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Results
Other: ML20079Q405, ML20079Q414, ML20082F335, ML20093C080, ML20099J326, ML20099J334, ML20137L067, ML20137L073, ML20137N914, ML20141N187, ML20141N189, ML20203P944
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MONTHYEARML20079Q4141983-09-30030 September 1983 Safety Parameter Display Sys Program Plan, in Response to Generic Ltr 82-33,Suppl 1 to NUREG-0737 Project stage: Other ML20082F3351983-11-0404 November 1983 Requests Info Re NRC Schedule for Preimplementation Review of Safety Parameter Display Sys.Nrc Review Needed to Enable Further Implementation of NUREG-0737,Suppl 1 Requirements Per Generic Ltr 82-33 Project stage: Other ML20079Q4051984-01-20020 January 1984 Forwards Safety Parameter Display Sys Program Plan & Responds to NRC Re Control Room Design Review in-progress Audit.Audit Proposed to Take Place During Wk of 840312 Project stage: Other ML20137L0731984-08-31031 August 1984 Rev 0 to Procedure EIP-24, Test Procedure for Performance & Isolation Testing of 1E Analog & Digital Isolators Project stage: Other ML20093C0801984-09-19019 September 1984 Informs That Safety Parameter Display Sys (SPDS) SAR Will Be Submitted by 841114.Preimplementation Audit Results Received 4 Months Later than Expected.Schedule for Submittal of SPDS Info Requested in NRC Will Be Provided Project stage: Other ML20099J3341984-11-13013 November 1984 Revised SPDS Program Plan Project stage: Other ML20099J3161984-11-13013 November 1984 Forwards Response to NRC 840914 Request for Addl Info Re SPDS Sar,Rev 0 to SAR, Fort St Vrain SPDS & Revised SPDS Program Plan Project stage: Request ML20099J3261984-11-15015 November 1984 Rev 0 to Fort St Vrain SPDS Sar Project stage: Other ML20141N1891984-12-0707 December 1984 Rev 2 to Procedure EIP-30, Isolator Circuit Differential High Voltage Fault Test Procedure Project stage: Other ML20107C1021985-01-31031 January 1985 Responds to 850131 Request for Addl Info Re SPDS Isolators. Description of Measures Taken to Protect Safety Sys from Electrical Interference Generated by SPDS Will Be Provided by Aug 1985 Project stage: Request ML20137L0671985-08-0101 August 1985 Rev 0 to Procedure PSCC-1-EIP-24, Test Procedure for Qualification of Fort St Vrain Electrical Isolation Sys for Public Svc Co of Co Project stage: Other ML20137L0561985-08-26026 August 1985 Forwards PSCC-1-EIP-24, Test Procedure for Qualification of Fort St Vrain Electrical Isolation Sys... & Rev 0 to EIP-24, Test Procedure for Performance & Isolation Testing..., Per NRC Request for SPDS Review Project stage: Request ML20137N9141985-09-0505 September 1985 Forwards Test Plan Used in Testing SPDS Isolation Equipment from Interference & Provides Action Taken Re Info Needed for NRC Review Project stage: Other ML20141N1871986-02-19019 February 1986 Forwards Response to 860103,14 & 15 Requests for Addl Info Re SPDS Project stage: Other ML20203P9441986-04-29029 April 1986 Clarifies to NRC Re Spds.Forwards Rev 2 to Procedure EIP-30, Isolator Circuit Differential High Voltage Fault Test Procedure Project stage: Other 1984-08-31
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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
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1 i
O Public Service ~
2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 mo s.-o.
Company of Colorado April 29, 1986 Fort St. Vrain Unit No. 1 P-86313 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Mr. H.N. Berkow, Director Standardization and Special Projects Directorate Docket No. 50-267
SUBJECT:
Safety Parameter Display System
REFERENCE:
PSC Letter, Warembourg to Berkow, dated February 19, 1986 (P-86119)
Dear Mr. Berkow:
The purpose of this letter is to clarify four points in the above referenced letter.
- 1) Clarification of PSC Response to NRC Comment Number Two (2)
PSC will limit the available fault to the isolator cabinet by installing a 4 amp Amp-trap Form 101, Catalog Number A13Z fuse in the distribution panel, in series with a 15 amp circuit breaker.
