Letter Sequence Other |
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Results
Other: ML20137H372, ML20197B076, ML20204G924, ML20205T170, ML20206B329, ML20206B459, ML20206F887, ML20207K386, ML20207K441, ML20207K446, ML20207K506, ML20207K512, ML20207P779, ML20207P991, ML20207P993, ML20209E329, ML20209F187, ML20209G043, ML20210A740, ML20210A748, ML20210A757, ML20210T436, ML20210T655, ML20210T686, ML20211D992, ML20211E058, ML20211E084, ML20211E110, ML20211G583, ML20211N368, ML20212M102, ML20214Q988, ML20214Q998, ML20214S836, ML20214S958, ML20215G796, ML20215H964, ML20215H973, ML20215J855, ML20215J871, ML20215L534, ML20216D570, ML20216E230, ML20234C109, ML20235E520, ML20235F508, ML20245C018
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MONTHYEARML20137H3721985-11-26026 November 1985 Memorandum & Order Granting Extension of 851130 Deadline for Environ Qualification of Electrical Equipment to 860531 & Approving Proposal to Allow Operation w/35% Reactor Power Limit During Interim.Served on 851127 Project stage: Other ML20211E0841986-02-20020 February 1986 Issue a to Fort St Vrain:Delayed Firewater Cooldown;Effect of Liner Cooling on Orifice Valve Temps Project stage: Other ML20209F1871986-03-18018 March 1986 Fort St Vrain Steam Generator Temps During Interruption of Forced Cooling from 105% Power Project stage: Other ML20214S9581986-09-25025 September 1986 Requests That Util Take Listed Actions Re Three Repts Submitted Concerning Firewater Cooldown Analysis,Per NRC Review & 860917 Telcon.Response to Item 1 Requested within 15 Days of Ltr Date & Item 2 at Time Analysis Submitted Project stage: Other ML20211E0581986-09-30030 September 1986 Effect of Delayed Firewater Cooldown W/Loss of Liner Cooling on Pcrv Temps Project stage: Other ML20215G7961986-10-10010 October 1986 Advises That Info Requested in NRC Re Best Estimate Schedule for Resolution of Problems Encountered W/Firewater Cooldown Analysis Will Be Submitted as Part of Util Graduated rise-to-power Program Project stage: Other ML20197B0761986-10-22022 October 1986 Informs That Util Will Update & Submit Rept on Chernobyl Accident by 861126.Update Will Ctr on Graphite Related Concerns,Including Analysis of Worst Case Explosive Gas Mixtures & Comparison of Reactor Kinetics Behavior Project stage: Other ML20211G5831986-10-22022 October 1986 Anticipates Completion of Steam Generator Analysis & App R Modeling Reanalysis Work by Feb 1987,per 860918 Telcon W/Nrc Re Steam Generator Cool Down Studies for App R Project stage: Other ML20215L5341986-10-23023 October 1986 Staff Requirements Memo Re Commission Briefing in Washington,Dc on Status of Facility Project stage: Other ML20207K5121986-11-13013 November 1986 Fort St Vrain Calculations for Circulator Temp-Related Operating Limits Project stage: Other ML20207K5011986-12-0404 December 1986 Effect of Firewater Cooldown Using Economizer-Evaporator- Superheater (EES) Bundle on Steam Generator Structural Integrity. Draft Rept of Steam Generator Ability to Withstand post-App R Firewater Cooldown Transient Encl Project stage: Draft Other ML20207K4461986-12-12012 December 1986 Issue a to Effect of Firewater Cooldown Using Reheater on Steam Generator Structural Integrity Project stage: Other ML20211N3681986-12-12012 December 1986 Forwards Restart Interaction Schedule,Per 861205 Request Project stage: Other ML20207K5061986-12-22022 December 1986 Issue a to Effect of Intentional Depressurization on Cooldown from 39% Power Using One Reheater Module (1-1/2 H Delay) Project stage: Other ML20207K4411986-12-23023 December 1986 Issue a to Economizer-Evaporator-Superheater (EES) Cooldown from 39% & 78% Power Using Condensate or Firewater (1.5 H Delay) Project stage: Other ML20207K3861986-12-30030 December 1986 Forwards Analyses Supporting Power Operation Up to 39% Power Based on Safe Shutdown Cooling Following 90 Min Interruption of Forced