ML20214Q998
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Letter Sequence Other | |
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TAC:63576, (Approved, Closed) | |
Results Other: 05000267/LER-1986-020, :on 860711,determined That FSAR Analyses for Safe Shutdown Cooling Following 90-minute Loss of Forced Cooling May Be Invalid.Caused by Design Omission.Three Options Presently Being Investigated, 05000267/LER-1986-026, :on 860917,FSAR Analysis for Safe Shutdown Cooling W/Firewater Invalid.Caused by Incomplete Analysis/ Inadequate Review.Review & Reanalysis Will Be Performed on Various Accidents Described in FSAR, ML19306G340, 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, ML20214Q988, ML20214Q998, ML20214S836, ML20215H964, ML20215H973, ML20215J855, ML20215J871, ML20234C109, ML20235E520, ML20235F508, ML20245C018 | |
MONTHYEARML20137H3721985-11-26026 November 1985
[Table View]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 05000267/LER-1986-020, :on 860711,determined That FSAR Analyses for Safe Shutdown Cooling Following 90-minute Loss of Forced Cooling May Be Invalid.Caused by Design Omission.Three Options Presently Being Investigated1986-08-10010 August 1986
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 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 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 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 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 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 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 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 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 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 ML20214S8361987-05-27027 May 1987 Requests Insp & Audit Per 10CFR50,App B of Licensee Activities Supporting Request for 82% Power Operation. Requests That Insp Be Conducted & