Letter Sequence Other |
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Results
Other: ML20083M935, ML20084H457, ML20084P594, ML20092D927, ML20094R400, ML20096C908, ML20106B579, ML20107K230, ML20112D736, ML20126C521, ML20127K137, ML20127N695, ML20128N286, ML20132G502, ML20154A542, ML20235N112
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MONTHYEARML20083M9351984-04-12012 April 1984 Discusses Problems W/Pcrv Prestressing Sys & Resultant Insp Test Results.Liftoff Tests Show Tendon Sys Operable.Nrc Permission to Return to Power Operation from Present Refueling Outage Requested by 840418 Project stage: Other ML20084H4571984-04-25025 April 1984 Forwards Relaxation Curves for Prestressed Concrete Reactor Vessel Tendon Sys,In Response to 840419 Request.No Immediate Mechanism for Controlling Sleeve Atmosphere Provided.Areas W/Indicated Corrosion Regreased Project stage: Other ML20084P5941984-05-0707 May 1984 Forwards Pcrv Tendon Sys Relaxation Curves Containing Min Design Lines,Per H Polk 840503 Telcon Request Project stage: Other ML20092D9271984-06-15015 June 1984 Responds to Requesting Details of Proposed Tendon Surveillance Program.Program Consists of Load Cell Data & Visual Insps.Surveillance Started on 840601.Program Developed Using Reg Guide 1.35 as Ref Project stage: Other ML20093J1171984-07-20020 July 1984 Forwards Rev 2 to Updated FSAR for Fort St Vrain.Rev Includes Safety Evaluations Either in Support of License Amends or in Support of Conclusions That Changes Did Not Involve Unreviewed Safety Question Project stage: Request ML20094R4001984-08-0909 August 1984 Confirms 840806 Telcon on Tech Spec Change Request Re Tendon Corrosion & Anchor Assembly Surveillance.Tech Spec Change Request Will Be Submitted by 840930 Project stage: Other ML20096C9081984-08-20020 August 1984 Responds to Re Possible Design Mods to Pcrv Tendons & Details of Evaluations & Schedule of Completion of Repts Detailing Results of Metallurgical Exams.Actions Necessary to Evaluate Design Mods for Pcrv Listed Project stage: Other ML20107K2301984-10-18018 October 1984 Updates Tendon Investigations & Corrosion Prevention Programs.Efforts Concentrated on Corrosion Prevention Methods Rather than Detailed Moisture Measurements Project stage: Other ML20112D7361984-12-14014 December 1984 Forwards Tendon Accessibility Info,Rationale for Tendon Surveillance & Info Re Corrosion Mechanism in Response to 840720 & 1029 Requests for Addl Info.Tendons Considered Acceptable If No Major Mods Necessary Project stage: Other ML20106B6131985-01-31031 January 1985 Discusses Visual Insp of Top Longitudinal Tendons,Per 850115 Meeting Request.Visual Insp of 30% of Longitudinal Tendons for Buttonheads Noted.Inconsistency Exists Between Last Mapping of Raised Buttonheads & Current Insp Results Project stage: Meeting ML20106B5791985-01-31031 January 1985 Submits Plans for Implementing Interim Tendon Surveillance Program,In Response to Concerns.Surveillance Program Will Be Based on Proposed Tech Spec SR 5.2.2,submitted in DW Warembourg Project stage: Other ML20132G5021985-03-12012 March 1985 Evaluation of CRD Mechanism & Reserve Shutdown Sys Failures & Pcrv Tendon Degradation Issues Prior to Fort St Vrain Restart Project stage: Other ML20128N2861985-05-20020 May 1985 Informs of Intent to Conduct Addl Insps of Random Sample of Pcrv Bottom Head Longitudinal Tendon Anchor Assemblies. Thirty-four Longitudinal Bottom End Caps Accessible.Ten End Caps Will Be Removed & Inspected Project stage: Other ML20126C5211985-05-23023 May 1985 Discusses Investigation of Methods to Control Tendon Corrosion Involving Establishment of Nitrogen Blanket on Pcrv Tendon Sys.Establishing & Maintaining Overall Nitrogen Blanket Sys for Tendons Highly Questionable Project stage: Other ML20127K1371985-06-0707 June 1985 Discusses Insp of 10 Bottom Longitudinal Tendon End Caps. Tendons Visually & Magnetic Particle Inspected for Evidence of Corrosion,Concavity,Water,Apparent Failures & Cracking.No Raised Buttonheads Found.All Tests Negative Project stage: Other ML20127N6951985-06-14014 June 1985 Elaborates on Util Commitments to Listed Plant Activities, Including CRD Mechanism Temp Recording,Requalification, Surveillance & Preventative Maint,Backup Reactor Shutdown Procedure,Tendons & Pcrv Integrity & Electrical Sys Project stage: Other ML20138A8551985-07-0202 July 1985 Safety Evaluation Accepting Util Tendon Surveillance Proposal.Proposal Will Lead to Maintaining Structural Integrity of Reactor Vessel.Plant Structurally Ready for Restart Project stage: Approval ML20138A8071985-07-0202 July 1985 Forwards Updated Safety Evaluation Accepting Util Commitments Re Tendon Surveillance as Basis for Restart. Util Will Incorporate Modified Tendon Surveillance Program Into Tech Specs & Provide Results 6 Months After Restart Project stage: Approval ML20132G4501985-07-0808 July 1985 Forwards Safety