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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 ML20137S5421997-04-0707 April 1997 Forwards Final Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Fort St Vrain Nuclear Station ML20137S1691997-04-0707 April 1997 Fifth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App K ML20137S0821997-04-0707 April 1997 Forwards Insp Rept 50-267/97-01 on 970310-11.No Violations Noted 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 ML20148D5951997-04-0404 April 1997 Forwards Confirmatory Survey for Fsv Nuclear Station, Psc,Platteville,Co, Final Rept 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 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) ML20137G9521997-03-24024 March 1997 Forwards Quarterly 10CFR50.59 Rept for Period 961201-970228 Re Changes,Tests & Experiments for Fort St Vrain Decommissioning 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 ML20135A5861996-11-25025 November 1996 Submits Suppl Info Re Annual Environ Rept for 1995 Operation of Fsv ISFSI 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) 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 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 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 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 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 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 ML20135D7891997-02-27027 February 1997 Forwards Responses to Comments Re Fort St Vrain Final Survey Rept 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 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 ML20116F3611996-08-0202 August 1996 Submits Revised Documentation for Fort St Vrain Final Survey Program 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) 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 ML20064A6841990-09-14014 September 1990 Notifies That Ms Frazier License OP-5608-1 Terminated Effective 900906,per 10CFR50.74 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) ML20058P6891990-07-20020 July 1990 Forwards Security Plan for Proposed ISFSI for NRC Review,Per 900622 & 0412 Ltrs.Plan Withheld (Ref 10CFR73.21) 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 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 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 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 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 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 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) 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 ML19332F2801989-12-0808 December 1989 Responds to Generic Ltr 89-19 Re Resolution of USI A-47, Safety Implications of Control Sys in LWR Nuclear Power Plants. Facility Has Been Shut Down Permanently & Being Defueled,Therefore No Further Action Required 1990-09-14
[Table view] |
Text
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s w; f .:
Public Service- **'Cc*--
c P.O. Box 840 Denver CO 80201 0840 July 23, 1990' Fort St. Vrain (Ug9]l,awford ISFSI Nuclear Operations P-90236 Director, Dikision of Industrial and Medical Nuclear. Safety Office of Nuclear Material Safety and-Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555
.=
ATTN: -John P. Roberts Section Leader Irradiated Fuels Section Fuel Cycle Safety Branch Docket No.=72-009
SUBJECT:
Fort St. Vrain Independent Spent Fuel Storage Installation Safety Analysis Report; Supporting Information
REFERENCE:
- 1) PSC Letter,- Crawford to Roberts, dated June 22, 1990 (P-90173).
- 2) PSC Letter,-Crawford to Roberts, dated June 22, 1990
'(P-90187)
Dear. Mr. Roberts':
Public- Service Company of Colorado (PSC)submittedanIndependent Spent Fuel Storage Installation License Application in two submittals
- .(References 1 -and 2). Reference 1 contained the non-proprietary License Application information and Reference 2 contained the ' items l considered proprietary b
' Applications Division (FW)y .
Foster PSC Wheeler stated Energy in Reference _ Corporation, 1 that a follow Energy 4_ up submittal would~ be made containing c'ferences, evaluations, l - calculations, and computer analyses to support information contained in' the License Application Safety Analysis Report (SAR). Attachment M;s8; D lists'the supporting information contained in the Enclosure to this p ga. : letter. 'All of these items are either PSC, GEC ALSTHOM Energy oo .SystemsLimited(GEC),orGeneralAtomics(GA) originated documents.
R Attachment,C contains a list of the information items in Attachment D considered by FW to be proprietary under the criteria set forth in 10
%o -~ CFR 2.790.
58: At your ' request, two copies of the enclosed supporting information t
.g4 g N- are being submitted with this letter and three additional copies are I l
18@ being _ sent to Mr. John Stokley of Science Applications International 04x Corporation. PSC will follow up this submittal with a telephone call
'to Mr. Steve Ruffin and Mr. Stokley to discuss the contents of this I letter and any additional information desired by either party. i 4" 2C > hp i at,u,.mSn om ew m.
gFPf upng,_ w w ux: t M
.l 1
E P-90236 g* , l July 23, 1990 Page 2' j In' accordance. with the requirements of 10 CFR 2.790, the following !
documents are aise submitted with this letter:
l (1)g One' copy of an ' Application for Withholding Proprietary .j Information from Public Disclosure, Attachment A. D v ,
(2) One copy of the Proprietary Information Notice, Attachment l
[ B.- .;
(3) One copy of an original affidavit listing the proprietary
=information. Attachment C. ;
If you .have any questions or .need additional information please i i .contactMr.M.H.Holmesat'(303);480-6960. j E' i I
T- Very truly yours, -
&"" ' h k / y l A.LClegg Craw rdi :l Vice President '
Nuclear Operations- J
< : Attachments Enclosure' ACC/BRD:faw. t cc Regional Administrator, Region =IV d.