Circulation.Conclusions of Repts Listed.Corrective Actions for LERs 86-020 & 86-026 Also Listed Project stage: Other ML20207P7791987-01-0707 January 1987 Forwards Current Integrated Schedule for Restart & Power Ascension Activities.Schedule Incorporates Consolidated Schedular Info on Both Interaction Activities.Updates Will Be Provided Twice Per Month.W/One Oversize Graph Project stage: Other ML20207P9931987-01-13013 January 1987 SAR for Tech Spec Limiting Condition for Operation 4.3.1 Change Permitting Safe Shutdown Cooling W/Evaporator- Economizer-Superheater Project stage: Other ML20207P9911987-01-15015 January 1987 Proposed Tech Specs,Requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of HXs Project stage: Other ML20207P9891987-01-15015 January 1987 Application for Amend to License DPR-34,requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of Operable HXs Project stage: Request ML20207P9871987-01-15015 January 1987 Forwards Application for Amend to License DPR-34,changing Tech Specs to Require Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power.Fee Paid Project stage: Request ML20211E1101987-01-26026 January 1987 Rev a to Engineering Evaluation of Procedure to Recover from Actuation of Steam Line Rupture Detection/Isolation Sys for Power Levels Through P2 Project stage: Other IR 05000267/19870021987-01-30030 January 1987 Partially Withheld Insp Rept 50-267/87-02 on 870106-09 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Matl Control & Accounting Project stage: Request ML20210A7571987-01-30030 January 1987 Fort St Vrain 1987 Power Ascension Plan Project stage: Other ML20210A7481987-01-30030 January 1987 Requests Concurrence to Start Up & Operate Facility Through Graduated Rise to Power Up to 100% of Rated Power,Subj to Listed Constraints. Fort St Vrain 1987 Power Ascension Plan Encl Project stage: Other ML20210A7401987-02-0202 February 1987 Forwards Updated Nrc/Public Svc Co of Colorado Restart Interaction Schedule, Reflecting Current Target Dates & Recently Completed Items Project stage: Other ML20209G0431987-02-0202 February 1987 Forwards Current Integrated Schedule for Plant Restart & Power Ascension Activities.W/One Oversize Encl Project stage: Other ML20210N8831987-02-0303 February 1987 Forwards Request for Addl Info on 861230 & 870115 Submittals Re Analysis of Firewater Cooldown from 82% of Full Power Project stage: RAI ML20210P0191987-02-0505 February 1987 Summary of 870113 Meeting W/Util Re Completion of Equipment Qualification Program & Program & Approvals Required for Plant Restart Project stage: Meeting ML20210T6861987-02-0505 February 1987 Rev a to Engineering Evaluation of Reanalysis of FSAR Accidents/Transients Relying on EES Cooling. W/Four Oversize Drawings Project stage: Other ML20211D9921987-02-0505 February 1987 Issue a to Economizer-Evaporator-Superheater Cooldowns for Equipment Qualification & App R Events W/Vent Lines (1.5 H Delay) Project stage: Other ML20210T6551987-02-0606 February 1987 Provides Results of Confirmatory Analyses for FSAR Accidents Which Utilize Either EES or Reheater Section of Steam Generator for DHR Project stage: Other ML20210T4361987-02-11011 February 1987 Requests Publication of Fr Notice of Consideration of Issuance of Amend to License DPR-34 & Proposed NSHC Determination & Opportunity for Hearing on 870115 Request Re Operation of evaporator-economizer-superheater Sections Project stage: Other ML20211E9791987-02-12012 February 1987 Forwards Proposed Agenda & Slides for 870226 Meeting W/ Commission & Staff to Secure Commission Approval for Full Power Operation of Facility Project stage: Meeting ML20211D8901987-02-17017 February 1987 Forwards Response to NRC 870203 Request for Addl Info Re Firewater Cooldown from 82% of Full Power,Per Util 861230 & s Project stage: Request ML20207Q7941987-03-0303 March 1987 Forwards Second Request for Addl Info Re Util