Letter Sequence Approval |
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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: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:NRC TO UTILITY
MONTHYEARML20058J0121990-11-16016 November 1990 Forwards Insp Rept 50-267/90-20 on 901029-1102.Violations Noted But Not Cited IR 05000267/19900161990-10-30030 October 1990 Discusses Insp Rept 50-267/90-16 on 900928 & 901018 Enforcement Conference & Forwards Notice of Violation ML20062B3971990-10-15015 October 1990 Forwards Insp Rept 50-267/90-14 on 900801-0930.No Violations or Deviations Noted ML20058A0941990-10-12012 October 1990 Confirms 901018 Enforcement Conference in Region IV Ofc Re Violations & Radiation Program Weakness Noted in Insp Rept 50-267/90-16.Proposed Agenda Encl ML20059N8231990-10-0303 October 1990 Forwards FEMA Final Radiological Emergency Preparedness Exercise Rept, for 891115 Exercise.One Deficiency & Several Areas Requiring Corrective Actions Identified ML20059C1381990-08-24024 August 1990 Forwards Notice of Consideration of Issuance of Amend to License DPR-34 & Opportunity for Hearing Re 900605 Application,For Info ML20056B4021990-08-20020 August 1990 Forwards Insp Rept 50-267/90-11 on 900601-0728.No Violations or Deviations Noted ML20058M8681990-08-0808 August 1990 Forwards Insp Rept 50-267/90-13 on 900709-13.No Violations or Deviations Identified.Licensee Commitment to Revise Manual Dose Assessment Procedure to Incorporate Appropriate Unit Conversion Factor,Noted ML20056A3601990-07-31031 July 1990 Forwards Insp Rept 50-267/90-10 on 900611-15.No Violations or Deviations Noted.Actions Taken Re Previously Identified Insp Findings & Status Examined ML20055J3951990-07-31031 July 1990 Ack Receipt of 900713 Request for Exemption from FY90 Annual Fee Requirements of 10CFR171.Annual Fee Will Not Be Billed ML20059D1281990-07-30030 July 1990 Ack Receipt of 900713 Request for Full Exemption from FY90 Annual Fee Requirements of 10CFR171 for Plant.Annual Fee Will Not Be Billed While Request Under Review ML20055G5921990-07-19019 July 1990 Agrees W/Removal of B Helium Circulator,Per Requesting NRC Concurrence.Solution to Correct Leakage Problem by Removal of Circulator Acceptable ML20055D2031990-06-26026 June 1990 Ack Receipt of 900525 Response to 900402 Emergency Preparedness Insp Rept & 900427 Notice of Violation ML20055C8021990-06-18018 June 1990 Concludes That Financial Info Forwarded by Meets Requirements of 10CFR140.21 ML20248H7751989-10-0303 October 1989 Forwards Insp Rept 50-267/89-19 on 890821-26 & 29-30.No Violations or Deviations Noted IR 05000267/19890081989-10-0202 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-08. Understands That Revised Flow Test Surveillance Procedures Performed on 890821 & 0921 & cross-connect Valves Stroked IR 05000267/19890171989-10-0202 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-17. Implementation of Corrective Actions Will Be Examined During Future Insps ML20248B2971989-09-26026 September 1989 Forwards Insp Rept 50-267/89-16 on 890716-0831 & Notice of Violation IR 05000267/19890121989-09-22022 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-267/89-12 ML20247L1381989-09-19019 September 1989 Advises That Request to Delete Requirement to Provide Status Repts on Performance Enhancement Program Approved.Updated List of Commitments Encl ML20247K4141989-09-15015 September 1989 Advises That Tech Specs Re Upgrade Program,Requested in NRC ,Must Be Approved by NRC Before Defueling ML20247K7741989-09-15015 September 1989 Informs That Partial Review of 890125 & 0320 Submittals Re Helium Circulators complete.Ten-yr Insp Recently Conducted on Circulator C-2105.Insp Revealed No Defects or Unacceptable Conditions ML20247D4691989-09-11011 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-15 