Letter Sequence Meeting |
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Results
Other: ML20137N628, ML20138L801, ML20138Q922, ML20148Q761, ML20151P101, ML20154A545, ML20154A550, ML20196B796, ML20198D059, ML20198D068, ML20206P200, ML20212B732, ML20236G302
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MONTHYEARML20138L8011985-12-12012 December 1985 Discusses NRC 851115 Request Re Status of Licensing Issues, Util 851105 Clarification Re Schedule of CRD Mechanism Assembly Environ Qualification Testing & Util Re Tech Spec Upgrade Program Review Schedule Project stage: Other ML20138Q9221985-12-19019 December 1985 Informs of Inability to Meet 851230 Completion Date of High temp,300 F,Crd Mechanism Test & Preliminary Evaluation,Due to Difficulties,Including Orifice Valve on Mechanism.Final Rept Will Be Submitted by 860331 Project stage: Other ML20151P1011985-12-27027 December 1985 Discusses long-term Action Re CRD Mechanism Position Indication Proposed by NRC Preliminary Rept Restart & Continued Operation of Fort St Vrain Nuclear Generating Station, Per Project stage: Other ML20137N6281986-01-30030 January 1986 Provides Preliminary Evaluation Test Results of High Temp, 300 F Test of CRD Mechanism Assembly,Per .Test Completed on 860122.Assembly Performed Required Operations of Scram & Drive Motor W/O Incident Project stage: Other ML20198D0681986-05-14014 May 1986 Final Rept - Fort St Vrain CRD & Orificing Assembly High Temp Functional Test Project stage: Other ML20198D0591986-05-16016 May 1986 Forwards 908813, Final Rept - Fort St Vrain CRD & Orificing Assembly High Temp Functional Test. No Failure of Assembly Component Experienced Project stage: Other ML20206P2001986-08-22022 August 1986 Ack Receipt of Transmitting Rept Entitled, Parameter Trending Test Program. Data from Rept Will Be Incorporated Into Listed Ongoing Licensing Actions Project stage: Other ML20212B7321986-11-30030 November 1986 Evaluation of Proposed CRD & Orifice Assembly 300 F Temp Limits,Fort St Vrain Nuclear Generating Station Project stage: Other ML20236G3021987-07-30030 July 1987 CRD Partial Scram Test Results & Max Daily Temp Rept, 870703-30 Project stage: Other ML20238E9291987-09-0303 September 1987 Responds to 870731 Request for Schedule for Resubmittal of 860815 Response Re CRD Rod Position Indication Instrumentation.Engineering Evaluation Will Be Resubmitted within 120 Days of Proposed Meeting Project stage: Meeting ML20237D2251987-12-15015 December 1987 Summary of 871204 Meeting W/Util Re Licensee Latest Proposals for Licensing Actions Concerning CRD Mechanism Temp Requalification & Position Instrumentation.List of Attendees & Related Info Encl Project stage: Meeting ML20196B7961988-01-31031 January 1988 CRD Partial Scram Test Results & Max Daily Temp Rept, 880117-31 Project stage: Other ML20148Q7611988-04-0707 April 1988 Provides Proposed Plan for Requalification of CRD Mechanisms for Elevated Temps.Items for Consideration in Temp Requalification Plan for CRD Mechanisms Listed Project stage: Other ML20154A5501988-04-28028 April 1988 Temp Prediction for CRD Mechanism Motors Project stage: Other ML20154A5451988-04-28028 April 1988 Integrated Sys Study of CRD Mechanism Rod Position Instrumentation Project stage: Other ML20154A5381988-05-0606 May 1988 Forwards Rev B to EE-12-0013, Integrated Sys Study of CRD Mechanism Rod Position Instrumentation & Temp Prediction for CRD Mechanism Motors, Per 871204 Meeting Project stage: Meeting 1986-08-22
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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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h Public Service ~ ~ah c
2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 May 6, 1988 Fort St. Vrain Unit No. 1 P-88152 ,
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267
SUBJECT:
Control Rod Drive (CRD) Rod Position Indication Instrumentation
REFERENCE:
(1) NRC Memorandum, Heitner to Calvo (NRC), dated December 15, 1987 (G-87445) l (2) PSC letter, Warembourg to Calvo, l
dated April 7, 1988 (P-88121)
Gentlemen:
As a followup to our site meeting of December 4,1987 (Reference 1), Public Service Company of Colorado (PSC) is transmitting as Attachments 1 and 2 to this letter the Control Rod Drive (CRD) Rod PositionIndication(RPI)Instrumentationevaluation. Also, based on commitments set forth in Reference 2, please find enclosed in Attachment 3 PSC's evaluation of the Control Rod Drive Motor (CRDM) service temperature projection which incorporates the results of the most recent core testing.