- 2) Clarification of PSC Response to NRC Comment Number Four (4)
The fuse f1 is not a standard feature of the iso)ator circuit cards provided by Energy incorporated. Thus the fuse was not present during the testing described by the Test Report (Attachment 2 to P-86119) that was supplied to substantiate qualification of the circuit card. g CP e605000387 860429 11 DR ADOCK0500g7
'P-86313 April 29, 1986
- 3) Clarification to Class IE Rating of Isolators The isolators being purchased by Public Service Company of Colorado are being purchased and are to be installed as Class IE equipment.
- 4) Clarification to the Handwritten Notes on Attachment 2 to P-86119,.Page 7 of 9, (i.e. 60 hz RFI Greatly Exceeds .25 mv and 60 hz RFI Greatly Exceeds 1.5V).
The RFI voltages were caused by using a variable resistor with 480 volts applied across it to control.the current in the test. These RFI voltages were measured before the test started. Attached is a. copy of a letter from Energy Incorporated explaining these notes.
Should you have any questions regarding these clarifications please contact Mr. M.H. Holmes at (303) 480-6960.
Very truly yours, J. p thus~d D. W. Warembourg, y Mahager Nuclear Engineering Division DWW/ MEN:pa Attachment
- Attachment to.P-86313
~
/ d INTERNAL LETTER EI-90-028-78 TO: Ken Merrill REF: SE-MTW-001-86 FROM: Matt Weseman O M DATE: April 18, 1986
SUBJECT:
Clarification of the Background floise Level During the Analog Isolator High Voltage Fault Test (WAP EIP-004)
DISTRIBUTI0ti: DWADD0UPS, WAP EIP-004 File, SE-MTW-RF The attached report should clear up all questions concerning the test results of the Analog Isolator High Voltage Fault Test.
1 The questions arose when copies of this test package were circulated without
~' the attached test data included.
Note: The fault test data is recorded on a 30 foot section of chart paper.
Since the completed test record copy of the test procedure contains ab-solutely no test data (only test results), the questions about the test and its validity are well founded.
In order to dispell these concerns, I have written the attached report and attached a copy of part of the chart recording. Unfortunately, due to the copying and reduction processes, the resolution of the chart is practically nonexistant. If it helps a little, I'll have achieved my goal.
dll F1 ,
ENERGY INCORPORATED CALCULATION / WORK SHEET P. O. Dox 736 M Idaho Falls, Idaho 83402 SHEET 1 OF 2 CLIENT: PROJECT:
El Products. REF: WAP EIP-004 COMPONENT / SYSTEM PgRPAR D BY: DATE: CHECKED BY: DATE:
Analoa Isolator 480 V Fault Test 'N/ - 4/18/86 N/A Introduction On December 18, 1984 the four channel analog isolator assembly (00798 series) was tested for high voltage, high power fault isolation performance.
In this test the output (non 1E) side of one of the isolator channels was subjected to a 480 VAC rms,10 amp minimum fault, while the isolator inputs (1E side) were monitored for isolation.
The actual test was performed to Energy Incorporated procedure EIP-30 and under the auspices of work activity package (WAP) EIP-004 (Energy Incorporated Products).
During the test a high amount of electrical interference was noted. (The level of measured noise on the signal lines significantly exceeded the signal level of the acceptance criteria.) This note has raised questions and concerns as to the validity of the test.
Scope The purpose of this report is to explain the interference problems encountered in the test and to show that the results of the test were indeed valid.
flote: This test was performed, not to determine the level of isola-tion, but to find out if the isolator could withstand the fault and still maintain a specific level of isolation.
Discussion Due to the relatively high voltage and power requirements for the test (480 Vrms and ~5000 watts), it was performed in a very noisy environment.
Radiated interference from the incoming power line resulted in ambient noise levels as high as 85 times the anticipated signals.
flote: This is to be expected in any system where .25 millivolt signals are in a 480 Vrms environment.
