988-03-10010 March 1988 Safety Evaluation Concluding That Seismic Analysis Methods for Bldg 10 & Walkover Structure Conservative.Gaps Provided Adequate to Accommodate Relative Motions Which Occur Between Subj Structures & Walkover Structure & Turbine Bldg Project stage: Approval 1985-07-23
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20205G8771999-03-26026 March 1999 Forwards Copy of Cover Page from Fort St-Vrain Welding Manual,Which Had Been Listed as Encl on Page 4 of 990325 Reply to EA 98-081.Cover Page Had Been Inadvertently Left Out with Original Reply ML20197H8811998-12-0101 December 1998 Forwards Proposed Change to Fsv ISFSI Physical Protection Plan in Which Commitment Is Made to Provide Feature to Security Posture for Facility ML20236R9191998-07-20020 July 1998 Ltr Contract:Mod 4 to Task Order 27, Task Area No 4 of Basic Contract - Fort St Vrain Insp Under Contract NRC-02-95-003 ML20199H8141997-11-21021 November 1997 Responds to Requesting Clarification as to Whether Increase in Tritium & Iron-55 Contamination Limits That Were Approved for Plant Apply to All Licensees ML20198K1931997-10-10010 October 1997 Provides Supplemental Info in Support of Util Proposed Rev to Physical Security Plan for Plant Plant Isfsi.Plan Withheld,Per 10CFR2.790(d) & 10CFR73.21 ML20198H5601997-09-16016 September 1997 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20141F3521997-05-14014 May 1997 Forwards Proposed Issue 4 of Physical Security Plan for Fort St Vrain ISFSI for Review & Approval.Encl Withheld,Per 10CFR2.790(d) ML20141C8611997-05-0909 May 1997 Informs of Approval of Fsv Final Survey Rept & Effluent Pathway Survey Plan & Supporting Analysis ML20141K9881997-05-0505 May 1997 Forwards Amend 89 to License DPR-34 & Supporting Safety Evaluation.Amend Designates All Elements of Approved Decommissioning Plan as License Termination Plan ML20138G2701997-04-28028 April 1997 Provides Response to NRC Comments Re Proposed Sampling & Survey Plan for Fsv Effluent Pathway.Response Documents Fsv Liquid Effluent Discharge Pathway Areas Are Acceptable for Release for Unrestricted Use IAW Draft NUREG/CR-5849 ML20148D4651997-04-24024 April 1997 Forwards Revised Interim Ltr Rept Which Describes Procedures & Results of Confirmatory Survey of Group E Effluent Discharge Pathway Areas at Fsv Station NUREG/CR-5849, Requests That Licensee Provide Evidence That Average Contamination Levels in Group E Effluent Discharge Pathway Areas Meet Averaging Criteria in Draft NUREG/CR-58491997-04-23023 April 1997 Requests That Licensee Provide Evidence That Average Contamination Levels in Group E Effluent Discharge Pathway Areas Meet Averaging Criteria in Draft NUREG/CR-5849 ML20138B0511997-04-22022 April 1997 Forwards Copy of Proposed Amend to Fsv NPDES Permit, Wastewater Discharge Permit CO-0001121 Requested to Support Repowering Activities,Iaw Section 3.2.d of Fsv Non-Radiological Ts,App B to License DPR-34 ML20140E1061997-04-10010 April 1997 Forwards Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20137S4481997-04-0808 April 1997 Informs That Decommissioning Activities at Fsv Are Complete & NRC Issued Exemption from Requirements of 10CFR50.54(w) in .Property Damage Insurance Policy Is Maintaned to Protect Fsv balance-of-plant Assets ML20137S0821997-04-0707 April 1997 Forwards Insp Rept 50-267/97-01 on 970310-11.No Violations Noted ML20137S1691997-04-0707 April 1997 Fifth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App K ML20137S5421997-04-0707 April 1997 Forwards Final Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Fort St Vrain Nuclear Station ML20148D5951997-04-0404 April 1997 Forwards Confirmatory Survey for Fsv Nuclear Station, Psc,Platteville,Co, Final Rept ML20137R6921997-04-0404 April 1997 Informs of Approval for Request for Addl 45 Days to Remedy Deficiencies Identified in NRC Re Financial Assurance Mechanism for Fsv Decommissioning Costs ML20137J8051997-03-31031 March 1997 Third Partial Response to FOIA Request for Documents.Records in App F Encl & Will Be Available in Pdr.App G & H Records Withheld in Part (Ref FOIA Exemptions 5 & 7) ML20148D5811997-03-26026 March 1997 Forwards Confirmatory Survey Plan for Group E Effluent Discharge Pathway Areas at Fsv Nuclear Station, Covered in Final Survey Rept,Vol 6 ML20137G7361997-03-25025 March 1997 Requests Addl Time for Util to Respond to NRC Comments in Re Financial Assurance Mechanism for Fort St Vrain Decommissioning Costs ML20137G9521997-03-24024 March 1997 Forwards Quarterly 10CFR50.59 Rept for Period 961201-970228 Re Changes,Tests & Experiments for Fort St Vrain Decommissioning ML20137H1131997-03-24024 March 1997 Second Partial Response to FOIA Request for Documents. Forwards Documents Listed in App D.Documents Also Available in Pdr.Documents Listed in App E Withheld in Part (Ref FOIA Exemption 6) ML20137C0181997-03-18018 March 1997 Documents That No Personnel Has Received Radiation Exposure at Fsv in 1997 or at Any Time Subsequent to ML20137C0061997-03-18018 March 1997 Documents That There Have Been No Activities Involving Release of Radioactive Matls from Fsv Nuclear Station That Potentially Could Have Affected Environ,Subsequent to