Letter Sequence Other |
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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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Publie service company e odermde o 2420 W. 26th Avenue, Suite 1000 Denver, Colorado 80211 /
November 9, 1983 Fort St. Vrain 0+ /
Unit No. 1
, P-83357
.~ -
Mr. G. L. Madsen, Chief h Reactor Project Branch 1 ]
U.S. Nuclear Regulatory Commission jL NOV211%3 Region IV 611 Ryan Plaza Drive, Suite 1000 h t W
! Arlington, Texas 76011
SUBJECT:
Notice of Deviation Building 10 Concrete
REFERENCE:
U.S. NRC Letter dated 10/12/83 Madsen to Lee (G-83368)
Gentlemen:
This letter is in response to the Notice of Deviation received as a result of an inspection conducted at Fort St. Vrain during the period
, August 1-31, 1983. The restatement of the deviation and the response to the items contained in the Notice of Deviation is hereby submitted.
NRC COM ENT The licensee has apparently deviated from good acceptable l construction practices fcr placement of concrete during placement j of Building 10-W-4800-6-015. Several examples are listed below:
- a. ACI 304, Section 9.7 states, in part, "For pumped concrete, it frequently is desirable to sample at both the point of delivery to the pump and the point of discharge from the line and perform correlation testing to determine if any significant changes -in slump, air content, and other mix i characteristics are occurring."
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8311280144 83J109 DR ADOCK 05000267 -
PDR
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P-83357 Page 2
.. Contrary to the above, no correlation tests were taken at
- point of placement.
- b. ACI 311 recommends: proper lighting and equipment for piscing
'of concrete.
^
- Contrary to - the above, there was insufficient lighting for 4
- placement of concrete, and there were or:1y two vibrators
-available.
- c. ACI 304, Section 10.2 recommends the so called " green cut" cleanup is a good method for preparing an inferior joint such as a cold joint.
Contrary to the above, the south ~ wall of. Building 10 contained a cold joint that was not discovered until the forms were removed.
The basis for the deviations' from. Specification 75-J-02 and
-ANSI 45.2.5 is because of the term "small . concrete quantities,"
as specified in the FSAR. "Small concrete quantities" is not clearly defined in the FSAR.
PSC RESPONSE ITEM a It has been PSC's normal practice to sample concrete at the
. point of discharge from a truck in order to have a standard basis for acceptance or. rejection for all . concrete for a projecc.
Section 9.7 of ACI 304 characterizes the double sampi Ing technique as being " desirable". In the particular case of Building 10, it was PSC's judgment that the concrete did not require double sampling to be performed.
PSC began taking concrete samples at the 'end of the concrete pump discharge line as requested by the NRC so that slump cad air
, content could be evaluated. This practice was started on
- August 5, 1983 and continued for all remaining concrete l- placements for Building 10, in which pumped concrete was l' required.
ITEM b After the first concrete placement for the walls on Building 10, PSC took the following actions to correct the problem with
! - voids in the concrete: (1) Additional lighting was placed above *
! the wall forms so that the construction forces could more easily .
- 1. view the concrete during placement. (2) The number of concrete vibrators for use 'during . concrete placements was increased
- significantly. These corrective actions were in'effect for all
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P-83357 Paga 3 remaining Building 10 concrete placements, starting August 5,
, 1983.
e ITEM c The cold joints in the lower portion of the Building 10 walls were due to a truckload of concrete that was rejected for failure to meet specifications and the resultant time delay until another truckload of concrete could be delivered to the job site.
During the placement of concrete for the walls for Building 10, it was determined that a cold joint was. starting in the east wall therefore the " green cut" cleanup method was used prior to placing the remainder of concrete for the east wall of Building
- 10. However, during this same concrete placement for the walls of Building 10, there was no indication that a cold joint was developing in the south wall, and therefore no corrective measures were taken. Upon removal of the concrete forms, and the discovery of the cold joint, it was technically evaluated by PSC and found to be acceptable. The corrective measures as mentioned above that PSC put into effect prior to the next concrete placement prevented future problems of this type. The corrective measures were in effect starting August 5, 1983.
NRC COMMENT
- It is requested that upon response to this report that the licensee define "small quantities" of concrete.
PSC RESPONSE Prior to the construction of Building 10, a conversation was held with Mr. W. Dickerson, the former NRC Resident Site Inspector, to discuss the applicability of the FSAR requirements for small quantities of concrete to Building 10. It was agreed that the concrete required for Building 10 would be considered to i be a small quantity and that the FSAR requirements for concrete would apply. In the future we do not anticipate significant concrete work that would require an on site batch plant. On a project by project basis it will be determir.ed whether an on site concrete batch plant can be justified. If the on site batch plant cannot be justified, then the amount of concrete to be installed shall be defined as a small quantity. In either event
. the applicable standards and codes for concrete shall be l followed. ,
l g . - . -- y - % ,. - . , , y .-, -_%_ , - -. ,wy
b83357 Page 4 t
This completes the PSC action items required by the Reference ietter.
If you have any further questions, please contact Mr. J.R. Reesy
.- (303):571-8406.
Very truly yours.
- W H. L. Brey, Manager Nuclear Engineering Division HLB / RAG:pa l
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