Because of this high system noise level, all signal measurements were made by determining the changes in signal levels occurring at the point of fault application. (Since all electrical signals were at the same frequency and phase, this is a valid method.) Therefore, the signal levels were noted and recorded before the application of the fault, (t;his explains the notes on page 7 of WAP-EIP-004, section 6.0), during the fault, and after the fault.
w - ... .
l J
2 ENERGY INCORPORATED CALCULATION / WORK SHEET
/ P. O. oom 73G SHEET 2
_OF 2 Idaho Falls. Idaho 83402 CLIENT: PROJECT: ~
EI P rod u c t s .- REF: WAP ElP-004 COMPONENT / SYSTEM PR,Ep Eg,0Y: DATE: ' CHECKED BY: DATE:
Analog Isolator 480 V Faul t Test N/.,, 6?' 4/18/86[- 'N/A The results of the test showed that the actual signal levels (without the noise) were on the order of < .18 m Vrms (maximum chart resolution, signal level changes were imperceptible). Since this level is below the acceptance level of .25 m Vrms (1.5 Vrms on the power supply lines) the goal of the test was achieved.
Conclusion As shown in WAP EIP-004 and as discussed above, the analog isolator passed
-the high voltage fault isolation test with margin.
The acceptance criteria of the test was met. This shows that the analog isolator provides more than [20 log (.25m/480)] 126 dB of isolation at 60 llz Note:
The above test results and conclusions are apparent when the test WAP is reviewed in its entirety (chart recordings included). liowever, if the test WAP is to be reviewed without the test data then the addi-tional explanations set forth here should be included.
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ww_Q cNEMf INCORPORATED TITLE ISOLATOR CIRCUIT DIFFERENTIAL HIGH VOLTAGE FAULT TEST PROCEDURE DATE PREPARED BY W'Y WAm%-n 'l" K -Sy REVIEWED BY C i&df df RELEASE DATE CUALITY ASSURANCE ' " /O-1 ? -N PREPARED FOR PROJECT MANAGER --
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REVISIONS l
NOTE: All revisions are flagged with the symbol d in the right margin j where N is the number of the revision.
j Ree. 0 - Issued for Use - 10/31/84 Rev. 1 - Expanded Test to Include Adjacent Isolator Channels - 11/29/84 I' 2 Rev. 1 - Procedure Corrections - 12/7/84 h/#/Gud l
Ml M FOR llEORMATlDi ONrYrarm LSSUE DATE APR 151986 Y gunJ uui si r#"I Q- - l- 0 0 PROCEDURE NO. EIP-30
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n TABLE OF CONTENTS PAGE 1.0 PURP0SE............................................................. 2 2.0 RESP 0NSIBILITIES...................... .......................... . 2 2.1 Te s t E n g i n e e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.2 Qual i ty As surance Representa tive. . . . . . . . . . . . . . . . . . . . ...... .. 3 2.3 Test Technician................................................ 3 3.0 TE S T PR E R E Q U I S I TE S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .,. . . . . . 3
, 3.1 Required Drawings and Special Instruction s. . . . . . . . . . . . . . . . . . . . . 3 3.2 Equipment Required.................................. ... ...... 3 3.3 Inspection.....................................................4 3.4 P roc e du re Do c ume n ta ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 4.0 EQ U I PM E N T C AL I B R AT I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5.0 TEST PROCEDURE............................ .................. . .... 5 6.0 ACCEPTANCE CRITERIA................................................. 6 FIGURE 1 - DIFFERENTI AL VOLTAGE ISOLATION TEST SETUP FIGURE 2 - HIP 0T TEST SETUP ATTACHUENT1-EIP-30DATASHEET REVISION NO. PROCEDURE NO, em an I, 2 PAGE 1 OF g EI-646 UXQLLXavUd -
-p 1.0 PURPOSE This procedure describes the methods to be used when performing a high voltage fault isolation test. Caution : This is a potentially destructive test and requires dangerous high voltages. When performing the test, employ adequate safeguards to protect against small projectiles, bright flashes, and high voltages.
The test involves applying a 483 Vrms,10 amp (nominal) source to the out-put of a single Energy Incorporated isolation amplifier and observing the effects. During the test, the 480 volt source will be applied to the output of channel 2 of the isolator card (798-X assembly) while the inputs of all four isolator channels are monitored. After the test, the isolator card will be inspected and all damage recorded. Also, all isolator chan-nels will be hipot tested to 600 VAC and channels 1, 3, and 4 of the isola-tor card will be electrically tested for performance.
As added provisions of the test, the system power supply lines will be wired and monitored.
2.0 RESPONSIBILITIES 2.1 Testing Engineer (TE)
It is the responsibility of the testing engineer to:
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( 1-) Provide or arrange for the necessary test equipment,
! (2) Ensure the correct application of the test equipment, (3) Supervise the test technician, (4) Enter the test records in the project files, (5) Be trained to level II as per EI QAP 10-2, and (6) Notify the QC Department of the pending test.