Evaluation Re Pcrv Prestressing Tendon Wire Corrosion Problems.Submittals & 0614 Acceptably Resolve Concerns.Lasl Evaluation Rept Encl Project stage: Approval ML20132G4761985-07-0808 July 1985 Safety Evaluation Re Pcrv Tendon Corrosion Investigation & Proposed Remedy.Tendon Surveillance Proposal Acceptable Project stage: Approval ML20235N1121987-07-0909 July 1987 Forwards Lasl Technical Evaluation Rept, Technical Assistance for Fort St Vrain Task Ii:Pcrv & Pcrv Tendon Evaluation, Final Rept Project stage: Other ML20154A5421988-08-30030 August 1988 Requests Addl Info Re Rev 7 to Schedule Commitment Items on Pcrv Tendon Surveillance Involving Provision of Schedule for Conducting Evaluation within 45 Days for Pcrv Tendon Degradation Project stage: Other 1985-01-31
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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
[Table view] |
Text
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public Servlee Company T Cdeds q
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,, 16805 WCR 19 1/2, Platteville, Colorado 80651 $
L April 25, 1984 Fort St. Vrain Unit #1 P-84119
)$@bNb, Mr. John T. Collins, Regional Administrator is .
U. S. Nuclear Regulatory Commission 'L APR 3 0 l984 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 l L
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SUBJECT:
Fort St. Vrain PCRV Tendons
- REF: 1) P-84110, Warembourg to Collins, dated 04/12/84
- 2) G-84120, Collins to Lee, dated 04/19/84
Dear Mr. Collins:
As requested in your letter (Ref. 2), we are providing relaxation curves for the Fort St. Vrain PCRV tendon system (Attachment 1). A few words of explanation are in order:
- 1. For all graphs, the curve labeled " Load Cell" is the alarm setpoint for those tendons equipped with load cells. The curve labeled " Maximum" is the tension expected in the tendons assuming relaxation losses corresponding to the maximum (i.e., Final Safety Analysis Report design) relaxation. The curve labeled " Minimum" is the tension expected in the tendons assuming relaxation losses corresponding to the minimum expected relaxation. Note that neither the " Maximum" nor " Minimum" relaxation curves should be construed as " limits" for the current situation, but are being provided for reference purposes.
- 2. From the Final Safety Analysis Report, the minimum design initial tendon stress is 1,395 KIPS for 169 wire tendons and 1,255 KIPS for 152 wire tendons (corresponding to 70% GUTS).
These minimum values were used in the development of the graphs. In all cases, the actual initial tendon stresses were above these minimum values.
- 3. For all tendons tested thus far, the lift off has been above the curves of maximum relaxation (again, for reference purposes).
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e-r To bring you up to date on our program, we have completed lift off tests of all accessible longitudinal (vertical) top head tendons.
The results of these lift off tests are shown in Attachment 2. Since these tendons were initially stressed in early 1970, the required tension (based only on the maximum relaxation curve at 14 years) is about 1,175 KIPS. Attachment 2 data confirms that all accessible vertical tendon lift off tests are well above this value.
Caution should be used when attempting to make a direct comparison between the values cited as original lift off and those for current lift off. Although we believe a reasonable correlation can be made, it must be remembered that different personnel, equipment, and methods were used for the two different data scts.
We expect to have the rebuild of a borrowed tendon jack completed shortly. Our intent would then be to perform double ended lift off L
tests on BI U3, detension this tendon, remove one good and one bad wire for evaluation, and then retension the tendon. A similar program for removal of wires from a circumferential and a top cross head tendon will also be performed. Our commitment to perform an expanded-scope surveillance test remains unchanged.
We are continuing our evaluation to determine the minimum required tendon tension to meet the design requirements of the PCRV at .any time in plant life. Although independent reviews of this evaluation are still in progress we can state that this " Design Minimum" tension will be a horizontal line which is below the " Load Cell" alarm setpoints shown in Attachment 1. Since our lift-off data to date is above the Maximum Relaxation curve, we have even further margin above any Design Minimum requirements.
In response to your inquiry concerning moisture within the tendon sleeves, as I have previously stated, there is no immediate mechanism for controlling the sleeve atmosphere. However, we have taken the precaution of regreasing the areas of indicated corrosion for the vertical tendons and of removing visible moisture from tendon caps.