Previous Radiological Envion Operating Rept ML20136G1201997-03-11011 March 1997 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1996 & Jan-Mar 1997. All Effluent Releases Completed as of 960703.Repts on Activities After 960703 Reflect Disposal of Solid Waste ML20136B1331997-02-28028 February 1997 First Partial Response to FOIA Request for Documents. Documents Listed in App a Already Available in Pdr.Forwards App B Documents.App C Documents Being Withheld in Entirety (Ref FOIA Exemption 5) ML20135D7891997-02-27027 February 1997 Forwards Responses to Comments Re Fort St Vrain Final Survey Rept ML20135D9531997-02-27027 February 1997 Forwards Copy of Amend to Util Npdes,Wastewater Discharge Permit CO-0001121,which Clarifies That Monitoring of Farm Pond Outlet Required When Industrial Wastewater Being Discharged Through Upstream Goosequill Ditch ML20135A8711997-02-14014 February 1997 Requests That Encl Deficiencies Identified in Financial Assurance Mechanism for Fort St Vrain Decommissioning Cost Be Addressed within 45 Days ML20134D1551997-01-31031 January 1997 Forwards Util Responses to NRC Comments Provided in NRC Ltr Re Sampling & Survey Plan Used for Final Radiological Survey of Liquid Effluent Pathway at Ft St Vrain ML20134C8481997-01-30030 January 1997 Forwards Draft Confirmatory Survey Rept for Fsv Nuclear Station,Psc,Platteville,Co Providing Info on Essap Activities on 960930-1003 ML20133L4961997-01-0707 January 1997 Forwards Comments That Need to Be Resolved Before Final Approval of Util Submittal Entitled, Proposed Sampling & Survey Plan for Effluent Pathway,Ft St Vrain Final Survey Program ML20133E0481997-01-0202 January 1997 Forwards Comments to Fsv Nuclear Station, Decommissioning Project Final Survey Rept (Volumes 4-11), for Consideration ML20132G0421996-12-23023 December 1996 Forwards Insp Rept 50-267/96-05 on 961203-05.No Violations Noted ML20132F2841996-12-19019 December 1996 Forwards Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Plant,Covering Period of 960901-1130 ML20133A8591996-12-16016 December 1996 Forwards Original & Copy Transcripts of Public Hearing,Held on 961203 in Platteville,Co Re Decommissioning & License Termination of Util Ft Saint Vrain Nuclear Generating Station ML20133N0011996-12-0404 December 1996 Recommends That NRC Require License to Modify Submission of Unexecuted Draft Trust Agreement Remaining Decommissioning Costs for Ft St Vrain Nuclear Generating Station in Listed Ways ML20135B3861996-11-25025 November 1996 Informs That NRC Reviewed Util 961114 Submittal (P-96096) Entitled, Fort St Vrain Final Emergency Response Plan, & Meets Requirements of 10CFR50.54(q) ML20135A5861996-11-25025 November 1996 Submits Suppl Info Re Annual Environ Rept for 1995 Operation of Fsv ISFSI ML20135A6361996-11-20020 November 1996 Submits Copy of Describing Discharge Practices for Groundwater Seeping Into Fsv'S Reactor Building Sump ML20134L4721996-11-14014 November 1996 Notifies NRC That Util Adopted Fsv ISFSI Emergency Response Plan to Direct Emergency Response for Radiological Accidents Occuring at Site,Until 10CFR50 License Is Terminated ML20134F4351996-10-30030 October 1996 Forwards Sections 1,2,6 & 8 from Survey Packages F0015, F0039 & F0126 & Sections 1,2 & 6 from Survey Package F0115 to Support on-site NRC Insp ML20134G5991996-10-30030 October 1996 Forwards Volumes 1-12 to Final Survey Rept for Groups A,B,C Rev 1,D Rev 1,E,F Rev 1 & G-J for NRC Approval in Support of Forthcoming Request for Termination of Fsv 10CFR50 License ML20133D7691996-10-22022 October 1996 Forwards Preliminary Rept Re Orise Support of NRC License Insp at Fsv on 960930-1003 ML20136B1411996-10-15015 October 1996 FOIA Request for Documents Re NOV Addressed to Scientific Ecology Group Re NRC Insp Rept 50-267/94-03 & OI Investigation Repts 4-94-010 & 4-95-015 ML20128M6181996-10-0404 October 1996 Forwards Ltr from PSC to Co Dept of Public Health & Environ Describing Monitoring Practices at Plant ML20128G8041996-10-0101 October 1996 Forwards Fsv Decommissioning Fire Protection Plan Update 1999-03-26
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20205G8771999-03-26026 March 1999 Forwards Copy of Cover Page from Fort St-Vrain Welding Manual,Which Had Been Listed as Encl on Page 4 of 990325 Reply to EA 98-081.Cover Page Had Been Inadvertently Left Out with Original Reply ML20197H8811998-12-0101 December 1998 Forwards Proposed Change to Fsv ISFSI Physical Protection Plan in Which Commitment Is Made to Provide Feature to Security Posture for Facility ML20198K1931997-10-10010 October 1997 Provides Supplemental Info in Support of Util Proposed Rev to Physical Security Plan for Plant Plant Isfsi.Plan Withheld,Per 10CFR2.790(d) & 10CFR73.21 ML20141F3521997-05-14014 May 1997 Forwards Proposed Issue 4 of Physical Security Plan for Fort St Vrain ISFSI for Review & Approval.Encl Withheld,Per 10CFR2.790(d) ML20138G2701997-04-28028 April 1997 Provides Response to NRC Comments Re Proposed Sampling & Survey Plan for Fsv Effluent Pathway.Response Documents Fsv Liquid Effluent Discharge Pathway Areas Are Acceptable for Release for Unrestricted Use IAW Draft NUREG/CR-5849 ML20148D4651997-04-24024 