ATTN: Mr. J. B. Baird .
Technical Assistant (!
Division of Reactor Projects- l' (withoutenclosure)
Mr. Robert Farrell Senior Resident. Inspector Fort 1St. Vrain.
(withoutenclosure)
- John Stokley"
-Science Applicat!ons International Corporation -;
1709 Goodridge Drive ~
5th Floor-
.1 McLean, VA 22102-(withthreecopiesofenclosure)
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Att'achsent A to P-90236 I
, July 23, 1990 :
Page 1.of 1-
, I APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE o
RE: Fort St. Vrain Independent Spent Fuel Storage Installation SAR - l Proprietary Information 1
- i. '
L This application for withholding Proprietary. Information is submitted .
.by Public Service Company of. Colorado on behalf of Foster Wheeler ',
Energy _ Corporation. Energy ApplicationsDivision(FW),:pursuantto the provisions' of: 10 CFR 2.790(b)(1). The referenced material- '
contains information which is commercially important to FW and that- ,
has been held in confidence by FW.
In accordance with10CFR2.790(b)(1),FWhasprovidedanaffidavit >
which sets forth the basis on which.the information may be withheld from public disclosure by the Nuclear Regulatory Commission. This affidavit, enclosed as Attachment C s ecifically addresses the l F considerationslistedin10CFR2.790(b)(4. ;
- It- is requested that the information which is proprietary to FW be l withheld from public disclosure in accordance with 10 CFR 2.790. !
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o - Attich ent B to P-90236 4
, e C- tJuly 23. 1990 c e ' '
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-Page 1:of I? .,
L, PROPRIETARY:INFORMATION NOTICE j' *}_y
. ',' Transmitted herewith are proprietary versions of documents; furnished in to the Nuclear Regulatory Commission in connection with a request for. .!'
issuance of a license to Public~: Service Company of Colorado to' i; . construct and operate an. Independent Spent Fuel Storage. Installation- ,
fl, l[ at the Fort.St. Vrain Nuclear Generating Station site. !
7;
);fi i < . :The : JustificationL for claiming ,the information (designated: ss. '
1 proprietary is contained in the: Foster Wheeler . Energy" Corporation.
4( ". Energy Application Division affidavit, Attachment C. -
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, n) 'l . Attschment- C': to' Pi90236 l .. h.' " July 23,-::1990 :
= 1.!! Page l.of'5
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- FORT ST.:VRAIN INDEPENDENT SPENT FUEL STORAGE INSTALLATION FOSTF.R WHEELER ENERGY CORPORATION AFFIDAVIT
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FOSTER WHEELER ENERGY CORPORATION
- y, , ENERGY' APPLIC ATIONS DIVISION 4
t , 8 PEAoH TREE ROAD e UVINGSToN. NEW JERSEY 07039 e PHONE 201 535-P354 0 '5798-90-2 V
July 19,,1990 i
AFFIDAVIT 9' ' STATE OF NEW JERSEY )
) SS
-COUNTY OF-ESSEX )
Before me,-the undersigned authority, Bubanesh K. Agarwal, personally appeared, known to me to be the General Nanager of Energy Applications Division of Foster Wheeler Energy Corporation, and under oath stated that he was authorized--
~
m -to make this affidavit on behalf of the corporation and that
-the-averments of fact set forth in this affidavit are true anc correct to the best of his knowledge, information and belief.
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)) Sra r< y Pu em a GRACF N".*O-
- NOTARY PUDtit (.< %w Jtitsgy
- Wy Coministic.) bpires ,wg. 17,1992 l
CADLE ADOHESS REWOP PERHYVILLENEWJERSEY
s 5798-2 page 1 of 3 (1) I, Bubanesh K. Agarwal, depose and say that I am the General Manager of Energy Applications Division of Foster Wheeler E7ergy Corporation, duly authorized to make this affidavit and have reviewed or caused to have reviewed the proprietary information sought to be with-held from public disclosure in connection with the appro-val of the Fort St. Vrain Modular Vault Dry Store System.