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P-88152 Page 2 May 6, 1988 If you have any questions on either of these subjects, please contact Mr. M. H. Holmes at (303) 480-6960.
Very truly yours, b A f}(tass M k D.W.Warembourg, Manage)-
Nuclear Engineering Division DWW:CRB/dvd Attachments cc: Regional Administrator, Region IV ATTN: Mr. T. F. Westerman, Chief Projects Section B Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain
Attachment 1 to -
P-88152 l Page 1 !
l ATTACHMENT 1 I CRD ROD POSITION INDICATION INSTRUMENTATION l BACKGROUND FSV Rod Position Indication (RPI) Instrumentation deficiencies
.were originally identified in Reference 1. In response to these NRC !
concerns, PSC performed an Integrated Systems Study and submitted !
recommended corrective actions in Reference 2 to resolve the CRD RPI [
concerns. In this-response, PSC comitted to the following actions: .
(1) replacement of the full-in/ full-out limit switches with proximity limit switches; (2) replacement of the existing potentiometers with improved potentiometers which are appropriately designed and l qualified for the life and service condit, ions to be experienced. l NRC's subsequent review of PSC's evaluation and proposed I corrective actions (Reference 7) indicated that PSC's solutions were i not adequately supported, r'ssulting in a general misunderstanding l between PSC and NRC. l l
To resolve the misunderstandings, PSC proposed (Reference 4) an j onsite technical meeting te discuss the original NRC concerns. This [
meeting was conducted on December 4, 1987, and results of this meeting are reported in Reference 5. The purpose of this letter is to provide an updated PSC evaluation of CRD RPI Instrumentation. ;
DISCUSSION i f
The Integrated Systems Study for CRD RPI has been revised to i resolve remaining concerns identified in the NRC Technical Evaluation !
Report (Reference 3) and has been included as Attachment 2 to this letter. PSC's resolution of specific NRC concerns identified in {
References 1 and 3 are contained in Enclosure 1 to Attachment 1. {
v CONCLUSIONS l l
Conclusions reached as a result of this revised study remain the same :
as those presented to the NRC in December, 1987. These conclusions !
are as follows:
(1)CRD RPI Instrumentation (continuous and limit switch) currently [
installed at FSV is acceptable to meet operability requirements i imposed by the FSAR and FSV Technical Specifications, when i operated in accordance with current aaministrative limits. !
Improved maintenance and surveillance requirements support ;
operational conditions. j (2) PSC will continue to pursue the corrective actions identified !
below to further improve the reliability of CRD RPI [
i Instrumentation, i
l k
(
Attachment 1 to
-P-88152-Page 2 PSC ACTIONS:
Short Term Corrective Actions Previously Implemented and Results:
The following practices have 'been implemented to improve overall reliability of the CRD RPI:
(1) Continuous Rod Position Indication (Potentiometers):
Imposition of administrative limits on operators (which prevent overdriving of the control rods past the full-in positiori) has resulted in N0 potentiometer failures since the CRDM incidents of 1984; no addTtional short term actions are deemed to be necessary for these potentiometers pending implementation of long-term corrective action.