April 1997 Forwards Revised Interim Ltr Rept Which Describes Procedures & Results of Confirmatory Survey of Group E Effluent Discharge Pathway Areas at Fsv Station ML20138B0511997-04-22022 April 1997 Forwards Copy of Proposed Amend to Fsv NPDES Permit, Wastewater Discharge Permit CO-0001121 Requested to Support Repowering Activities,Iaw Section 3.2.d of Fsv Non-Radiological Ts,App B to License DPR-34 ML20140E1061997-04-10010 April 1997 Forwards Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20137S4481997-04-0808 April 1997 Informs That Decommissioning Activities at Fsv Are Complete & NRC Issued Exemption from Requirements of 10CFR50.54(w) in .Property Damage Insurance Policy Is Maintaned to Protect Fsv balance-of-plant Assets ML20137S5421997-04-0707 April 1997 Forwards Final Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Fort St Vrain Nuclear Station ML20148D5951997-04-0404 April 1997 Forwards Confirmatory Survey for Fsv Nuclear Station, Psc,Platteville,Co, Final Rept ML20148D5811997-03-26026 March 1997 Forwards Confirmatory Survey Plan for Group E Effluent Discharge Pathway Areas at Fsv Nuclear Station, Covered in Final Survey Rept,Vol 6 ML20137G7361997-03-25025 March 1997 Requests Addl Time for Util to Respond to NRC Comments in Re Financial Assurance Mechanism for Fort St Vrain Decommissioning Costs ML20137G9521997-03-24024 March 1997 Forwards Quarterly 10CFR50.59 Rept for Period 961201-970228 Re Changes,Tests & Experiments for Fort St Vrain Decommissioning ML20137C0061997-03-18018 March 1997 Documents That There Have Been No Activities Involving Release of Radioactive Matls from Fsv Nuclear Station That Potentially Could Have Affected Environ,Subsequent to Previous Radiological Envion Operating Rept ML20137C0181997-03-18018 March 1997 Documents That No Personnel Has Received Radiation Exposure at Fsv in 1997 or at Any Time Subsequent to ML20136G1201997-03-11011 March 1997 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1996 & Jan-Mar 1997. All Effluent Releases Completed as of 960703.Repts on Activities After 960703 Reflect Disposal of Solid Waste ML20135D7891997-02-27027 February 1997 Forwards Responses to Comments Re Fort St Vrain Final Survey Rept ML20135D9531997-02-27027 February 1997 Forwards Copy of Amend to Util Npdes,Wastewater Discharge Permit CO-0001121,which Clarifies That Monitoring of Farm Pond Outlet Required When Industrial Wastewater Being Discharged Through Upstream Goosequill Ditch ML20134D1551997-01-31031 January 1997 Forwards Util Responses to NRC Comments Provided in NRC Ltr Re Sampling & Survey Plan Used for Final Radiological Survey of Liquid Effluent Pathway at Ft St Vrain ML20134C8481997-01-30030 January 1997 Forwards Draft Confirmatory Survey Rept for Fsv Nuclear Station,Psc,Platteville,Co Providing Info on Essap Activities on 960930-1003 ML20133E0481997-01-0202 January 1997 Forwards Comments to Fsv Nuclear Station, Decommissioning Project Final Survey Rept (Volumes 4-11), for Consideration ML20132F2841996-12-19019 December 1996 Forwards Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Plant,Covering Period of 960901-1130 ML20133A8591996-12-16016 December 1996 Forwards Original & Copy Transcripts of Public Hearing,Held on 961203 in Platteville,Co Re Decommissioning & License Termination of Util Ft Saint Vrain Nuclear Generating Station ML20133N0011996-12-0404 December 1996 Recommends That NRC Require License to Modify Submission of Unexecuted Draft Trust Agreement Remaining Decommissioning Costs for Ft St Vrain Nuclear Generating Station in Listed Ways ML20135A5861996-11-25025 November 1996 Submits Suppl Info Re Annual Environ Rept for 1995 Operation of Fsv ISFSI ML20135A6361996-11-20020 November 1996 Submits Copy of Describing Discharge Practices for Groundwater Seeping Into Fsv'S Reactor Building Sump ML20134L4721996-11-14014 November 1996 Notifies NRC That Util Adopted Fsv ISFSI Emergency Response Plan to Direct Emergency Response for Radiological Accidents Occuring at Site,Until 10CFR50 License Is Terminated ML20134F4351996-10-30030 October 1996 Forwards Sections 1,2,6 & 8 from Survey Packages F0015, F0039 & F0126 & Sections 1,2 & 6 from Survey Package F0115 to Support on-site NRC Insp ML20134G5991996-10-30030 October 1996 Forwards Volumes 1-12 to Final Survey Rept for Groups A,B,C Rev 1,D Rev 1,E,F Rev 1 & G-J for NRC Approval in Support of Forthcoming Request for Termination of Fsv 10CFR50 License ML20133D7691996-10-22022 October 1996 Forwards Preliminary Rept Re Orise Support of NRC License Insp at Fsv on 960930-1003 ML20136B1411996-10-15015 October 1996 FOIA Request for Documents Re NOV Addressed to Scientific Ecology Group Re NRC Insp Rept 50-267/94-03 & OI Investigation Repts 4-94-010 & 4-95-015 ML20128M6181996-10-0404 October 1996 Forwards Ltr from PSC to Co Dept of Public Health & Environ Describing Monitoring Practices at Plant ML20128G8041996-10-0101 October 1996 Forwards Fsv Decommissioning Fire Protection Plan Update ML20128G0481996-09-30030 September 1996 Submits Rev to Psco Definitions of Contents of Documentation Packages Re Fsv Final Survey Project ML20129C0421996-09-20020 September 1996 Forwards Quarterly Submittal