ML20247H3431989-09-0808 September 1989 Ack Receipt of Informing NRC of Status of Security Sys Upgrades ML20247H2891989-09-0606 September 1989 Concurs W/Util 890714 Request for Changes to Basis for Limiting Condition for Operation 4.2.2 of Facility Tech Specs Re Statement About Automatic Initiation of Backup Bearing Water Sys ML20247B2661989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executives Meeting on 890818 in Arlington,Tx.Topics Discussed Included, Improving Communications,Salp Process in Region IV & Enforcement.List of Attendees & Agenda Encl ML20246J2911989-08-30030 August 1989 Forwards Amend 72 to License DPR-34 & Safety Evaluation. Amend Imposes Early Shutdown by Limiting Reactor Power to 2% of Full Power After 900630 ML20246E5941989-08-21021 August 1989 Forwards Insp Rept 50-267/89-14 on 890710-14 & Notice of Violation.Two Separate Findings of Missing Info in Semiannual Effluent Rept,Resulting in Failure to Satisfy Tech Spec Administrative Requirements Identified ML20246A2651989-08-16016 August 1989 Forwards Insp Rept 50-267/89-13 on 890626-30.Violations Noted But No Citation Issued.Expresses Concern About Status of Model FSV-1 & FSV-1A Shipping Casks ML20245J3511989-08-14014 August 1989 Forwards Amend 71 to License DPR-34 & Safety Evaluation. Amend Revises Provisions in Tech Specs Re Radiological Effluents ML20246A6841989-08-14014 August 1989 Forwards Exam Rept 50-267/OL 89-02 Administered During Wk of 890710 ML20245J5651989-08-10010 August 1989 Forwards Insp Rept 50-267/89-17 on 890717-21 & Notice of Violation ML20245J4421989-08-0808 August 1989 Forwards Safety Evaluation,Responding to Issues Re Tech Spec Upgrade Program & Defueling of Plant.Requests That Tech Spec Changes Be Requested within 30 Days of Ltr Date ML20245H3891989-08-0808 August 1989 Forwards Insp Rept 50-267/89-12 on 890601-0715 & Notice of Violation ML20248E0041989-08-0303 August 1989 Forwards Team Insp Rept 50-267/89-08 on 890522-26 & Notice of Violation.Response Should Include Corrective Actions Taken or Planned to Ensure That Reactor Water Cooling Sys 46 Operated as Designed IR 05000267/19890071989-07-28028 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-07 ML20247N7581989-07-26026 July 1989 Discusses Licensee 890616 Request Re Changes to Previous Commitments Concerning Plans to Shut Down Plant.Commitment 2c to Be Subj of Separate Correspondence.Commitment 7 to Be Considered Not Applicable.W/Revised Summary of Commitments ML20247M4521989-07-25025 July 1989 Forwards Request for Addl Info Re Reactor Defueling.Info Needed within 30 Days of Ltr Date ML20247M4281989-07-25025 July 1989 Responds to 890120 & 0616 Requests for Relief from Requirements of Fuel Surveillance Program.Nrc Considers Util Obligations Under Fuel Surveillance Program Will Terminate W/Planned Shutdown of Reactor by 900630 ML20247L9801989-07-14014 July 1989 Discusses 890711 Meeting in Region IV Ofc Re Introduction of AC Crawford & Future Plans for Facility.Slides Presented at Meeting & List of Attendees Encl ML20247L5971989-07-14014 July 1989 Forwards Insp Rept 50-267/89-15 on 890623-27 & Notice of Violation.Response Should Describe Corrective Actions to Assure That safety-related Changes Introduced by Other Parts of Organization Are Properly Incorporated Into Procedures ML20246M6941989-07-11011 July 1989 Forwards Agenda for 890808 Meeting of Senior Util Executives Sponsored by Region IV at Univ of Texas.Map to Facilitate Access to Meeting Room Also Encl ML20246F4851989-07-10010 July 1989 Discusses Util Re Alternative Compensatory Measures Instituted,Per Fire Protection Operability Requirement-16.Proposed Guidance Adequate ML20246J2791989-07-0707 July 1989 Forwards Safety Evaluation Concluding That Operators Role in Mitigating High