(2) The proprietary information sought to be withheld in this submittal is as follows:
GEC Technical Specification, MVDS Crane, No. 362 F 0008 GEC Technical Specification, MVDS Project Data File, No. 362 F 0001 GA Technologies Report No. 910055, Nuclear Safety of FSV ISFSI GEC Technical Specification, FSV MVDS Interlock Schedule, No. 362 F 0027 GA Technologies Report No. 910061, Fission Product Release Inventory Appendix A8-8 Calc 2 Calculation File number JH2879/941/TH/200
" Fort St. Vrain MVDS Thermal Calculations on Vault" Calculation Numbers: 4, 7, 8, 11, 13 to 20 inclusive, 22 Calculation File number JH2879/941/SH/300
" Fort St. Vrain MVDS Vault & Surround Shielding" Calculation Humbers: Volume 1; 1, 2, 4 to 12 inclusive Volume 2; 1 to 4 inclusive Calculation File number JH2879/941/SH/301
" Fort St. Vrain MVDS Cask and FHM Shielding" Calculation Numbers: Volume 1; 1 to 9 inclusive, 12, 13 Volume 2; 1, 2 Calculation File number JH2879/941/SH/302
" Fort St. Vrain MVDS Neutron Shielding" Calculation Numbers
- 1 to 12 inclusive Calculation File number; JH2879/941/SH/000
" Fort St. Vrain MVDS Radiological Release Assess ment" Calculation Numbers: 3, 5, 9, 12
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-5798-2 page'2 of13.
Also included in. support.of these calculations are all the shielding data sets and output. files used in the above calcu-lations.- These are included on the magnetic tape included in a format suitable for u USNRC ix) use, i.e. Backup.in, ESCDIC' code with no label r.t a density of 6250 bpi. -A-listing of: the files on;this tape. is included with the. tape.
t
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4 ' Wind Tunnel Investigation on the Fort-St. Vrain MVDS',_ University of Bristol, Department of Aerospace Engineering report TVL 9016 7% Reference No. SAR'A3.1-1
' Design and Analysis of Dry Stores, Validation of Version C', '
-ESL TM 9037 GEC'Alsthom Engineering Systems drawings:-
362A0007 - Fuel Storage Container 362A0029 - FSC Leak Test Equipment j 362A0041 --
Charge Face Structure GECA ESL Drawings 362A0014 sheets 1 to 7 - Civil "A" information
. . GECA ESL' Drawings . 36230052 Sheets 1 tx) 9 - Civil 'B&C information.
A4.1.3 Structural Desian Calculations A4-2.2.3 Reference Desian Calculations
.A4-2.3.4 Reference Desian Calculations
-A4-2.4.2 Reference Desian Calculationg 1A4-2.5.2 Reference Desian Calculations
~A4-2.6.2 Enference Desian Calculations 7q , A4-2.7.2 Egference Desian Calculations A4-2.8.2 Reference Desian Calculations A4-2.9.2 Reference Desian Calculations 6
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A4-2 '. 3 0. 2 Reference Desian Calculations 5798-2 page 3 of-3' s
A4-2.11.4 Reference Desian Calculations A4-2.12.2- Reference Desian Calculations A4-2.15.11 Reference Desian Calculations (3) LI have personal knowledge of-the criteria and procedures utilized by Energy Applications Division of Foster Wheeler.
in. designating information as-a trade EnergyCorporationileged/confidantialinformation:ofa-secret, or a, priv commercial or financial nature
.(4) . 7The following informationLis 3.urnished pursuant.to-the (b (4), for considera-provisions of paragraph 10CFR 2.790 tion ~by the Commission in determining.w)hethe s
tion-sought:to be withheld from public disclosure should be-
' withheld.
(1) The informacion sought to be withheld'from public:
disclosure consists of design drawings, manufacturing details,! technical-specifications, materialLspecif1-
'. cations and analytical / experimental results which are owned and held in confidence by Energy Applications
-Division'of' Foster Wheeler-Energy-Corporation and is not to be1 disclosed to anyLthird party withor.t first obtaining.that party's written agreement'to hold'the information-in cantidence.,
t (ii) The information is- of a typeccustomarily held in: confi-o dance by Entrgy-Applicartions Division of Foster Wheeler.