Analysis of Firewater Cooldown from 82% of Full Power Operation,Based on Review of 861230,870115 & 0217 Submittals Project stage: Approval ML20212M1021987-03-0505 March 1987 Forwards Assessment of Addl Concerns Per 870226 Request Re Restart of Facility.Events & Circumstances Involving Contracts Had No Adverse Impacts Re Plant Safety or Safe Plant Operations Project stage: Other ML20204G9241987-03-20020 March 1987 Forwards Restart & Power Ascension Schedule,Incorporating Consolidated Schedular Info on NRC-util Interaction Activities.Brief Narrative Description of Scope of Each Line Item Activity Also Encl.W/One Oversize Encl Project stage: Other ML20205B3441987-03-20020 March 1987 Forwards Response to NRC 870303 Second Request for Addl Info Re Firewater Cooldown from 82% of Full Power (Safe Shutdown Cooling) Project stage: Request ML20205M8901987-03-30030 March 1987 Forwards Third Request for Addl Info Re Util 861230,870115 & 0217 Submittals Concerning Analysis of Firewater Cooldown from 82% of Full Power.Major Concerns Re Effects of Transient Loading Due to Seismic Motion or Flow Project stage: RAI ML20205T1701987-04-0101 April 1987 Forwards Oversize Current Integrated Schedule for Facility Restart & Power Ascension Activities Required for Equipment Qualification Completion Certification,Startup/Plant Criticality & Power Ascension to 82%.Related Info Encl Project stage: Other ML20206B6031987-04-0101 April 1987 Forwards Comments Re Implication of Chernobyl Reactor Accident.Design Differences Between Fort St Vrain & Chernobyl Preclude Accident Similar to Chernobyl from Occurring at Fort St Vrain Project stage: Approval ML20206B4591987-04-0303 April 1987 Forwards Summary of Equipment Qualification (EQ) Insp Conducted by NRR & IE on 870126-30.EQ Program Approved. Detailed Results of Insp Will Be Provided Project stage: Other ML20206B3291987-04-0707 April 1987 Submits Daily Highlight.Public Svc Co of Colorado Authorized to Restart & Operate Facility HTGR at Level of Up to 35% Full Power.Facility Out of Operation Since 860531,when Shut Down for Equipment Qualification Mods Project stage: Other ML20206F8871987-04-10010 April 1987 Submits Requested Addl Info for Analysis of Firewater Cooldown for 82% Power Operation,Per Project stage: Other ML20209E3291987-04-27027 April 1987 Provides Written Authorization to Operate Reactor at Up to 35% Full Power,Per Section IV of 870406 Confirmatory Order Modifying License DPR-34 Project stage: Other ML20215H9641987-04-30030 April 1987 Forwards Updated Ga Technologies Procedure 909410, Buckle Users Manual, Per 870330 Request.Manual Updated to Include Revs to Computer Code Required by High Temps & Short Times Assumed for Steam Generator Tube Stress Analysis Project stage: Other ML20215H9731987-04-30030 April 1987 Revised Buckle Users Manual:Creep Collapse of Thin-Walled Circular Cylindrical Shells Subj to Radial Pressure & Thermal Gradients Project stage: Other ML20215J8711987-05-0404 May 1987 Rev a to Evaluation of Test Data for Confirmation of Fire Water Flow Rate to Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling Project stage: Other ML20215J8551987-05-0404 May 1987 Forwards Rev a to EE-EQ-0057, Evaluation of Test Data for Confirmation of Fire Water Flow Rate to Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling Project stage: Other 1987-01-07