(2) Full-in/ Full-out Limit Switchas:
(a) All full-in/ full-out limit switches were replaced following the multiple limit switch failures in 1984; (b) As a result of improved maintenance, surveillance and N0 failures of full-in/ full-out limit operations switches havepractices, been e Eierienced since the CRDM incidents of 1984. Operator awareness of moisture ingress concerns and subsequent moisture reduction in the PCRV since 1984 have also contributed to the reduction in CRD RPI problems, Long-Term Corrective Actions:
The following activities will be implemented as improvements intended to further improve CRD RPI reliability:
(1) Continuous Rod Position Indication (Potentiometers):
(a) PSC will replace existing 10-turn dual element potentiemeters with 15-turn dual element potentiometers, which will significantly reduce the possibility of breakage of the potentiometers due to overdriving the CRDM's, These new potentiometers will be procured to specifications which will ensure that the materials are suitable for the service conditions to which they will be exposed ud will have suitable service life for their intended application.
Appropriate quality standards will be applied to the procurement of these potentiometers to satisfy their design function.
(b) Replacement of existing 10-turn dual element potentiometers with 15-turn dual element potentiometers will begin following completion of qualification analyses and type testing. This replacement is not expected to begin until after the 4th refueling and will be performed sequentially on CRDM's in the region being refueled during each subsequent refueling outage,
Attachment 1 to :
P-88152 Page 3 ;
i (2) Full-in/ Full-out Limit Switches:
i (a) To reduce mechanical wear between the limit switch shaft and i guide tube, reduced angle cams will be installed to actuate the limit switch shaft roller, per the manufacturer's recommendations. This replacement will be performed :
sequentially on CRDM's in the region being refueled during each subsequent refueling outage and is not expected to ,
- begin until after the 4th refueling.
(b) Limit switches will continue to be replaced (like-for-like);
replacement is intended to reduce the likelihood that 4
- mechanical wear or corrosion on the limit switch shaft will result in mechanical failure of the limit switch.
Replacement of limit switches will be performed sequentially ;
on CRDM's in the region being refueled during each refueling outage, commencing with the upcoming 4th refueling, ,
(c) PSC will continut to evaluate design improvements or replacement indication which will improve the reliability of RPI full-in/ full-out indication. Proximity switches which meet suitable quality and service requirements will be evaluated to determine if replacement in desirable.
1 1
l 1
4 4
4 i
Attachment I to P-88152 Page 4
References:
(1) NRC letter, Denton to Walker, dated October 16, 1984 (G-84392)
(2) PSC letter, Warembourg to Berkow, dated August 15,1986(P-86522)
(3)NRCletter,HeitnertoWilliams,datedJuly 31,1987(G-87262)
(4) PSC letter, Warembourg to Calvo, dated September 3,1987 (P-87307)
(5) NRC Memorandum, Heitner to Calvo (NRC), dated December 15, 1987 (G-87445) i
- . . - - _ --< -~ - - -- , - - __ _
- a. ,- - -,--
r Encicssre 1 to Attachment 1 )
P:ge 1 ENCLOSURE 1 NRC R0D POSITION INDICATION CONCERNS CONTROL R00 INSTRLMENTATION ANOMALIES: PSC RESPONSE:
(NRC Letter, Denton to Walker, dated 10/16/84 (G-84392))
Actions Prior to Restart (following 1984 CRDM incident):
- 1. To prevent CRDM damage and to protect rod position Plant operating procedure 50P 12-01 has baen potentiometers and limit switches, plant procedures implemented which provides precautions regarding the-
! should be changed to prevent overdriving the CRDM potential damage to the CRD RPI resulting from I past the full-in limit (yo-yo-ing). overdriving the control rod drives. Since.the implementation of these administrative controls, there have been no failures of the potentiometer shafts. Additionally, heavy emphasis is plcced on this issue during initial operator. training and operator requalification training.
- 2. Periodic surveillances of rod position potentiometers This concern has been addressed by compliance and switches should be developed and implemented in with Interim Technical Specifications 3.1.2 and interim procedures and be proposed for inclusion in 3.1.3, as implemented by supporting surveillances.
the plant technical specifications. This Additional guidance is also contained in 50P 12-01 surveillance should include verification of limit which directs operators to ensure that accurate and I
switch operability and confimation that redundant RPI is available.
redundancy has not been lost.