Energy Corporation cand is not customarily' disclosed to1the public.and 1s1 transmitted to the Commission in confidence.-
(iii)- The information-to the best-of my_ knowledge and. belief,.
is'not available in public sources.
(iv) Publicl disclosure of the information is likely to cause substantial harm to the competitive position'of Energyx Applications Division of Foster Wheeler-Energy Corpora-- '
gc tion.-
c, 7 Fl $O
- b. K. Kgarwal \ Date General Manager y- AM o ,
GRACE RUSSO NOTARY PUBLIC OT NEW JERSEY Nof*47 b da/C My Commission En; ires Au;;. 17,1992
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~ ; ., ,u 28' > ' ~" Attach' ment D to P 90236-July 23, 1990 y ,
Page 1 of 9
, LIST OF ENCLOSED REFERENCES. EVALUATIONS CALCULATIONS; AND COMPUTER ANALYSES-
,i SAR SECTION 2-r 0 --PSC Drawing- 172-1.01,LSheets 1 thru.4 of 4,
" Property Survey Map. i i
, - PSC Engineering Evaluation: EE-DEC-0029,:
"20-Year Demographic Projection Within 5-Mile Radius j of the-Independent Spent Fuel Storage' Installation 4
(ISFSI)."
- PSC Design Criteria 2 (DC-2), " Plant Site."
- CTL/ Thompson- Report, "Geotechnical Services Entrance Facility, MVDS Facility, f,SFSI Road,' Parking and Leach Field, Fort St.
- 4 Vrain Generating Station, Platteville, Colorado."
, SAR SECTION 3 l 3
. . - PSC' Engineering Evaluation EE-DEC-0023, .
" Fort St. Vrain Decay Heat Analysis:for-Spent Fuel." i
- PSC' Engineering Evaluation EE-DEC-0028, "ISFSI Flood Analysis (From the .FSV. Storage Ponds)."
- PSC Design Criteria.70 (DC-70), " Structures-General."
-; PSC Engineering Evaluation EE-FP-0019, " Independent i Spent: Fuel: Storage Installation Fire Hazards Analysis." ;
1
- GEC Technical Specification No. 362 F 0001, " Modular Vault j Dry Storage -Project Data File." j u
- GA Report No. 910055, " Nuclear Safety of FSV ISFSI." l
- GA Document-GADR-55 Volume II, " Consolidated Design Report
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for the Model FSV-1A Package."
- GA Report No. GAMD-10493, " Summary of Nuclear Critically Safety for the FSV HTGR Fuel." i
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Attachment D t'o P 90236L 1 L
', - July 23,i1990 Page'2 of 9,
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f' SAR SECTION 4- .,
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" - PSC Engineering Evaluation EE-DEC-0031, " Corrosion Issues 1
.Related to the Interior of the:ISFSI. Storage Canisters."
' PSC Certificate of Compliance No. 6346, FSV-1A and FSV Shipping Casks. ,
y 0
SAR SECTION 5 l 7' - GEC . Technical Specification'No. 362 F 0027, " Fort St. j
- Vrain MVDS ' Interlock Schedule." l h
SAR SECTION 7 t'
- PSC Engineering Evaluation EE-DEC-0026, "Use of Origin-S :
p Computer Code for Fort St. Vrain' Applications." 'l L
,,, SAR SECTION 8 1
- GEC Design Calculation 1 and 2, " Fort St. Vrain MVDS
-Chapter 8.SAR." ,
SAR APPENDIX A3-1 .
- ' ' British Hydromechanics Research Association, " Internal Flow
- 1 Systems." a
- GEC/ University of Bristol' Report TVL 9016, " Wind Tunnel ,
Investigation on the Fort St. Vrain MVDS."-
. GEC Report ESL/TM(90)37, " Design and Analysis of I y Dry Stores (DADS), Validation of' Version C."
+ - GEC Calculation File- No. JH2879/941/TH/200, " Fort St. Vrain MVDS 7 Thermal Calculations on Vault", Calculations 4, 7, 8,11, 13 thru 20, 22. 1 I
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- Y 1 Attachment D to P 90236L ,
July 23;-:1990' N" ,
Page,3 of 9
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- SAR APPENDlX A4-1
- GEC Drawings'362A0014 Sheets 1 to 7-- Civil "A" information
- GEC Drawings 362A0052 Sheets 1 to 9 --Civil "B&C" information I GEC Calculation No. 001
" Fort St. Vrain Structural Design Calculations" m D01.1 METHOD-STATEMENT D01.2 LOADING 4
- 1. 2. I '- Tornado
~
, l.2.2L Snow ..
j 1.2.3 Temperature
% 1.2.4 Impact j 1.2.5- Flood ]
l 1.2.6 Normal Wind 001.3; STRUCTURAL STEELWORK AND CLADDING 1.3.1 Main.Steelwork Frame ;
1.3.2 Structural Steel to Concrete Connections a 1 ,
1.3.3 Stairway l DC1.4 EXHAUST STACK
- 1. 4. l' Exhaust Stack in Main Wall-
< l.4.2 -.CanopyLand Spoilers g D01'.5 CELLS AB0VE FOUNDATIONS 1.5.1 Vault Walls 1.5.2 -Cask Receipt Bay 1.5.3 Standby Storage Tube Area 1.5.4 Walls Above Charge Face 1.5.5 ' Extension Walls to Inlet Duct .
I
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MV. W'A",,p
? 1 (Attachment D to P-90236-: j
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. Page 423,1990.- of 9 , ,i m
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k, #. <-p DC1'. 6: FOUNDATIONS-y' tj:l . .
$ g, w 1.6.1 Basemat-Geometry i l.6.2 Basemat Contact Pressure, DBE & DBT Loads
+p y ;
1.6.3 Building' Settlements-D' 11.6.4- Basemat Design l 1 ,
& DCl.7 COLLIMATORS :
- - 001.8 MISSILE IMPACT CONSIDERATIONS l
j 1.8.1 - Dropped Loads-1.8;2 Tornado Borne Missil'e ;
1.8.3 4 Flood: Impact 001.9~ CAST-IN ITEMS t
sal'4 SLISMIC ANALYSIS j f .
SA1.5 S0ILS STRUCTURE. INTERACTION SPl.5 ~S0ll REPLACEMENT SPECIFICATION 4
- SAR' APPENDIX A4-2 1 . . . . .
L - GEC Calculation No.' A4-2.2.3 't 1
L x : Calc 1 Charge' Face Structure Stiffness.
Calc 2-) Weight of Charge Face Structure.'. ,l m
Calc' 3- . CHM.and. Valve Bolting to CFS.
- Calc 4 Seismic Loads from CHM and Valve Connected to CFS. r j,
i Calc 5- -Deflections and Stressing of CFS During Normal Operations. ,
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Attachment D to P-90236
, July 23, 1990.
Page 5 of_9-m GEC CalculationLNo. ~ A4-2.3.4--
Calc 1 Basis of The-Design Temperature and Pressure For The FSC.-
Calc - 2 Dimensional Constraints of- Fuel- Elements..
Calc 3 Metallic 'O'- Ring Seals.
- Caic 4 FSC Boundary Calculations, t
Calc 5 FSC~ Pressure Test.
Calc 6 FSC Corrosion Allowance.
Calc 7 FSC Lifting Feature.
~Cale' 8 Thermal Expansio'n of the FSC at Design-Temperature..
' Calc 9 Center of Gravity of the FSC.
Calc:10 Fission Product Gas Release.
- GEC Calculation No.! A4-2.4.2 Calc l ' Center of Gravity land Angle of Topple of CHM-Calc 2. Stresses in CHM Supports Due to Drop of 4 in.
Calc 3 - Not Used.
. Calc 4 - CHM Stresses in- Lifting Beam and Top Plate.
. GEC- Calculation No. A4-2.5.2 Calc 1 Stresses in Raise / Lower Mechanism.
.' Calc 2 Grapple Suspension System, Assessment of Impact
' Loads.
- GECC' alculation No A4-2.6.2 f
Calc 1. Fuel Storage Container Grapple - Loads and Stresses
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$ 10 Attachment D to'P-90236
' July 23,1990 L "H @ f.C '
~Page 6 of 9-A 3-r
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- GEC Calculation No. ' A4-2.7.2 Cal'c 1 IFE Grapple. Actuation loads Calc 2 IFE Grapple. Misalignments of: Sword !
.L .?
b Calc 3 IFE Grapple. Shape of-Interlock Cam !
h .