Energy Line Break at Facility Acceptable. Technical Evaluation Rept Also Encl ML20245G4491989-06-22022 June 1989 Forwards Exam Rept 50-267/OL-89-01 Administered During Wk of 890523 ML20245G4831989-06-20020 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-06 ML20245F8161989-06-20020 June 1989 Proposes Meeting in Region IV to Discuss SALP Process in Region Iv,Improving Communication W/Licensee Mgt,Region IV Enforcement Philosophy,How to Improve Safety Performance & Topics Util Wishes to Discuss ML20245A2201989-06-15015 June 1989 Forwards Insp Rept 50-267/89-10 on 890501-31.No Violations or Deviations Noted ML20244C1221989-06-0808 June 1989 Forwards Insp Rept 50-267/89-07 on 890319-0430 & Notice of Violation ML20248B8741989-06-0505 June 1989 Forwards Draft Reg Guide, Assuring Availability of Funds for Decommissioning Nuclear Reactors, Task CE 025-4,for Use in Preparing Preliminary Decommissioning Plan for Plant 1990-08-08
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20236R9191998-07-20020 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 ML20198H5601997-09-16016 September 1997 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety 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 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 ML20137S1691997-04-0707 April 1997 Fifth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App K ML20137S0821997-04-0707 April 1997 Forwards Insp Rept 50-267/97-01 on 970310-11.No Violations Noted 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) 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) 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) 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 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 ML20132G0421996-12-23023 December 1996 Forwards Insp Rept 50-267/96-05 on 961203-05.No Violations Noted 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) ML20128G1421996-09-25025 September 1996 Advises NRC Approved Decommissioning Plan, Impact Of... Fsv Final Decommissioning, Satisfies All Elements of License Termination Plan as Required by Rev to Reactor Decommissioning Rule 10CFR50.82(a)(9) ML20136B2561996-04-0202 April 1996 Informs That NOV Issued on 951030 Revised to Reflect NRC Reanalysis of Info Re Falsification of Radiation Survey Records.Revised NOV Encl ML20136B2731996-04-0202 April 1996 Informs That NOV Issued on 951030 Revised to Reflect NRC Reanalysis of Info Re Util Failure to Assure Compliance w/10CFR50.9 Concerning Accuracy of Radiation Survey Records. Revised NOV Encl ML20136B3241996-04-0202 April 1996 Informs That NRC Will Be Withdrawing NOV ,based on Reevaluation of Evidence Provided & Response to NOV ML20058G9671993-12-0707 December 1993 Ack Receipt of Ltrs of 931110,responding to Notice of Violation & Proposed Imposition of Civil Penalty Issued on 931013 IR 05000267/19930021993-09-0303 September 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Deviations Noted in Insp Rept 50-267/93-02. Deficiency Determined to Have Contributed to 930527 Crane Overload Event IR 05000267/19930011993-09-0303 September 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/93-01 ML20056G0041993-06-25025 June 1993 Submits Info Re Implementation of Training Rule 10CFR50.120 for Licensees of Plant in Decommissioning Process ML20128D6931992-12-0101 December 1992 Forwards Exemption from Requirement in 10CFR50,app E,Section IV.F.2 to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise. EA & SE Also Encl ML20198C7511991-06-25025 June 1991 Suggests That Region Iv/Senior Util Executive Conference Be Held During Month of Sept 1991 in Arlington,Tx to Provide Open Forum for Candid Discussions Limited to Topics of General Interest & Not Pertain to Plant Specific Issues ML20058K0231990-11-30030 November 1990 