of 10CFR50.59 Rept of Changes, Tests & Experiments for Facility Decommissioning,Covering Period of 960601-0831 ML20133D7601996-09-16016 September 1996 Forwards Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project,First Final Survey Rept Submittal- Vols 1-5.NRC Comments Incorporated.Spending Plan Attached ML20117P0711996-09-13013 September 1996 Describes Util Plans to Remove Bldg 28 from Plant Facility ML20129A4431996-09-11011 September 1996 Describes Util Plans for Demonstrating That Liquid Effluent Pathway & Surrounding Open Land Areas Satisfy 10 Mrem/Yr Criteria Provided in Plant Final Survey Plan ML20117K5291996-09-0404 September 1996 Provides Notification That Util Will Be Revising Financial Assurance Mechanism That Will Be Used to Cover Remaining Costs of Decommissioning Plant ML20117C7281996-08-22022 August 1996 Discusses Impact of Final Decommissioning Rule & Requests NRC Concurrence That Requirements to Submit & Obtain Approval of License Termination Plan Have Been Satisfied ML20116P3431996-08-16016 August 1996 Describes Actions to Remove Structures & Equipment Items from Fort St Vrain Facility for NRC Info.Requests That NRC Advise Util of Wishes to Perform Confirmatory Survey of Any Parts of New Fuel Storage Building Before 960903 ML20133D7551996-08-14014 August 1996 Provides Environ Survey & Site Assessment Program'S (Essap) Comments Re Review of Fsv Nuclear Station Decommissioning Project Final Survey Rept ML20116M0771996-08-14014 August 1996 Provides Suppl Response to Re Insp Rept 50-267/96-01 in Jan 1996 Re NRC Concerns About Fsv Final Survey Program.Specifically,Bias in Instrumentation Response Overestimating Amount of Contamination Present ML20116M1841996-08-13013 August 1996 Forwards Util Responses to NRC Comments in Re Use of in-situ Gamma Spectroscopy to Measure Exposure Rates During Plant Final Survey.Approval to Use in-situ Gamma Spectroscopic instrument,Microspec-2,requested ML20116K0061996-08-0909 August 1996 Submits Fort St Vrain Nuclear Station Decommissioning Project Final Survey Rept ML20116M1241996-08-0808 August 1996 Responds to NRC Bulletin 96-004, Chemical,Galvanic,Or Other Reactions in Spent Fuel Storage & Transportation. Informs That Modular Vault Dry Storage Sys Is Not Susceptible to Problems Addressed in Bulletin ML20116F3611996-08-0202 August 1996 Submits Revised Documentation for Fort St Vrain Final Survey Program ML20116F8141996-08-0202 August 1996 Informs of Util Intent to Modify Fort St Vrain Control Room,Which Will Make Certain Final Survey Locations Unavailable for Further Review.Final Survey Efforts Are Complete ML20116A4511996-07-19019 July 1996 Requests NRC Approval of Proposed Method to Fsv Final Survey Plan to Determine Exposure Rates in Prestressed Concrete Reactor Vessel 1999-03-26
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059H9471990-09-14014 September 1990 Forwards Rev to Proposed Physical Security Plan,Per .Encl Withheld (Ref 10CFR73.21) ML20064A6841990-09-14014 September 1990 Notifies That Ms Frazier License OP-5608-1 Terminated Effective 900906,per 10CFR50.74 ML20059K2091990-09-14014 September 1990 Requests That Dj Trumblee Reactor Operator License Be Terminated,Effective 900912 ML20059L5831990-09-14014 September 1990 Forwards Application for Amend to License DPR-34,changing Tech Spec Design Features Section to Remove CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20059D3231990-08-15015 August 1990 Forwards fitness-for-duty Performance Data Rept for Plant ML20058N5661990-08-0808 August 1990 Requests Exemption from 10CFR50.54(w)(1) Requirements for Min Property Insurance Coverage ML20058L8031990-08-0303 August 1990 Forwards GA-C18103, Fort St Vrain Cycle 3 Core Performance, Per Request for Addl Info Re Proposed Amend to Tech Spec Which Would Allow Util to Complete Defueling of Facility ML20058M1931990-07-31031 July 1990 Advises of Termination of Kj Einig Reactor Operator License, Effective 900727 ML20056A1791990-07-30030 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-267/90-07.Corrective Actions:Electrical & Mechanical Craft Personnel Assigned to Planning & Scheduling Organization ML20055H8091990-07-23023 July 1990 Forwards Addl Info in Support of 900622 SAR for Isfsi. Proprietary SAR Withheld (Ref 10CFR2.790) ML20056A1711990-07-20020 July 1990 Discusses Decommissioning Funding for Plant.Util Revised Decommissioning Financial Plan,Based on Safstor,Currently in Effect & Funds Will Be Accumulated Per Plan Provisions ML20055H6571990-07-20020 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Model 1153 or 1154 Transmitters Presently in Use at Plant ML20058P6891990-07-20020 July 1990 Forwards Security Plan for Proposed ISFSI for NRC Review,Per 900622 & 0412 Ltrs.Plan Withheld (Ref 10CFR73.21) ML20055G8601990-07-20020 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-267/90-07.Corrective Actions:Site Mgt Recognized Applicability of 10CFR50.72(b)(2)(vi) Re Previous Day Notification & Immediately Notified NRC ML20055H2811990-07-20020 July 1990 Forwards Rev 4 to Updated Fire Protection Plan ML20055G7061990-07-20020 July 1990 Forwards Application for Amend to License DPR-34,revising Tech Spec 6.1 to