REVISION NO. PROCEDURE NO. EIP-30 2 PAGE 2 OF 9 EI-146 w ((R2V 1 1M4)
2.2 Ouality Control Representative (QCR)
It is the responsibility of the quality control representative to:
(1) Verify the test is conducted per the procedure, (2) Verify that the data are taken per this procedure, (3) Verify the equipment used has a current and valid calibration sticker or certificate, (4) Verify the proper disposition and storage of test records, and (5) Obtain and maintain the test record copy of the procedure, data sheets, and all applicable drawings.
2.3 Test Technician (TT)
(1) Perfonn the test.
3.0 TEST PREREQUISITES 3.1 Reouired Drawings and Special Instructions The test engineer shall record all required drawings and applicable special instructions in Attachment 1.
3.2 Equipment Required (1) High voltage source: 480 t 25 VAC rms open circuit,12 amp rms minimmn short circuit current, 60 Hz, single phase.
(2) Clamp on current meter: 0 to 12 amp, 60 Hz, 5%.
(3) Vol tmeter : 15%, compatible with high voltage probe.
(4) Eight channel strip chart recorder: 60 Hz min. , Watanabe model b
WR 3101-8L or equivalent.
REVISION NO. PROCEDURE NO. Eip_30 2 PAGE 3 OF 9 EI-146
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(5) Tnree 50 a,1/4 watt resistors, two 100 n,1/4 watt resistors, one 48 0, 6000 watt resistor, two 1.4 k,1/4 W resistors, and two each 220 uF 25 volt min. capacitors, electrolytic.
(6) Hipot tester: 600 Vrms AC output,10 pamp sensitivity, Hiptron-ics model HD125 or equivalent.
(7) Test leads and switches: as required.
3.3 Inspection Verify that all special instructions will be followed, that all items under test appear to be in working order (visua.1 inspection only), and that the ,
test equipment is in good shape (no frayed insulation, etc.).
3.4 Procedure Documentation Attachment 1 will (when conpleted) become part of the test procedure docu-mentatio n. It will be incorporated into the test record copy of the test and then submitted to project management for final review.
4.0 EQUIPMENT CALIBRATION Verify that the following equipment has valid calibration dates. Record these dates and equipment descriptions in Section 3.3/4.0 of Attachment 1.
( l') Both vol tmeters, (2) Strip chart recorder, and /b$\
(3) Hipot tester.
Also record a description of the 48 0, 6 kw resistor.
REVISION NO. PROCEDURE NO. EIP-30 2 PAGE 4 OF 9 EI-646 w
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5.0 TEST PROCEDURE (Reference Figure 1 for isolation test setup.)
During the high voltage fault test, the following eight signal points are monitored and recorded with the strip chart recorder:
(1) Vg source, (2) V in channel 1, (3) Vin channel 2, (4) Vin channel 3, (5) V in channel 4, (6) V+15' (7) Y-15, and (8) V in RJC.
CAUTION: Lethal voltages will be present during the performance of this test. Also guard against small projectiles and bright flashes.
(1) Assemble the test setup as shown in Figure 1.
(2) Verify the open circuit voltage and the short circuit current of the 483 VAC source. Obtain these parameters from 31 and V3 via changing the position of switch S1. Record these values in Attachment 1.
(3) Wn11e monitoring the fault current and load voltage, apply 480 25 YAC, rms, 60 Hz to the isolator circuit output. Record both the magnitude and time response of all voltage measurements with the eight channel chart recorder.
(4) Remove the applied voltage only after the fault current has reached a steady-state value (within 10%) or after one minute (whichever is longer) .
REVISION NO. PROCEDURE NO. E r p_30 2 PAGE 5 CF 9 EI-146 m GQ4LL EMI6 - - -
(5) Af ter power is removed froin the circuit, inspect for damage caused by the test. Include in your inspection both visual (burnt or melted parts) and electrical (resistance) observa-tions. Record all findings in Section 5.0 (5) of Attachment 1.
Disconnect the chart recorder from all points.
(6) Perform an output to input Hipot test as follows.
(7) Turn on Hipot tester and set the voltage control to zero volts.
- 19) Connect the Hipot tester to the items under test as shown in Figure 2.