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20212G5351999-09-27027 September 1999 Forwards Signed Original Confirmatory Order (Effective Immediately)(Morrison Knudsen Corp,Cleveland,Oh) for Transmittal to Ofc of Fr for Publication.Without Encl ML20236W8131998-08-0404 August 1998 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed RM Entitled Miscellaneous Changes to Licensing Requirements for Independent Storage of Spent Nuclear Fuel & HLW Which Amended 10CFR72 ML20202D5011997-11-28028 November 1997 Forwards Table Summarizing Contractor Costs,Staff Hours & FTEs Expended in Removing Sites from Site Decommissioning Mgt Plan & Fsv & Shoreham Nuclear Power Facilities,In Response to C Paperiello 970605 Memorandum ML20141C8691997-05-0505 May 1997 Forwards Notice for Transmittal to Ofc of Fr Re Issuance of License Amend for Psc,Fort St Vrain Nuclear Generating Station Re Redesignated Approved Decommissioning Plan, & Approved Final Radiation Survey Plan ML20136D6041997-03-0404 March 1997 Forwards Signed Original of FRN for Transmittal to Ofc of Federal Register for Publication ML20134G2511996-11-0505 November 1996 Forwards Notice of Forthcoming Meeting W/Psc on Decommissioning & License Termination of Fsv ML20134F8951996-11-0505 November 1996 Notification of 961203 Meeting W/Public Service Co of Co in Rockville,Md to Discuss Decommissioning & License Termination of Fort St Vrain ML20236X0011996-09-12012 September 1996 Provides follow-up to Meeting Re Use of Natural or Depleted U in Storage Casks/Use of Neutron Absorbing Matls,In Order to Improve Basis & Shed Light on Direct Final Possibility ML20137H1331995-12-29029 December 1995 Responds to Request of 951108 for Investigative Assistance in Interviewing R Sawyer & K Zarht Re Alleged Discrimination & Wrongful Termination of Contractor Radiation Protection Technicians at Fort St Vrain,Oi Case A4-95-064 ML20137H2951995-11-21021 November 1995 Forwards Copies of Transcripts of R Sawyer & K Zarht Re Alleged Discrimination & Wrongful Termination of Contractor Radiation Protection Technicians Case A4-95-064.W/o Encls ML20136B2301995-11-17017 November 1995 Forwards Repy to NOV ML20136B1831995-08-31031 August 1995 Discusses Proposed Meeting Re OI 4-95-015 ML20136B1711995-08-31031 August 1995 Agrees W/Office of Enforcement Regional Approach ML20136B2121995-08-30030 August 1995 Confirms 950911 for OI Meeting Re OI 4-95-015 ML20136B1901995-08-30030 August 1995 Ack Receipt of Mail ML20137H2651995-08-25025 August 1995 Forwards Copy of OI Rept Where Investigation Did Substantiate That Seg Technician Deliberately Failed to Perform Response Checks in Accordance W/Procedures.W/O Encl ML20136B1661995-08-17017 August 1995 Forwards OI Rept of Investigation Re Alleged Falsification of Records.W/O Encl ML20136B2191995-08-0707 August 1995 Informs That Enforcement Action Will Be Required Re OI 4-95-015 Concerning Failure to Perform Response Checks ML20136B1581995-06-20020 June 1995 Requests That General Counsel Anlayze Rept & Determine Whether Sufficient Evidence Exists to Take EA Re Falsification of Records ML20137H2551995-06-0303 June 1995 Forwards Copy of OI Rept,Reviewing Licensee Investigation Rept & Confirmed Licensee Conclusions That Radiation Survey Records & Radiation Work Permits Falsified.W/O Encl ML20136B1471995-05-26026 May 1995 Forwards OI Rept of Investigation Re Alleged Falsification of Radiation Survey Records ML20137K0111995-04-20020 April 1995 Discusses Verbal DOJ Declination of Prosecution Re Public Svc Co of Colorado,For Plant ML20137K0781995-04-12012 April 1995 Documents Events Surrounding Segs Placement of Problematic Radiation Protection Technician on Administrative Leave ML20137K0611995-04-12012 April 1995 Documents Events Surrounding Discovery of Barrels Being Shipped from Plant to Richland Disposal Facility W/Different Radiation Exposure Readings than Were Listed on Shipping Manifest NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20137J8251994-04-14014 April 1994 Discusses Chronology of Events Since Preliminary Notification of Event or Unusual Occurrence Case 4-94-010 ML20137S2081994-03-28028 March 1994 Discusses 940325 Telcon from Listed Licensee & Contractor Personnel Re Rept of Falsified Survey Records IA-97-311, Submits Physical Security Info for Export of Unirradiated Fort St Vrain Fuel Containing high-enriched U Mixed W/Th to France for recovery,down-blending & Subsequent Use as Fuel in Research & Test Reactors.Supporting Documentation Encl1993-11-18018 November 1993 Submits Physical Security Info for Export of Unirradiated Fort St Vrain Fuel Containing high-enriched U Mixed W/Th to France for recovery,down-blending & Subsequent Use as Fuel in Research & Test Reactors.Supporting Documentation Encl ML20198H5751993-11-18018 November 1993 Submits Physical Security Info for Export of Unirradiated Fort St Vrain Fuel Containing high-enriched U Mixed W/Th to France for recovery,down-blending & Subsequent Use as Fuel in Research & Test Reactors.Supporting Documentation Encl ML20058B1681993-11-18018 November 1993 Notification of 931109 Meeting W/Psc in Rockville,Md to Discuss Fort St Vrain Decommissioning Status ML20059C2741993-10-25025 October 1993 Notification of Significant Licensee Meeting W/Util on 931116 to Discuss Decommissioning Status of Plant ML20058N9831993-10-0606 October 1993 Notification of 931109 Meeting W/Util in Rockville,Md for Briefing on Status of Plant Decommissioning ML20127D3281993-01-12012 January 1993 Notification of 930128 Meeting W/Util in Rockville,Md to Brief NRC on Plant Decommissioning Status ML20126A3141992-11-27027 November 1992 Forwards Insp Plan for Fsv,Developed for Current Fiscal Yr Ending 930930.Plan Based on Mc 2560,Decommissioning Insp Program ML20127L8411992-11-27027 November 1992 Forwards Insp Plan for Facility Which P Michaud Developed for Current Fy Ending on 930930.Plan Based on Mc 2560, Decommissioning Insp Program ML20059P0831990-10-12012 October 1990 Notification of 901017 Meeting W/Nrc in Rockville,Md to Discuss Decommissioning of Facilities ML20055F7381990-07-16016 July 1990 Notification of 900725 Meeting W/Util in Rockville,Md to Discuss Plant Status & Plans for Final Defueling & Decommissioning ML20248E8301989-09-26026 September 1989 Notification of 891013 Meeting W/Util in Rockville,Md to Discuss Plant Spent Fuel Storage.Agenda Encl ML20247J6831989-09-18018 September 1989 Forwards Comments on Facility Preliminary Decommissioning Plan,Per 890803 & 21 Memos Re Transfer of Regulatory Authority for Reactor Decommissioning ML20246F1871989-08-24024 August 1989 Summary of 890803 Meeting W/Util in Rockville,Md Re Preliminary Decommissioning Plan of 890630 for Plant.Related Info,Including List of Attendees & Util Info Re Use of Tax Deduction in Calculation of Funding Requirements Encl ML20245G5541989-08-0808 August 1989 Requests Support in Conducting Review of Plant Preliminary Decommissioning Plan.Areas to Be Reviewed,Requested Reviewers & Tentative Review Schedule Encl ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247K6271989-07-24024 July 1989 Forwards Revised Filing Instructions for Rev 7 to Updated FSAR ML20246L7971989-07-17017 July 1989 Submits Daily Highlight.Notifies of of 890718 Meeting W/Util in Rockville,Md to Discuss Defueling of Plant & Tech Spec Upgrade Program ML20246L3741989-07-12012 July 1989 Notification of 890803 Meeting W/Util & State of Co in Rockville,Md to Discuss Preliminary Decommissioning Plan ML20247H6041989-05-29029 May 1989 Requests Encl Draft Reg Guide, Assuring Availability of Funds for Decommissioning Nuclear Power Reactors, Task CE 025-4 Be Forwarded to Util for Use in Preparing Preliminary Decommissioning Plan for Plant ML20247D7421989-03-27027 March 1989 Forwards FEMA 890313 Memo Transmitting FEMA Region Viii Update Rept of 870805 Exercise.Rept Includes Results of Remedial Drill Conducted on 880830 & Status of Areas Requiring Corrective Action ML20236B9461989-03-13013 March 1989 Notification of Significant Licensee Meeting W/Util on 890322 in Region IV Ofc to Review OL Requirements ML20155A2481988-09-28028 September 1988 Notification of 881013 & 14 Meetings W/Util in Platteville, Co to Discuss Potential Decommissioning & Conversion of Facility.Meeting Agenda Encl ML20155B4111988-09-27027 September 1988 Notification of Significant Licensee Meeting W/Util on 881003 to Discuss Items in Insp Repts 50-267/88-15 & 50-267/88-23,control of Special Processes,Welding Program & NDE Program 1999-09-27
