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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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O Public Service ~ ::::::.N P.o. Box 840 Denver, Co 80201-0840 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 R.O. WILLIAMS, JR.
VICE PRESIDENT NUCLEAR OPERATIONS January 21, 1987 Fort St. Vrain Unit No. 1 P-87031 Executive Director of Operations U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-267
SUBJECT:
Partial Exemption From Annual Fees Under 10CFR Part 171
REFERENCE:
Federal Register (51 FR 33223) 10CFR Parts 51 and 171, Final Rule (G-86514)
Dear Sir:
Pursuant to 10 CFR 171.11, Public Service Company of Colorado (Public Service) hereby makes application to the Nuclear Regulatory Commission (Commission) for an exemption regarding the payment of annual fees provided for in 10 CFR 171, et seq. As you know, this recently enacted regulation requires that the fees assessed thereunder shall be reasonably related to the regulatory services provided by the Commission and shall fairly reflect the cost to the Commission of providing such services. While the Commission is concerned with recovery of the costs associated with regulation of power reactors, it was not the intent of the Commission to promulgate a fee schedule that would have the effect of imposing fees of such magnitude that owners of smaller, older reactors would suffer an adverse economic impact.
Public Service believes that the annual fee assessed under 10 CFR 171 is unduly burdensome to Public Service and, as such, requests a partial exemption therefrom so as to eliminate this burden. In support of this request, Public Service states the following. O
. t I I 87020407o4 870121 7 DR ADOCK 0500 m 7& 4A>dl,// s/J. ?25 fd/5)lf EDO 002485
. P-87031' Page 2 January 21, 1987 Public Service's Fort St. Vrain Nuclear Generating Station is unique in the industry in that it is a High Temperature Gas Cooled Reactor (HTGR). Public Service is only permitted by the Colorado Public Utilities Commission (PUC) to sell power generated therefrom at 4.8 cents per kilowatt hour. Furthermore, because of the age and size of Public Service's Fort St. Vrain reactor, Public Service believes that the Commission's general regulatory costs for the plant and the benefits bestowed on Public Service as a result of the general services rendered by the Commission are st.bstantially below that of other power reactors, thus warranting a partial exemption from the above referenced fees.
Under 10 CFR 171.11, Exemption, the criteria for the granting of an exemption from the annual fee include the following:
A) Are of Reactor: Fort St. Vrain first went critical in January 1974. As such it was the first reactor to go initially critical in 1974. Prior to 1970 eight reactors went critical, between 1970 and 1972 fifteen more went critical, and during 1973 eleven reactors went critical. Therefore, of the 107 reactors currently having operating licenses, Fort St. Vrain was the 35th reactor to go critical. This makes Fort St. Vrain among the oldest third of the nuclear units currently licensed.
- 8) Size of Reactor: Fort St. Vrain is rated at 330 MWe net.
Therefore, only three reactors currently licensed are smaller.
The three smaller reactors are Big Rock Point 1, Lacrosse, and Yankee-Rowe. The reactors that have become critical since 1980 have ranged in size from 829 MW for Farley 2 to 1221 MW for Palo Verde 1 and 2. The newer units are roughly three times the size of the Fort St. Vrain reactor. This factor alone limits the capability of the Fort St. Vrain reactor to produce revenue to offset any licensing fees imposed by the Commission.
C) Number of Customers in Rate Base: The number of customers in rate base is not applicable to Fort St. Vrain. No additional expenses of any kind, including additional fees such as the 10 CFR 171 fees, can be passed on to the Public Service rate payers as the result of a settlement of litigation between Public Service and the PUC, along with other litigants. As a result of the settlement, Fort St. Vrain was removed from the Public Service rate base.
D) Net increase in KWh Cost for Each Customer Directly Related to the Annual Fee Assessed Under This Part: No increase in KWh cost to customers of Public Service will result due to the imposition of the annual fee. Public Service is not permitted to seek '
future rate increases based on increased cests due to Fort St.
Vrain. The Fort St. Vrain Nuclear Station was removed from the
P-87031 Pag? 3 January 21, 1987 Public Service rate base as a result of the settlement of litigation referenced in paragraph C above. Of additional importance is the fact that the PUC has limited Fort St. Vrain cost recovery to 4.8 cents per kilowatt hour produced.
E) Any Other Relevant Matter Which the Licensee Believes Justifies the Reduction of Annual Fee:
- 1) Fort St. Vrain is an HTGR. Most of the Commission investigations, rule makings, program development, and regulatory research are directed to light water reactors.
The Commission HTGR related research and development activity is directed to advanced HTGR reactors and has little application to Fort St. Vrain. Substantial additional effort must be made on the part of Public Service to analyze the results of the light water reactor determinations in order to apply them to Fort St. Vrain where indicated. The NRC seldom attempts to explicitly define the relevance of a general regulatory activity to an HTGR.
Because the work that is being funded by the Part 171 annual fee is not directed to Fort St. Vrain in most cases, Public Service must incur substantial additional and unusual costs to analyze NRC regulatory information for non-light water reactor applicability and implementation. A reduction in the annual fee should be permitted to help offset the increased expenses that Public Service incurs in this process.