Remove Equipment to Support Plant Closure ML20059D1361990-07-13013 July 1990 Applies for Exemption from Payment of Annual Fees for FY90, Per 10CFR171 ML20055E0401990-07-0303 July 1990 Forwards Issue 3 to FPOR-18, Fire Protection Operability Requirements, as Result of Rev 3 to Facility Fire Protection Plan ML20055E0331990-07-0202 July 1990 Informs of Plans to Remove B Helium Circulator from Plant Prestressed Concrete Reactor Vessel in Mannner Similar to Previous Circulator Maint Outages.Requests Timely Ack of NRC Concurrence W/Undertaking ML20055E9171990-06-29029 June 1990 Resubmits Semiannual Radioactive Effluent Release Rept Jul-Dec 1989, as Result of Omitted Tables ML20044A8281990-06-29029 June 1990 Notifies of Termination of Wj Ashmore,License SOP-43244 & Requests That Reactor Operator License Be Terminated Effective 900620,per 10CFR50.74 ML20055D3931990-06-29029 June 1990 Forwards Response to Generic Ltr 90-04,requesting Info on Status of Generic Safety Issues.W/O Encl ML20055D1591990-06-22022 June 1990 Forwards Proposed Change to Updated Fsar,App B Re Use of Controls Other than Change Notice Sys to Implement Mods Such as Cutting & Capping of Piping,In Order to Obtain Positive Equipment Isolation ML20043J0581990-06-15015 June 1990 Forwards Proposed Issue 5 to Fort St Vrain Nuclear Generating Station Defueling Emergency Response Plan, Deleting Offsite Emergency Response Capabilities,Per Util 890816 Defueling SAR & NUREG-0654 ML20043D3291990-05-25025 May 1990 Forwards Response to NRC 900330 Ltr Re Violations Noted in Insp Rept 50-267/90-04.Encl Withheld (Ref 10CFR73.21) ML20055D2051990-05-25025 May 1990 Responds to Violations Noted in Insp Rept 50-267/90-06. Corrective Actions:Extensive Training on Radiological Emergency Response Plan Implementing Procedures Will Be Provided to Operating Crews Beginning in May 1990 ML20043C8981990-05-25025 May 1990 Responds to NRC 900427 Ltr Re Violations Noted in Insp Rept 50-267/90-05.Corrective Actions:Mgt Will Continue to Stress Requirement for Procedural Compliance on Ongoing Basis ML20043B3691990-05-22022 May 1990 Describes Util Current Plans for Removal of Certain Plant Equipment Items.Components to Be Removed Have No Required Nor Useful Function During Planned or Postulated Remaining Defueling or Shutdown Conditions ML20043A9491990-05-11011 May 1990 Forwards Issue 59 to AOP-K-1, Environ Disturbances - Earthquake. ML20042F9771990-05-0404 May 1990 Forwards Assessment of Possible Sources of Water in Plant Core,Means of Detecting Water in Pcrv & Effects of Water Ingress on Reactivity,For Info ML20042F9011990-05-0101 May 1990 Forwards Conceptual Plan & Cost Estimates for Early Dismantlement of Fort St Vrain Pcrv, Per NRC 900315 Request ML20042E8911990-04-27027 April 1990 Requests 30-day Extension to 900529 to Submit Response to Violations Noted in Insp Rept 50-267/90-04 ML20042F3111990-04-26026 April 1990 Forwards Application to Amend License DPR-34,providing Tech Spec Changes Needed to Complete Defueling ML20012D4711990-03-19019 March 1990 Requests Approval of Encl Exemption Request Allowing Util to Accumulate Decommissioning Funds Beyond Termination of Operations ML20012B7541990-03-0707 March 1990 Informs of Electronic Transfer of Fees on 900307 for Invoice IO547 ML20011F4691990-02-22022 February 1990 Responds to NRC 900116 Ltr Re Violations Noted in Insp Rept 50-267/89-23.Violation Re Fire Doors 13 & 9 Between 480-volt Ac Switchgear Room & Bldg 10 Propped Open on 891129 Disputed.Improved Communications Underway ML20006E7821990-02-15015 February 1990 Forwards Responses to 891004 Questions Re Decommissioning Financial Plan ML20011E8941990-02-0707 February 1990 Responds to 890719 NRC Bulletin 89-002 Re safety-related Anchor/Darling Model S350W Swing Check Valves.Licensee Reviewed Plant Data Base & Design Documents & Concludes That No Anchor/Darling Model S350W Valves Installed at Plant ML20011E7861990-02-0707 February 1990 Forwards Overview of Evaluation on Compliance W/Environ Qualification Regulation (10CFR50.49) During Defueling of Facility.During Defueling,Pcrv Will Be Maintained at Nearly Atmospheric Pressures & Rapid Depressurization Not Possible ML20011E5031990-02-0606 February 1990 Notifies of Termination of Ma Rhoton Employment W/Util, Effective 900206 ML20006D6621990-02-0606 February 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Currently Established Preventive Maint & Tech Spec Surveillance Activities on HXs Remaining in Svc Will Continue ML20006B2091990-01-26026 January 1990 Forwards Fire Operability Requirements 3 & 14,Issues 3 & 4, Respectively,To Fire Protection Program Plan,Section FP.6.1. Changes Cover Halon Sys & Basis & Records Ctr Halon Sys ML20006B7791990-01-25025 January 1990 Forwards Application for Amend to License DPR-34,changing Section 7.1 of Tech Specs.Specifically,Senior Vice President,Nuclear Operations Revised to Vice President, Nuclear Operations & Nuclear Training Manager Revised ML20006A5001990-01-19019 January 1990 Notifies of Util Intent to Bore 10 Concrete Core Drills Into Prestressed Concrete Reactor Vessel Barrel Section at Various Elevations Found Necessary for Decommissioning Planning.Drillings Wil