We would have a similar program for accessible portions of other tendons. Our program .for wire removal will provide additional information concerning possible corrosion in the mid-length portion of other tendons including, the bottom cross head tendons.
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. i In the long term, design modifications may be warranted to minimize tendon corrosion, and these modifications are being evaluated presently. However, Public Service Company's position continues to be that the Fort St. Vrain prestressing system is operable and that any future degradation will be detected before minimum requirements are encountered. This position is based on the successful lift-off tests to date, the continuous monitoring provided by the load cells, and the enhanced awareness of the tendon condition provided by our expanded surveillance testing. Therefore, we again request a release from the Commission to return to power operation.
If I can be of further assistance, please let me know.
Very truly yours, h WW Don W. Warembourg Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station DW/alk Attachments
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. m Page 1 ATTACHMENT 2 ORIGINAL CURRENT NUMBER OF TENDON LIFT OFF LIFT OFF BROKEN NUMBER KIPS KIPS WIRES REMARKS VI-1 1,440 1,432 0 VM-1 1,440 1,409 0 VI-2 1,440 1,348 5 VM-2 1,430 1,404 0 VI-3 1,438 Not 0 Accessible VM-3 1,470 1,445 0 Load Cell Alarm Low = 1,160 KIPS VI-4 1,440 1,422 0 VM-4 1,480 1,438 0 VI-5 1,450 Not 0 Accessible VM-5 1,440 1,412 0 VI-6 1,460 Not Not Acessible Accessible VM-6 1,425 1,412 0 VI-7 1,440 1,430- 0 VM-7 1,445 1,403 0 V0-7 1,430 1,398. O VI-8 1,455 1,438 0 VM-8 1,445 1,385 3-VI-9 1,445 Not- 0 Acessible VM-9 1,460 ~1,451' 0-
e Page 2 ATTACHMENT 2 ORIGINAL CURRENT NUMBER OF TENDON LIFT OFF LIFT OFF BROKEN NUMBER KIPS KIPS WIRES REMARKS VI-10 1,470 1,390 5 Load Cell Alarm Low = 1,160 KIPS VM-10 1,450 1,344 3 VI-11 1,440 1,423 0 VM-11 1,440 1,380 1 VI-12 1,435 Not 0 Accessible VM-12 1,460 1,438 0 VI-13 1,445 Not 0 Accessible VM-13 1,440 1,424 0 VI-14 1,440 1,443 0 VM-14 1,460 1,430 0 V0-14 1,440 1,380 4 VI-15 1,455 1,427 0 VM-15 1,450 1,417 0 VI-16 1,450 1,422 0 VM-16 1,460 1,438 0 VI-17 1,450 1,433 0 VM-17 1,484 .1,454 5 Load Cell Alarm i : Low = 1,160 KIPS VI-18 1,450 1,417 0 VM-18 1,450 1,438 0-
r Page 3 ATTACHMENT 2 ORIGINAL CURRENT NUMBER OF TENDON LIFT OFF LIFT OFF BROKEN NUMBER KIPS KIPS WIRES REMARKS VI-19 1,430 1,406 0 VM-19 1,450 1,438 0 VI-20 1,450 1,443 0 VM-20 1,460 1,448 0 VI-21 1,455 1,443 0 VM-21 1,445 1,442 0 V0-21 1,440 1,401 0 VI-22 1,455 1,444 0 VM-22 1,420 1,412 0 VI-23 1,425 1,433 0 VM-23 1,440 1,417 0 VI-24 1,440 1,430 0 Load Cell Alarm Low = 1,160 KIPS VM-24 1,425 1,422 0 VI-25 1,430 1,428 0 VM-25 1,460 1,443 0 VI-26 1,445- Not- 0 Accessible VM-26 1,450 1,433 0 ..,.
VI-27 1,450 1,454 0 VM-27 1,450 1,428 0 VI 1,440 Not 0-i Accessible o
r Page 4 ATTACHMENT 2 ORIGINAL CURRENT NUMBER OF TENDON LIFT OFF LIFT OFF BROKEN NUMBER KIPS KIPS WIRES REMARKS VM-28 1,440 1,417 0 V0-28 1,440 Not 0 Accessible VI-29 1,460 1,446 0 VM-29 1,430 1,404 1 VI-30 1,420 1,406 0 VM-30 1,460 1,296 21 VI-31 1,450 1,438 0 VM-31 1,450 1,429 0 Load Cell Alarm Low = 1,160 KIPS VI-32 1,430 Not 0 Accessible VM-32 1,448 1,423 0 VI-33 1,440 Not 0 Accessible VM-33 1,460 1,449 0 VI-34 1,440_ Not 0 Accessible
'VM-34 1,450 1,443 0 VI-35 1,430 1,433 0 VM-35 1,450 1,428 0-V0-35 1,480 Not 0 Accessible VI 1,445 1,460 0
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