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20212G5351999-09-27027 September 1999 Forwards Signed Original Confirmatory Order (Effective Immediately)(Morrison Knudsen Corp,Cleveland,Oh) for Transmittal to Ofc of Fr for Publication.Without Encl ML20236W8131998-08-0404 August 1998 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed RM Entitled Miscellaneous Changes to Licensing Requirements for Independent Storage of Spent Nuclear Fuel & HLW Which Amended 10CFR72 ML20202D5011997-11-28028 November 1997 Forwards Table Summarizing Contractor Costs,Staff Hours & FTEs Expended in Removing Sites from Site Decommissioning Mgt Plan & Fsv & Shoreham Nuclear Power Facilities,In Response to C Paperiello 970605 Memorandum ML20149H4801997-07-24024 July 1997 Staff Requirements Memo Re SECY-97-138, Termination of Fort St Vrain Nuclear Generating Station Ol ML20141C8691997-05-0505 May 1997 Forwards Notice for Transmittal to Ofc of Fr Re Issuance of License Amend for Psc,Fort St Vrain Nuclear Generating Station Re Redesignated Approved Decommissioning Plan, & Approved Final Radiation Survey Plan ML20136D6041997-03-0404 March 1997 Forwards Signed Original of FRN for Transmittal to Ofc of Federal Register for Publication ML20134F8951996-11-0505 November 1996 Notification of 961203 Meeting W/Public Service Co of Co in Rockville,Md to Discuss Decommissioning & License Termination of Fort St Vrain ML20134G2511996-11-0505 November 1996 Forwards Notice of Forthcoming Meeting W/Psc on Decommissioning & License Termination of Fsv ML20236X0011996-09-12012 September 1996 Provides follow-up to Meeting Re Use of Natural or Depleted U in Storage Casks/Use of Neutron Absorbing Matls,In Order to Improve Basis & Shed Light on Direct Final Possibility ML20137H1331995-12-29029 December 1995 Responds to Request of 951108 for Investigative Assistance in Interviewing R Sawyer & K Zarht Re Alleged Discrimination & Wrongful Termination of Contractor Radiation Protection Technicians at Fort St Vrain,Oi Case A4-95-064 ML20137H2951995-11-21021 November 1995 Forwards Copies of Transcripts of R Sawyer & K Zarht Re Alleged Discrimination & Wrongful Termination of Contractor Radiation Protection Technicians Case A4-95-064.W/o Encls ML20136B2301995-11-17017 November 1995 Forwards Repy to NOV ML20136B1711995-08-31031 August 1995 Agrees W/Office of Enforcement Regional Approach ML20136B1831995-08-31031 August 1995 Discusses Proposed Meeting Re OI 4-95-015 ML20136B2121995-08-30030 August 1995 Confirms 950911 for OI Meeting Re OI 4-95-015 ML20136B1901995-08-30030 August 1995 Ack Receipt of Mail ML20137H2651995-08-25025 August 1995 Forwards Copy of OI Rept Where Investigation Did Substantiate That Seg Technician Deliberately Failed to Perform Response Checks in Accordance W/Procedures.W/O Encl ML20136B1661995-08-17017 August 1995 Forwards OI Rept of Investigation Re Alleged Falsification of Records.W/O Encl ML20136B2191995-08-0707 August 1995 Informs That Enforcement Action Will Be Required Re OI 4-95-015 Concerning Failure to Perform Response Checks ML20136B1581995-06-20020 June 1995 Requests That General Counsel Anlayze Rept & Determine Whether Sufficient Evidence Exists to Take EA Re Falsification of Records ML20137H2551995-06-0303 June 1995 Forwards Copy of OI Rept,Reviewing Licensee Investigation Rept & Confirmed Licensee Conclusions That Radiation Survey Records & Radiation Work Permits Falsified.W/O Encl ML20136B1471995-05-26026 May 1995 Forwards OI Rept of Investigation Re Alleged Falsification of Radiation Survey Records ML20137K0111995-04-20020 April 1995 Discusses Verbal DOJ Declination of Prosecution Re Public Svc Co of Colorado,For Plant ML20137K0611995-04-12012 April 1995 Documents Events Surrounding