Begin on 900205.Assessment Encl ML20006A5041990-01-19019 January 1990 Responds to NRC 891218 Ltr Re Weaknesses Noted in Insp Rept 50-267/89-22.Corrective Actions:During Power Operations Three Licensed Reactor Operators Will Be Present in Control & Short in Emergency Public Address Sys Repaired ML20005G5001990-01-12012 January 1990 Forwards Approved Proposed Change to NPDES Permit to Use Halocide Product for Microbiological Control in Smaller Cooling Tower ML19354D8581990-01-0505 January 1990 Forwards Safety Assessment of Proposed Changes to Fire Protection Program Plan,Per P Erickson Request.Changes Cover Acceptance Criteria for Shutdown Cooling Following Fire & New Fire Protection Cooldown Trains 1 & 2 ML20005F5531990-01-0303 January 1990 Certifies That Util Has Implemented fitness-for-duty Program Meeting 10CFR26 Requirements ML20005D8921989-12-21021 December 1989 Forwards Proposed Change to Plant NPDES Permit ML19354D7441989-12-0808 December 1989 Requests Relief from Requirements of Generic Ltr 89-10 Re motor-operated Valves Since Plant Permanently Shut Down Since 890818 & Defueling Initiated on 891127 1990-09-14
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l 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211
'May 29, 1987 j Fort St, Vrain l Unit No. 1 I 1
P-87170 8
'l U. S. Nuclear Regulatory Commission 1 ATTN: Document Control Desk I Washington, D.C. 20555 l Attention: Mr. Jose A. Calvo Director, Project Directorate IV Docket No. 50-267
SUBJECT:
Request for Additional Information on FSV Building 10
REFERENCES:
'1) NRC Letter, Heitner to Williams,-dated ;
03/31/87,(G-87104) 2)Telecon,PSC.(Holmes)'.
to NRC (Heitner)~and Brookhaven National Laboratory (Miller)'on
Dear Mr. Calvo:
As requested during the -telephone conversation .on May 27, 1987 l (Reference 2), PSC has prepared written ~ responses to the' requests for ;
additional information on Fort' St. . Vrain' Building '10, posed in '
Reference 1. This.information is contained in Attachment'l- to- this letter.
Supporting material for all; Building 10 structural analyses is- l available in our office for'your review. '
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P-
P-87170 l
4 Page 2 May 290 1987 I
If you have any questions concerning this subject, please contact Mr. M. H. Holmes at (303) 480-6960. l Very truly yours, 1 1
1 b /Y fY& 0 D.W. Warembourg, M l Nuclear Engineering Division DWW/MM:pa Attachment l
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NRC REQUEST In the analysis of the Building 10 caissons, two foundation moduli !
values were considered. It should be demonstrated that these two I cases bound the actual condition, where a stiff layer is sandwiched f between two soft layers. Consideration should be given to both the equivalent interaction springs and dampers. .
1' PSC RESPONSE See next page. ,
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s Response to Request 1 The modulus of subgrade reaction (K h ) is significant in determination of the horizontal soil springs and, to a lesser degree, the torsional l soil springs. The torsional spring has very'little significance in the '
overall building response due to the symmetry of the building. The peak of the response (especially for the upper floors) is' governed by the rocking springs, which are based primarily on the full length of the :
caisson to bedrock. !
From Attachment 2 of Reference 2, the lengths of the equivalent cantilever and the horizontal and rocking soil spring values are:
Kh=50 lb/in3 Kh = 170 lb/in 3 j Lb 17.3 ft 1.35 E + 01 ft 1 Horizontal sprinos 8.50 E + 04 k/ft 1.79 E + 05 k/ft E W Rockino 1.96 E + 08 ft k/ rad 1.9 9 E + 0 8 ft k/ rad N.S Rockino 1 1.57 E + 08 ft k/ rad 1.5 9 E + 08 ft-k/ rad Since the horizontal response is a function of both the rocking and-lateral:
soil springs, the major difference in the response of the two soil , cases is due to the horizontal soil spring values since the rocking springs are nearly identical.
Using the approach given in Reference 1, the equivalent cantilever bending length places the base of the equivalent cantilever a- short distance into the stiff soil layer. For the assumptions used in the . equivalent cantilever analysis, the stiffness of the soil near the surface is much more sf gnificant than that at the base. Therefore, the lateral stjffness of the system is most closely approximated by tpe Kh = 50 lb/in - case.
The usage of soil springs based on Kh = 170 lb/in was included to provide an upper bound for the frequency of the system.
A damping value of 7% for SSE and 4% for' OBE was used for all modes. These are much-lower than the values typically used in soil damping.which -could be in the range of 10 to 30%. The damping values used will .give a -
conservative response of the system.
In order to demonstrate that the two soil cases bound the layered soil-condition, the ' computer program . Dynamic Response of' Piles (PILAY2),
developed under the direction of Professor M. Novak by Systems. Analysis Control and Design Activity - The University of Western .0ntario. wasi run for several conditions. This program is based on years of. studies by M. Novak and his associates.