Long-Tem Actions:
- 3. Damage due to ciertravel should be precluded by PSC intends to proceed with their long-tem corrective installation of a positive mechanical stop or by action to replace the 10-turn dual element potentiometers providing sufficient clearance to prevent damage, with 15-turn dual element potentiometers. To' resolve the overtravel as it relates to potentiometer damage, the.
installation of a mechanical stop was evaluated and determined to be not feasible.
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Enclosure I to Attachment 1 Page 2 4 An appropriate, independent and definitive means As reported to the NRC in PSC letter, Gahm to Johnson, of verification of control rod full-in position dated 7/31/87 (P-85262), PSC has modified and strengthened should be provided because the installed rod position the requirements specified in SOP 12-01. Surveillance it,strumentation can be inadequate to verify control Procedure SR-TE-9-X (Inserted Rod Position Indication) roo oosition. In the present form, Watt-meter of the is specified to be used to accurately establish shim Msting motor is considered inadequate to verify (wattmeter test)' full-in rod position for control full insertion of control rods. It is therefore rod pairs with inoperable position indication per concluded that the Watt-meter method be refined or an FSV Interim Technical Specifications.
alternate method be developed to achieve sufficient resolution of rod position and then formalized into a plant procedure.
- 5. Conduct an integrated systems study to resolve RPI The previous 1**"grated systems study has beer revised maintenance and operability questions. to incorporate coments received during the NRC onsite technical visit in December 1987.
CRDM ROD POSITION INDICATION INSTRUMENTATION TECHNICAL EVALUATION:
(NRC Letter, Heltner to Williams, dated 7/31/87 (G-87262))
- 1. The contribution of corrosion of the full-in limit Effects of corrosion and mechanical eroston have switches was not evaluated. been evaluated in the revised integrated systems study. It has been determined that H moisture ingress events which occurred during or before 1984 resulted in corrosion of metallic surfaces of the potentiometers and the limit switches.
Increased operator awareness of the consequences H and causes of moisture ingress into the core has resulted in significantly reduced core moisture levels, and therefore reduced corrosion.
Erosion was also noted to be a problem with the limit switches due to the steep cam angle, thereby causing frictional forces to be present between the limit switch actuating shaft and the guide cylinder.
Both erosion and corrosion concerns have been ~!
to Attochment 1 Page 3 reduced by the one-time replacement of all limit switches following the CRDM incident, and the continuing program of regional limit switch replacement during region refueling. Replacement of existing cam actuators with reduced angle cams will further reduce the likelihood of limit switch failure.
- 2. The design of the replacement targets for the As discussed during the December 1987 onsite full-in/ full-out limit switches did not consider technical meeting, there is not a credible mechanism the potential for damaging the rod position for the replacement targets (or limit switch actuating potentiometers when the control rods are overdriven. cams) to mechanically interfere with the position potentiometer shaft.
- 3. The failure of the slack cable limit switches As discussed during the December 1987 onsite was not eva?uated. technical meeting and addressed in the discussion of limit switch failures in the revised integrated systems study, there have been no failures associated with the slack cable limit switches; ac* - .on of the slack cable limit switch during 1984 was proper indication of a failed CR0M cable.
- 6. The specification for the replacement rod position The specification for the replacement rod position potentiometers did not include all the potentiometers has been prepared and incorporated environmental conditions that the components into a PSC engineering evaluation to ensure could be exposed to and did not define how the that the replacement potentiometers will be potentiometers would be qualified. suitably qualified for the service conditions and operating requirements that they are expected to experience. Qualification will include appropriate consideration of the temperature qualification plan previously provided to the NRC in PSC letter, Warembourg to Calvo, dated 4/7/88 (P-88121).
- 5. The proposed replacement instruments that are important As discussed during the December 1987 onsite technical to safety (full-in limit switch and rod position meeting, the CRD RPI potentiometers and limit potentiometer) did not comply with the quality switches are non-safety relatrd components.
Enciostre 1 to Attcchment 1 Pcge 4 standard and instrumentation requirements of GDC 1 Therefore, requirements of GDC 1 and 13 are not and 13 of Appendix A to 10 CFR 50. directly applicable. PSC will take suitable precautions to ensure that replacement components will be manufactured and qualified to withstand the service conditions and operating requirements to which they will be exposed.
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l Attachment I to P.88]Sg