Discovery of Barrels Being Shipped from Plant to Richland Disposal Facility W/Different Radiation Exposure Readings than Were Listed on Shipping Manifest ML20137K0781995-04-12012 April 1995 Documents Events Surrounding Segs Placement of Problematic Radiation Protection Technician on Administrative Leave NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20137J8251994-04-14014 April 1994 Discusses Chronology of Events Since Preliminary Notification of Event or Unusual Occurrence Case 4-94-010 ML20137S2081994-03-28028 March 1994 Discusses 940325 Telcon from Listed Licensee & Contractor Personnel Re Rept of Falsified Survey Records ML20059G9501994-01-19019 January 1994 Staff Requirements Memo Re SECY-93-352,Proposed Export of Fort St Vrain Unirradiated HEU Fuel Assemblies to France for Recovery & Down-Blending to LEU XSNM-2748, & SECY-93-333, Final Amend to 10CFR55 on Renewal of Licenses.. ML20198H5751993-11-18018 November 1993 Submits Physical Security Info for Export of Unirradiated Fort St Vrain Fuel Containing high-enriched U Mixed W/Th to France for recovery,down-blending & Subsequent Use as Fuel in Research & Test Reactors.Supporting Documentation Encl IA-97-311, Submits Physical Security Info for Export of Unirradiated Fort St Vrain Fuel Containing high-enriched U Mixed W/Th to France for recovery,down-blending & Subsequent Use as Fuel in Research & Test Reactors.Supporting Documentation Encl1993-11-18018 November 1993 Submits Physical Security Info for Export of Unirradiated Fort St Vrain Fuel Containing high-enriched U Mixed W/Th to France for recovery,down-blending & Subsequent Use as Fuel in Research & Test Reactors.Supporting Documentation Encl ML20058B1681993-11-18018 November 1993 Notification of 931109 Meeting W/Psc in Rockville,Md to Discuss Fort St Vrain Decommissioning Status ML20059C2741993-10-25025 October 1993 Notification of Significant Licensee Meeting W/Util on 931116 to Discuss Decommissioning Status of Plant ML20058N9831993-10-0606 October 1993 Notification of 931109 Meeting W/Util in Rockville,Md for Briefing on Status of Plant Decommissioning ML20127D3281993-01-12012 January 1993 Notification of 930128 Meeting W/Util in Rockville,Md to Brief NRC on Plant Decommissioning Status ML20127L8411992-11-27027 November 1992 Forwards Insp Plan for Facility Which P Michaud Developed for Current Fy Ending on 930930.Plan Based on Mc 2560, Decommissioning Insp Program ML20126A3141992-11-27027 November 1992 Forwards Insp Plan for Fsv,Developed for Current Fiscal Yr Ending 930930.Plan Based on Mc 2560,Decommissioning Insp Program ML20059P0831990-10-12012 October 1990 Notification of 901017 Meeting W/Nrc in Rockville,Md to Discuss Decommissioning of Facilities ML20055F7381990-07-16016 July 1990 Notification of 900725 Meeting W/Util in Rockville,Md to Discuss Plant Status & Plans for Final Defueling & Decommissioning ML20248E8301989-09-26026 September 1989 Notification of 891013 Meeting W/Util in Rockville,Md to Discuss Plant Spent Fuel Storage.Agenda Encl ML20247J6831989-09-18018 September 1989 Forwards Comments on Facility Preliminary Decommissioning Plan,Per 890803 & 21 Memos Re Transfer of Regulatory Authority for Reactor Decommissioning ML20246F1871989-08-24024 August 1989 Summary of 890803 Meeting W/Util in Rockville,Md Re Preliminary Decommissioning Plan of 890630 for Plant.Related Info,Including List of Attendees & Util Info Re Use of Tax Deduction in Calculation of Funding Requirements Encl ML20245G5541989-08-0808 August 1989 Requests Support in Conducting Review of Plant Preliminary Decommissioning Plan.Areas to Be Reviewed,Requested Reviewers & Tentative Review Schedule Encl ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247K6271989-07-24024 July 1989 Forwards Revised Filing Instructions for Rev 7 to Updated FSAR ML20246L7971989-07-17017 July 1989 Submits Daily Highlight.Notifies of of 890718 Meeting