The . program. showed that the horizontal 1 stiffness of the pile group for, the layered soil condition is 11 percent -
1 higher than that for a condition based entirely on the lower soil' stiffness and is significantly less than that' based entirely on the higher soil' stiffness. This is well within the range of soils ' springs ' used.' for. the analysis, and shows that the response of the layered soil system will be .very close to that based on the lower soil' spring . values.1
<L Response to Request 1 (cont...)
Reference 1 - Design ~of Machine Foundations on Piles, Journal of the Geotechnical Engineering Division, J. P. Singh, N. C.
Donovan, A. C. Jobsis, August 1977, pages 863-877
- Reference 2 - PSC Letter Warembourg to Berkow (P-86489) dated-July 28,.
1986.
Reference 3.- Systems Analysis Control and Design Activity (SACDA),
User Manual, PILAY2, A' Computer Program for. Calculation.
of Stiffness and Damping of Piles in Layered Media, the.
University of Western Ontario, London, Ontario, Canada',
January, 1981.
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l Item 2 NRC REQUEST !
The rocking interaction parameters were developed based on the l assumption that the foundation is rigid in flexure relative to the axial stiffness of the caisson. Provide information so that the ;
validity of this assumption may be reviewed.
PSC RESPONSE The foundation is stiffened by the vertical walls of the building.
This gives a moment of inertia of the wall system of two to four {
times that of the caisson stiffness. This relative stiffness was sufficient to utilize the standard practice of ~ assuming the- i foundation was rigid for the calculation of the rocking soils springs. ;
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Item 3~ ~l NRC REQUEST The seismic input ground motion used .for : Building 10 and the turbine building are different. Information describing and justifying the-use of two different inputs should be provided. )1 i
PSC' RESPONSE ]
Design for seismic loading conditions on_ both Building 10 and Walkover-
' Structures are accomplished by the response spectrum '(modal superposition) method, using. . appropriate response spectra curves dictated by application of Regulatory Guides 1.60 (Rev. 1, 12/73) g and 1.61 (10/73). . Curves from _ Reg. Guide 1.60 are scaled to .0.05g .i (0BE) . and 0.10g (DBE) maximum horizontal ground acceleration to be-used in structural design - for Fort St. Vrain, as specified .in FSV.-
FSAR Section 14.1.1. Both the horizontal and vertica1L component design response spectra for Building 10 and the Walkover Structure a.re derived in this manner.
The FSAR; horizontal component design response spectra for 0,10g maximum
. horizontal ground acceleration are' shown in Fig. 14.1-l' of the' FSAR '
-(see attached). This is the input ground motion used _in design .of the' Turbine Building. The vertical . component is taken _as 2/3 of the horizontal (FSAR 14.1.1-1). Data for a 0.05g earthquake' is obtained i by multiplying the.0.10g accelerations by 1/2.
l Building.10 is 'a reinforced concrete structure; the Walkover Structure ~ 1 and Turbine _ Building are cross-braced bolted steel' structures. Assumed _~
damping factors-from Reg. Guide 1.61 are used in the design'of Building 10 and the Walkover Structure. . .The Reg.' Guide 1.61 '. damping values-for reinforced concrete and bolted steel structures. differ. from those outlined in FSAR Table 14.1-2, used - in the design of the o Turbine ?
Building. A tabulation of these values is shown in Table 1 (in terms of percent of critical damping)..
Because the design inputs -for .Buil' ingd 10 .and the. Walkover 1 Structure '
are different than FSAR seismic criteria (in terms.' of ; curve.. shape; and permissible. damping factors), a graphical comparison of appropriate -
design curves was generated. Comparing Reg. Guide 1 60 0.05g earthquake horizontal component at 5% damping to FSAR 0.05g earthquake horizontal component at 2% damping (Fig.1). addresses OBE case for both structure.
types. . Reg. Guide -1.60 data at 5%.was _used since the 4% curve requires interpolation ' between Reg. Guide ' information for- 5% ~.and 2%: damping (both . directly . available), and.; the 4%' curve lwould be abovef the' 5%
curve. .Likewise, a plot of Reg. Guide 1.60' O.10g earthquake horizontal-
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component . spectrum at 7% damping versus FSAR 0.10g earthquake ~ horizontal component . spectrum at 5% damping (Fig. 2)Laddresses DBE: (SSE) case fori reinforced : concrete directly and _ bolted steel indirectly, since. FSAR
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curve.at 5% envelopes the'FSAR curve at 10%.
CONCLUSION Response spectra curves for horizontal' component -from . Reg. Guide L1.60 envelope their FSAR counterparts, with appropriate. damping -values a
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2 taken into account, as shown in Figs. 1 and 2. These comparisons j adequately encompass the vertical component spectra also, because )
ratio of vertical to horizontal components is a constant 2/3 for FSAR requirements, and varies between 2/3 and 1 for Reg. Guide 1.60 l Guidelines. Therefore, seismic design response spectra input for j Building 10 and the Walkover Structure can conservatively be used 1 to fulfill seismic design criteria specified in Fort St. Vrain's FSAR. j a
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1 REG. GUIDE 1.61- FSAR TABLE 14.1-2 i TYPE OF STRUCTURE OBE DBE (SSE) OBE DBE (SSE)
BOLTED STEEL 4 7 2 10 i
REINFORCED CONCRETE 4 7 2 5 l
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H Item 4 NRC REQUEST f The license's submittal includes spectra labeled " Isolated" and~
"Cou pl ed . " It is not clear whether the " coupled" spectra are the spectra of the Turbine Building basemat motion,'or spectra of the -l response of Building 10 to an input motion due _to the Turbine- l
' Building basemat motion. If the first is the' case, then 3 information should be provided demonstrating that this solution- l bounds' the structure / soil / structure interaction situation. If the 1 latter is true, information describing the model'used and the input. j motion should be provided.. J q
PSC RESPONSE i a
The " coupled" spectra referenced in PSC's submittal (Attachment 3 )j to PSC Letter P-86489, dated July 28,1986) represent the' response '
spectra of the Turbine / Reactor Building grade slab at the given.
damping values. As stated in the Attachment 3 report (Sargent & i Lundy Report No. 481)', this . spectra also represents the grade :
elevation motion of Building 10 resulting from the structure-soil- {
structure interaction effects.