Forwards Insp Rept 50-267/90-17 on 901001-1109.No Violations or Deviations Noted ML20062H8131990-11-29029 November 1990 Forwards Partially Withheld Insp Rept 50-267/90-18 on 901022-26 & Notice of Violation ML20062H2041990-11-21021 November 1990 Forwards Insp Rept 50-267/90-19 on 901015-19.No Violations or Deviations Noted ML20058J0121990-11-16016 November 1990 Forwards Insp Rept 50-267/90-20 on 901029-1102.Violations Noted But Not Cited IR 05000267/19900161990-10-30030 October 1990 Discusses Insp Rept 50-267/90-16 on 900928 & 901018 Enforcement Conference & Forwards Notice of Violation ML20062B3971990-10-15015 October 1990 Forwards Insp Rept 50-267/90-14 on 900801-0930.No Violations or Deviations Noted ML20058A0941990-10-12012 October 1990 Confirms 901018 Enforcement Conference in Region IV Ofc Re Violations & Radiation Program Weakness Noted in Insp Rept 50-267/90-16.Proposed Agenda Encl ML20059N8231990-10-0303 October 1990 Forwards FEMA Final Radiological Emergency Preparedness Exercise Rept, for 891115 Exercise.One Deficiency & Several Areas Requiring Corrective Actions Identified ML20059C1381990-08-24024 August 1990 Forwards Notice of Consideration of Issuance of Amend to License DPR-34 & Opportunity for Hearing Re 900605 Application,For Info ML20056B4021990-08-20020 August 1990 Forwards Insp Rept 50-267/90-11 on 900601-0728.No Violations or Deviations Noted ML20058M8681990-08-0808 August 1990 Forwards Insp Rept 50-267/90-13 on 900709-13.No Violations or Deviations Identified.Licensee Commitment to Revise Manual Dose Assessment Procedure to Incorporate Appropriate Unit Conversion Factor,Noted ML20055J3951990-07-31031 July 1990 Ack Receipt of 900713 Request for Exemption from FY90 Annual Fee Requirements of 10CFR171.Annual Fee Will Not Be Billed ML20056A3601990-07-31031 July 1990 Forwards Insp Rept 50-267/90-10 on 900611-15.No Violations or Deviations Noted.Actions Taken Re Previously Identified Insp Findings & Status Examined ML20059D1281990-07-30030 July 1990 Ack Receipt of 900713 Request for Full Exemption from FY90 Annual Fee Requirements of 10CFR171 for Plant.Annual Fee Will Not Be Billed While Request Under Review ML20055G5921990-07-19019 July 1990 Agrees W/Removal of B Helium Circulator,Per Requesting NRC Concurrence.Solution to Correct Leakage Problem by Removal of Circulator Acceptable ML20055D2031990-06-26026 June 1990 Ack Receipt of 900525 Response to 900402 Emergency Preparedness Insp Rept & 900427 Notice of Violation ML20055C8021990-06-18018 June 1990 Concludes That Financial Info Forwarded by Meets Requirements of 10CFR140.21 ML20248H7751989-10-0303 October 1989 Forwards Insp Rept 50-267/89-19 on 890821-26 & 29-30.No Violations or Deviations Noted IR 05000267/19890171989-10-0202 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-17. Implementation of Corrective Actions Will Be Examined During Future Insps IR 05000267/19890081989-10-0202 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-08. Understands That Revised Flow Test Surveillance Procedures Performed on 890821 & 0921 & cross-connect Valves Stroked ML20248B2971989-09-26026 September 1989 Forwards Insp Rept 50-267/89-16 on 890716-0831 & Notice of Violation IR 05000267/19890121989-09-22022 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-267/89-12 ML20247K9051989-09-19019 September 1989 Advises That 890726 Request for Approval of Route to Transport Spent Reactor Fuel Approved.Route,From Facility to DOE Inel in Idaho,Encl ML20247L1381989-09-19019 September 1989 Advises That Request to Delete Requirement to Provide Status Repts on Performance Enhancement Program Approved.Updated List of Commitments Encl 1998-07-20
[Table view] |
Text
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March 3, 1987 Docket No. 50-267 Mr. R. O. Williams, Jr.