In an attempt to quantify the extent to which the Commission's general work product applies or does not apply to Fort St. Vrain, the Commission budget for 1987, dated February 1986, was analyzed. A document indicating the Commission staff's determination of FY 1987 budgeted costs that are related to nuclear power regulation, dated June 24, 1986, was also analyzed. Public Service then determined the portion of those costs related to nuclear power regulation that are also applicable to the Fort St. Vrain HTGR, that are partially applicable, or that are not applicable to Fort St. Vrain.
The results of the Public Service analysis are shown in Attachments I and II. The NRC allocation figures shown in column 2 of Attachment I are taken from the June 24, 1986 Commission staff document. The other figures shown in column 3 of Attachment I and columns 2, 3, and 4 of Attachment 11 are based on Public Service's analysis of the
P-87031
. Page 4 January 21, 1987 commission budget items as they are presented in the February, 1986 budget publication.
The analysis summarized in Attachments I and II indicates that less than forty percent of the Commission's work product funded by Part 171 is directly applicable to Fort St. Vrain. Included in the directly applicable category are such items as security, power reactor safeguards, and inspection and enforcement activities.
Approximately one third of the Commission budget allocated to nuclear power regulation was determined to be non-applicable to Fort St. Vrain. This category includes items such as Thermal Hydraulic Transients, a large portion of the accident evaluation work, and power reactor casework.
The remaining portion of the Comission's work product is partially applicable to Fort St. Vrain. As stated above, the partially applicable information requires extensive effort on the part of Public Service to analyze and apply the results to the Fort St. Vrain HTGR. i Since only an approximate forty percent of the 1987 budgeted costs related to nuclear power regulation are directly applicable to Fort St. Vrain, a reduction of the Part 171 annual fee is appropriate and requested.
- 2) The Commission staff has estimated that $37 million will be collected during 1987 from Part 170 fees. The April 23, 1986 Mid-Year Review indicates that $32 million of this will be obtained from Operating Licenses, Part 55 Operator Exams, the Materials Program, and inspections. These items either don't apply to Fort St. Vrain or are completely dependant on the number of operators assigned to the unit or the number of inspections required.
Unusually high user fees are charged to Fort St. Vrain under 10 CFR 170 due to the unit's unique design. Public Service is charged more than the average reactor for services provided by the Commission under Part 170. These charges are for amendments and special projects.
The charge to the approximately 107 reactors during 1987 for amendments and special projects is estimated to be $5 million or $47,000 per reactor. The actual charges paid by Public Service during 1985 (the most recent data available, 1986 billings are estimated by the NRC staff to be much higher) for amendments and special projects totaled
$149,067. The result is $102,000 or more in extra charges
~
. P-87031
. Page 5 January 21, 1987 to Public Service or approximately three times the average charge to a utility utilizing a light water reactor.
Since Public Service is billed approximately $100,000 or more per year more than the average reactor for 10 CFR 170 services, a reduction in annual fee under 10 CFR 171 is appropriate. As the efforts under Part 171 are generally not applicable to the HTGR, Public Service is paying more for the specialized services provided under 10 CFR Part 170.
Public Service's requested reduction in Part 171 annual fee is calculated based on the following formulation. Fort St. Vrain is one third the size of the new reactors and only forty percent of the work product funded by the Part 171 annual fee is directly applicable to Fort St. Vrain (950,000 x .33 x .40 = approximately $125,000). Also, l Fort St. Vrain is billed approximately $100,000 or more per year more than the average reactor for Part 170 fees, is among the older units, cannot recover additional costs from anyone, and must incur additional costs to analyze the Commission's work product.
In summary, due to the size, age, and Colorado regulatory treatment of Fort St. Vrain, as well as the absence of applicability of the Commission expenditures, recovery of which is represented by the assessment under 10 CFR 171, and additional inhouse expenses incurred by Public Service in utilizing the Commission's work product, Public Service hereby requests a reduction in the annual fee payable thereunder from $950,000 for 1987 to $125,000 for 1987 and each year thereafter.
Should you have any questions regarding Public Service's application for partial exemption, please contact Mr. M. H. Holmes at (303) 480-6960.