Calc 4 -
IFE Grapple. Self Centering Device l 1 (
m Calc 5 IFE Grapple. Stresses in: Shaft Fixing Calc 6 IFE Grapple. - Approx. Weight !
k Calc 7 'IFE Grapple. Approx. Gear Strength i
- GEC Calculation-No. A4-2.8.2 i Calc.l. Filtration Unit
- GEC Calculation No. A4-2.9.2 [
Calc l- Stress Induced in Valve Securing = Bolts Against the 4-MVDS-Crane: Lifting. Capacity.
i
- GEC- Calculation No. A4-2.10.2 4
Calc 1 Stress Induced-in SPHD Location Pegs Against"the MVD.C~
l Crane Lifting Capacity.
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- GEC Calculation No. 'A4-2.11.4 Calc 1 Basis of design temperature and associated pressure- ,
for the SSW/NSW.
Calc 2 Vessel Boundary Calculations. l
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, Calc 3 Pressure Testing Requirements of the- SSW/NSW.
Calc 4- Vessel Corrosion Allowance.
.a t
Calc 5 Weights and Center of Gravity of the SSW/NSW.
Calc 6 Thermal- Expansion of the.SSW/NSW.
- GEC Calculation . A4-2.12.2 Calc 1 Stresses in the Support Structure of the Transfer Cask Load / Unload Port.
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LAttachment D to P 90236 L*;
LG July =23,:1990 W Page 7 of 9_
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i , :- GEC Calculation No. A4-2.15.11 t:
- Calc 1 Key interlock System
- Calc 2 Grapple Operation and Height Limits Calc 3 CHM Weight _ Sensing Trip levels Calc 4: Effects'of Incorrect Interlock Selection Calc 5 Grapple Solenoid Operation Calc 6 Interlock Summary
. SAR APPENDIX A7-1
-GEC Technical' Specification No. 362 Fl 0206,
-" Specification for Neutron Source Handling."
- GEC Calculation File No. JH2879/941/SH/300, " Fort St.
> ,Vrain MVDS Vault.& Surround Shielding."
, Calculations Volume 1; 1, 2,.4 thru 12 Volume'2; I thru 4'
.-:GEC Calculation File No; JH2879/941/SH/301
+ " Fort St. Vrain MVDS Cask and FHM Shielding."
- Calculations Volume 1; 1;thru 9, 12,;13 Volume 2;--l', 2 GEC Calculation File No. JH2879/941/SH/302, W "
Fort St, .Vrain MVDS Neutron Shielding."
Calcti'.ations 1 -thru 12 f
I
- GF'. Computer File, "RANKERN - A Point Kernal Integration Code for Complicated Geometry Problems."
- GEC Computer File, "MCBEND - A Monte Carlo Program for Shielding Calculations."
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, Attachment D to P-90236
,c July 23 1990:
Page 9 of 9 p ,
SAR APPENDIX A8 - GEC. Drawings No. 362A0007, Fuel' Storage Container
- GEC Drawings No. 362A0029, FSC Leak Test Eluipment
- GEC Drawings No. 362A0041, Charge Face Stricture 2I 9
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"#- Attachment D'to P-90236-
- July 23, 1990
, .Page 8 of9
. 7 SAR APPENDIX A8-2
- Cale= 1 -SSW Tube Seismic Stresses-
- Calc 2 Storage Tube- Fixing Bolts .
-- Calc 3 ' FSC. Seismic- Calculations'
-- Cale- 4 Assessment of Seismic Acceleratior. Forces
- Calc 5 Fort:St.- Vrain Container Handling Machine-
- Calc 6- Fort St. Vrain Container Handling Machine
- Calc. 7 Not Used.
- Calc 8 Container Handling Machine
-- Calc 9 Fort .St. Vrain Container Handling-Machine SAR APPENDIX A8-3
- Calc 11- Impacts on Charge Face Structure Due to MVDS Crane Failure
~
- Calc 2 Impact on CFS'from; Tornado Generated Missile 1
ec; SAR APPENDIX A8-6:
- Calc 1. I'mpact Stresse!. in the Fuel Storage' Container 4 and Storage We'll Tube
-SAR APPENDIX A8-8
- Cale 1 l. IDS Cask Receipt Bay, Cask Drop and Toppling onto Floor Slab and Vault Wall
- Calc 2 MVDS, Impact loads onto Civil Structure Due to 1
Equipment' Drops SAR APPENDIX A8-9
- GA Report- No. 910061, " Fission Product Release Inventory."
- GEC. Calculation File No. JH2879/941/SH/600, I
" Fort-St. ~Vrain MVDS Radiological Release Assessment."
Calculations 3, 5, 9,12 P
_ _ _ _ _ _ _ _ _ _ _ _ _