Vice President, Nuclear Operations Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201-0840
Dear Mr. Williams:
SUBJECT:
ANALYSIS OF FIREWATER C00LDOWN FROM 82% POWER OPERATION -
SECOND REQUEST FOR ADDITIONAL INFORMATION We are reviewing your submittals dated December 30, 1986, January 15,and February 17,1987 (P-86683, P-87002 and P-87055) concerning your analysis of a firewater cooldown from 82% of full power. In order to complete this review, we are making a second request that you provide certain additional information. Our request for this information is enclosed.
The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Original signed by Kenneth L. Heitner, Project Manager
, Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See.next page DISTRIBUTION:
tDectet file -
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(* n NUCLEAR REGULATORY COMMISSION f ,E WASHINGTON, D. C. 20555
- " March 3, 1987 Docket No. 50-267 Mr. R. O. Williams, Jr.
Vice President, Nuclear Operations Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201-0840
Dear Mr. Williams:
SUBJECT:
ANALYSIS OF FIREWATER C00LDOWN FROM 82% POWER OPERATION -
SECOND REQUEST FOR ADDITIONAL INFORMATION We are reviewing your submittals -dated December 30, 1986, January 15,and February 17, 1987 (P-86683, P-87002 and P-87055) concerning your analysis of a firewater cooldown from 82% of full power. In order to complete this review, we are making a second request that you provide certain additional information. Our request for this information is enclosed.
The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, w~ h.'
Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page
p t
( Mr. R. O. Williams Public Service Company of Colorado Fort St. Vrain cc:
Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nuclear Engineering Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Cenver, Colorado 80220 Denver, Colorado 80701 Mr. David Alberstein, 14/159A Mr. J. W. Gahm, Manager GA Technologies, Inc. Nuclear Production Division Post Office Bcx 25608 Public Service Company of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Mr. P. F. Tomlinson, Manager Public Service Company of Colorado Quality Assurance Division P. O. Box 840 Public Service Company of Colorado Denver, Colorado 80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission Mr. R. F. Walker P. 0. Box 840 Public Service Company of Colorado Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 80201-0840 Kelley, Stansfield & 0'Donnell Public Service Company Building Commitment Control Progran Room 900 Coordinator 550 15th Street Public Service Company of Colorade Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-0 Denver, Colorado 80211 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite '1000 Arlingtcn, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Padiation Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 Denver, Colorado 80202-2413
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-w .,;
'i
Enclosure-Recuest 'for Additional Irformation Concerning Safe Shutdown Cooling Fort St. Vrain Docket flo. 50-267
- 1. What is the status of the hot and cold reheat header isolation valves during a firewater cooldown?
- 2. Are the valves either closed or operable for automatic closure should a leak develop'in the reheater tubes?
- 3. Are there initiating events for which this system is not qualified, or does not meet regulatory requirements, such as an earthquake or single fire?
A. What safety benefits would come from closing the valves before restoring helium circulation?
- 5. What safety benefits would come from being able to pressurize the reheater with dry gas before restoring helium circulation?
- 6. Page 14 of Attachment I to P-87055 refers to the results of special testing of si:nulated firewater supply to the steam generators and circulator Pelton drives. The text of Unusual Event Report 76/05A indicates that Test T-30 yielded only 540 gpm supply to the steam generator. What was the circulator speed achieved during this test?
What were the steam generator supply flow and circulator speed during Test T-30A7 Test RT-403 achieved circulator speeds in excess of 700 RPM on each circulator. What was the steam generator supply flow during RT-403? What circulator speeds and concurrent steam generator flow rates were obtained during any testing after installation of the emergency water booster pumps? What were the simulated firewater supply pressure (booster pump suction), steam generator back pressure, and Pelton wheel supply pressure during each of these tests for which data are provided?
- 7. SR 5.2.7.? is indicated to be performed with 115 psig suction pressure at the emergency booster pump from throttled condensate. Provide the results of SR 5.2.7.? in terms of booster pump suction pressure, booster pump differential pressure, circulator speed, simulated firewater flow rates from the booster pump and to the Pelton wheel, and primary system flow at rated helium inventory. Has SR 5.2.7.?
been performed in conjunction with simulated firewater flow to the steam generator? If so, provide the above results plus the steam generator flow and back pressure measurerents.