Very truly yours,
/
R. O. Williams, Jr.
Vice President, Nuclear Operations R0W/JW:jmt
.Le t! YNb p/so 006n
. Attachment I to P-87031 Page 1 APPLICABILITY OF NRC ACTIVITIES FUNDED BY 10 CFR PART 171 ANNUAL FEES NRC* ' Di rectly**
-Allocation Applicable to Part 171 To FSV (Dollars in Thousands)
- 1. NUCLEAR REGULATORY RESEARCH Reactor Engineering $ 44,186 .$ 0 Thermal Hydraulic 17,522 0 Transients Accident Evaluation 20,522 0 Reactor Operations 15,085 0 and Risk Waste Management, Earth 14,544 14,544 Sciences and Health less High and Low Level -7,622 -7,622 Waste SUBTOTAL $104,237 $ 6,922
- 2. NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Power Reactor $ 3,742 $ 3,742 Safeguards
- From U.S. Nuclear Regulatory Commission Funds Related to Operating Reactors, June 24, 1986
. Attachment I to P-87031 Page 2 APPLICABILITY OF NRC ACTIVITIES FUNDED BY 10 CFR PART 171 ANNUAL FEES NRC* Directly**
Allocation Applicable to Part 171 To FSV (DollarsinThousands)
- 3. NUCLEAR REACTOR REGULATION Operating Reactors $ 46,971 $13,325 Operator Licensing 8,019 0 Casework a) Power Reactors 6,045 0 b) All Other 2,227 0 c) Less Other Licenses -1,316 0 Safety Technology 12,941 0 TMI-2 531 0 SUBTOTAL $75,418 $13,325
- 4. INSPECTION & ENFORCEMENT Reactor Construction $ 2,513 $ 0 Reactor Operations 50,225 50,225 Less Nonpower Inspection -484 -484 Vendor and QA 7,139 7,139
- From U.S. Nuclear Regulatory Commission Funds Related to Operating Reactors, June 24, 1986
, Attachment I to P-87031 Page 3 APPLICABILITY OF NRC ACTIVITIES FUNDED BY 10 CFR PART 171 ANNUAL FEES NRC* Directly**
Allocation Applicable to Part 171 To FSV (Dollars in Thousands)
Enforcement, Technical 18,178 18,178 Support and Incident
Response
a) Less Technical -1,175 -1,175 Support to Investigations b) Less Allegation -1,314 -1,314 Follow-Up Specialized Technical 3,890 3,890 Training SUBT0TAL $78,972 $76,459
- 5. PROGRAM TECHNICAL SUPPORT Analysis and Evaluation $ 7,720 $ 2,700 of Operational Data SUBTOTAL $ 7,720 $ 2,700 GRAND TOTAL $270,089 $103,148
- From U.S. Nuclear Regulatory Commission Funds Related to Operating Reactors, June 24, 1986
. Attachment II to P-87031 Page 1 APPLICABILITY OF NRC ACTIVITIES FUNDED BY 10 CFR PART 171 ANNUAL FEES Directly** Partially ** No t**
Applicable Applicable Applicable To FSV To FSV To FSV (Dollars in Thousands)
- 1. NUCLEAR REGULATORY RESEARCH Reactor Engineering $ 0 $35,200 $ 8,986 Thermal Hydraulic 0 0 17,522 Transients Accident Evaluation 0 1,775 18,747 Reactor Operations 0 13,245 1,840 and Risk Waste. Management Earth 14,544 0 0 Sciences and Health Less High and Low Level -7,622 0 0 Waste ,
SUBTOTAL $ 6,922 $50,220 $47,095
- 2. NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Power Reactor $ 3,742 $ 0 $ 0 Safeguards ,
i l
- From U.S. Nuclear Regulatory Commission Funds Related to
! Operating Reactors, June 24, 1986
- Public Service Estimate i
i l
i
Attachment II to P-87031 Page 2 APPLICABILITY OF NRC ACTIVITIES FUNDED 8Y 10 CFR PART 171 ANNUAL FEES Directly** Partially ** Not**
Applicable Applicable Applicable To FSV To FSV To FSV (Dollars in Thousands)
- 3. NUCLEAR REACTOR REGULATION Operating Reactors $13,325 $ 2,895 30,751 Operator Licensing 0 8,019 0 Casework a Power Reactors 0 0 6,045 b All Other 0 0 2,227 c Less Other Licenses 0 0 -1,316 Safety Technology 0 9,693 3,248 THI-2 0 0 531 SUBTOTAL $13,325 $20,607 $41,486
- 4. INSPECTION & ENFORCEMENT Reactor Construction $ 0 $ 0 $ 2,513 Reactor Operations 50,225 0 0 Less Nonpower Inspection -484 0 0 Vendor and QA 7,139 0 0 Enforcement Technical 18,178 0 0 From U.S. Nuclear Regulatory Commission Funds Related to Operating Reactors, June 24, 1986
f.
' . . ; ', .+ . .
Attachment II' to P-87031 Page 3 APPLICABILITY OF NRC ACTIVITIES FUNDED BY 10 CFR PART 171 ANNUAL FEES Directly** Partially ** Not**
Applicable Applicable Applicable To FSV To FSV To FSV (DollarsinThousands)
Support and Incident
Response
a) Less Technical -1,175 0 0 Support to Investigations b)LessAllegation -1,314 0 0 Follow-Up Specialized Technical 3,890 0 0 Training SUBTOTAL $76,459 0 $ 2,513
- 5. PROGRAM TECHNICAL SUPPORT Analysis and Evaluation $ 2,700 $ 2,700 $ 2,320 of Operational Data SUBTOTAL $ 2,700 $ 2,700 $ 2,320 GRAND TOTAL $103,148 $73,527 $93,414
- From U.S. Nuclear Regulatory Comission Funds Related to Operating Reactors, June 24, 1986