W/Util in Rockville,Md to Discuss Defueling of Plant & Tech Spec Upgrade Program ML20246L3741989-07-12012 July 1989 Notification of 890803 Meeting W/Util & State of Co in Rockville,Md to Discuss Preliminary Decommissioning Plan ML20247H6041989-05-29029 May 1989 Requests Encl Draft Reg Guide, Assuring Availability of Funds for Decommissioning Nuclear Power Reactors, Task CE 025-4 Be Forwarded to Util for Use in Preparing Preliminary Decommissioning Plan for Plant ML20247D7421989-03-27027 March 1989 Forwards FEMA 890313 Memo Transmitting FEMA Region Viii Update Rept of 870805 Exercise.Rept Includes Results of Remedial Drill Conducted on 880830 & Status of Areas Requiring Corrective Action ML20236B9461989-03-13013 March 1989 Notification of Significant Licensee Meeting W/Util on 890322 in Region IV Ofc to Review OL Requirements 1999-09-27
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April 7, 1987 Docket No. 50-267 MEMORANDUM FOR: H. Denton R. W. Houston J. Sniezek D. Crutchfield J. Lyons E. Rossi F. Miraglia .G. Lainas R. Bernero T. Speis G. Holahan W. Russell T. Novak F. Schroeder THRU: Herbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B FROM: Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B
SUBJECT:
DAILY HIGHLIGHT - FORT ST. VRAIN RESTART ORDER ISSUED By confirmatory order, the Public Service Company of Colorado has been
! authorized to restart and operate the Fort St. Vrain HTGR at a level up to 35%
i
! of full power. The facility has been out of operation since May 31, 1986, when it was shut down for equipment qualification modifications. Current reactor i core conditions will allow for a short " dry out" period. After startup, the licensee will " hold" at 10% of full power to allow the Region IV staff to evaluate the facility's performance. Upon Region IV's approval, the plant may operate up to 35% of full power. Pending completion of additional licensing actions, the plant will be authorized to operate at 82% of full power.
Nd8dE8LI $iaMinIF, pr83eh"Maa$P ' "
, Standardization and Special Projects Directorate Division of PWR Licensing-B
, DISTRIBUTION:
iD5ctet F.ne 1 PNoonan Local PDR PBSS Reading NRC PDR KHeitner Olynch HBerkow 2 PBS v' PhS, / PBSS P oonan XHe'{tner:cw Olynch HB 04/ / /87 p04/d/87 04Td/87 04/ '/87
., G)704090079 B70407 4
PDR ADOCK 05000267 P PDR
+ jog UNITED STATES
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-l NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 70555 j k.....,/ April 7, 1987 Docket No. 50 267 i
MEMORANDUM FOR: H. Denton R. W. Houston J. Sniezek D. Crutchfield, i
J. Lyons E. Rossi l F. Miraglia G. Lainas *
, R. Bernero T. Speis j G. Holahan W. Russell T. Novak
- F. Schroeder I THRU
- Herbert N. Berkow, Director V
'l Standardization and'Special r Projects Directorate 1
Division of PWR Licensing-B -
FROM: Kenneth L. Heitner, Project Manager i Standardization and Special Projects Directorate .
.i Division of PWR Licensing;B
SUBJECT:
DAILY HIGHLIGHT - FORT ST. VRAIN RESTART ORDER ISSUED By confirmatory order, the Public Service Company of Colorado has been i
authorized to restart and operate the Fort St. V, rain HTGR at a level up to 35%'
] of full power. The facility has been out of operatio'n since May 31, 1986, when
- it was shut down for equipment qualification modifications. Current reacto.r .'
core conditions will allow for a short " dry out" period. After startup, the lq licensee will " hold" at 10% of full power to allow the Region IV staff to l evaluate the facility's performance. Upon Region IV's approval, the plant may l'
operate up to 35% of full power. Pending completion of additional licensing actions, the plant will be authorized to operate at 82% of full power.
M& s/
l hKennethLLHeitner,ProjectManager '
j Standardization and Special -
- Projects Directorate
{ Ulvision of PWR Licensing-B .
i i
i
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