The occurrence of this phenomenon is discussed in detail in the j above referenced report. In summary, this report demonstrates the j following: J
- 1. Because Building 10 is very close to and its' size and mass are-very small compared to the Turbine / Reactor Building,- th.e ;
Turbine / Reactor Building will drive the~ grade slab. (elevation 4791 feet) of Building 10 by the same horizontal motion:as:the i motion of its own grade slab. ;
- 2. In the vertical direction, the structure-soil-structure .
interaction will have an insignificant effect on Building 10. l
- 3. The presence of Building 10 will not- affect the seismic j response of the Turbine / Reactor Building. 1 The seismic response spectra at the grade slab for which Building' 10 was designed envelopes the' grade slab response _ spectra _ resulting from structure-soil-structure interation (i.e. the Turbine / Reactor- o
. Building grade . slab spectra) at all frequencies ~of- concern.
Therefore,_the_ design. of Building 10, which uses a' conservative ,
Reg.' Guide 1.60 input motion, bounds the structure-soil-structure lj interaction situation. .y a
~
l 1
. g m
e 3
l
1 Item 5 NRC REQUEST The basis for the displacements of the Turbine Building and Building 10 ,
used to determine the relative. building displacements should be l provided. ,
l I
PSC RESPONSE The Turbine-Reactor Building Seismic Analysis models the structure l as a three-dimensional slab-spring system. A dynamic modal. analysis l was performed on this building, using the computer program DSASS l (Ref. 1). This program calculated the maximum building displacements which were supplied to the NRC in Attachment 4 to Ref. 2. As stated in PSC's response to Request #3, contained in this letter, the seismic input motion used in the Turbine-Reactor Building design is taken from the response spectra shown on FSV FSAR Figure 14.1-1.
Building 10 was analyzed using a lumped mass model as outlined in Attachment 1 of Ref. 2. A dynamic' modal analysis was performed, and seismic displacements calculated, using the STRUDL II computer program (Ref. 3) and the results verified by use of Ref. 4. As stated in PSC's Response to Request #3, the seismic input motion used in the design of Building 10 was derived from the response spectra curves of Regulatory Guide 1.60 scaled to 0.05g (0BE) and 0.10g (DBE).
The Walkover Structure is a fixed base, cantilever truss building- a system, and is modeled accordingly in the dynamic modal analysis which !
was performed using the P-DELTA STRUDL computer program (Ref. 5).
The seismic input motion used for this analysis is the'same as that used for Building 10.
Please note that the maximum walkover displacement listed in Attachment 4 of Ref. 2 is in error. The actual peak east-west ;
displacement resulting from DBE input ground motion is 0.858 inches, l not 0.6 inches as reported previously. This discrepancy results from I an error in the original computer analysis of the Walkover Structure l which incorrectly calculated the lumped mass terms representing non {
structural attachments, such as building siding and bullet-proof steel. {
The structure was reanalyzed using correct mass terms, resulting in the peak displacement of 0.858 inches. This error did not have a .
detrimental impact on the results of the structural analysis of the building, and therefore the Walkover Structure is adequate to resist ,
the design basis loading, as previously concluded.
A summary of peak east-west displacements, resulting from DBE loading, is shown below:
Turbine Building 0.096" Buildir- 10 0.210" Walkover structure 0.858" From the above figures, the maximum probable differential displacement
i 2 >
between two adjacent structures is as follows: I
- 1. Between Turbine-Reactor Buf1 ding and Wal kover Structure -
o = 0.096" + 0.858" = 0.954"
- 2. Between Walkover Structure and Building 10 -
A = 0.858" + 0.210" = 1.068" The aforementioned displacements do not present a problem with adjacent structures impacting during a seismic event, since the 2-inch clearance
_ provided between structures is greater than the maximum displacements.
The computed maximum relative displacements occur at the Walkover ,
Structure roof and are less than 1.068 inches at lower elevations.
The large difference in computed displacements . between the Turbine Building and Walkover Structure / Building 10 can be best explained by the following factors:
- 1. The input ground motion used in the Building 10 and Walkover Situcture seismic analyses envelopes that used in the Turbine Bui.1 ding analysis. This fact results in a more conservative analysis and thus greater dynamic response of these two structures.
- 2. The geometry of the structures vary appreciably. The Wal kover Structure is an extremely tall, narrow building relative to the Turbine Building and thus would be expected to have a greater l response to seismic input motion. Likewise, Building 10 _is very f
tall and narrow in comparison to the Turbine Building and would j also be expected to have a greater response.
)
{
References
- 1) "DSASS - Dynamic Seismic Analysis of Shear Structures", by M. Amin and S. L. Chu, Analytical & Computer Division, Sargent and Lundy Engineers, Feb., 1967. 1
- 2) PSC Letter Warembourg to Berkow (P-86489) dated July 28, 1986.
- 3) STRUDL-II, Version -10 Level-06.
- 4) GT-STRUDL-BCS, Version-2, level-04.
- 5) P-Delta STRUDL, Version 1086.}}