(9) Gradually increase the output voltage up to 600 VAC.
(10) Note and record ( Attachment 1) the leakage current when 600 VAC is reached.
(11) Wait at least 15 seconds. Note and record the leakage current a ga i n.
NOTE: If the two values (step 10 and step 11) differ by more than t 207,, record these values in Attachment 1.
(12) Turn off the Hipot tester before disconnecting.
(13) Perform an isolator performance test on isolator channels 1, 3, and 4 as per EIP-24 (Sections 8.2 and 8.7) .
Retain the test record copy of the procedure in the test WAP.
l l 6.0 ACCEPTANCE CRITERIA The isolator circuit is considered to hava passed the 600 V differential l fault isolation test if the following test criteria are met:
REVISION NO. PROCEDURE NO. EIP-30 2 PAGE 6 0F 9 EI-146
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f (1) During the application of the 480 VAC power, no more than 0.25 mV of the 60 H: signal shall appear across the 50 0 isolator input and the 100 0 isolator and RJC input load resistors.
yok . g o H+ RFE p rew Wy exceearSg /. T V pg3 (2) During the 480 VAC test, no more than 1.5 V RMS may appear across either of the power supply resistor-capacitor networks.
p d 9 (3) The extent of the damage resulting from the test shall be con-gg fined to the tested channel's output circuitry (adjacent channels shall be unaffected and the tested channel's input side must dd'AYe ( p '2 del remain intact; also, the isolator card connector must not be affected).
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(4) The leakage current resulting from the 600 VAC Hipot test shall be less than 50 pA at all times during the 1C-second test.
pe 55 (5) isolator channels 1, 3, and 4 must pass the testing as required in EIP-24, Sections 8.2 and 8.7, according to the criteria set forth in EIP-24, Sections 10.2 and 10.6 ( .1% linearity).
REVISION NO. PROCEDURE NO. gip _30 2 PAGE 7 0F 9
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~ *p ATTACHMENT 1 EIP-30 DATA SHEET Reference Section 2.0 TE Training to Level II: Name A 43, a Date Trained 3.1 Special instructions Design Drawings 79 y- / Assembly Part Number osJ Assembly Serial Number ver Rev. Assembly Drawing (if applicable)
"/s Rev. Wiring and Cable List (if applicable)
Special Instructio: s i
3.2/4.0 Egeipment Record Cal. Dates Equi pment Model Manufacturer S/N Last Due High Voltage Source W4/ : jfs : "/4 : N/A S
Current 14eter boroA: Evg : ze9g % : N/A MW Revision 2 EIP-30 Sheet 1 of 3 31-5
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( j., w eg go (10) Initial leakage at 600 VAC jj ,f], ' Arms. esco 2s0 }M.s (11) Final leakage at 600 VAC 40 /p Arms.
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(13) Results of EIP-24 (Pass / Fail): Chann 1 a5s Chann 3 /qs s Chann 4 # cts s Test Data Certi fication All test data recorded above were measured and recorded as described in procedure EIP-30.
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['r f.b,( QC Representative Date Test Data Acceptance All test data and records have been reviewed and accepted according to the criteria of Section 6.0.
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Cal. Dates Equi pment Model flanufacturer S/N Last Due Chart Recorder we 3m / : 4fsuym : yofff a / : fa o f./ : :
Voltmeter yn . uk _ 3: 2 c! l 1: <' - ]_ v fS: ?$l, tr0 TA F/u h e AY96100 f47-TV c'/7-9-s tg /g Hipot Tester rip feo _ : M,/oyt,y,c3 : /4 rod-/ sis: 8et y ev': /c g N:
48 0, 6 kw resistor:
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5.0 TEST PROCEDURE NOTES Step (1) Power source open circuit voltage h'f?,7 / TNS Power hource short circuit current /2 3 4 f f7, g (2) Fault Current Load Voltages Max See Qu f-/- Attach Chart Recorder Chart Time to Reach Steady State ^ W 5ec (5) Inspection Comments c ba se R varres k/ exp/oc(e<f c han n / sa Peres SwtoAe day g c 4,,, a q Su n ,,ap S *#U U M97g [4 ,, y p- V ~ A/O e fecf R'evision 2 Cf gU= E P-30 Sheet 2 of 3 31-5 R C U Ptt f'ra c p f u p'
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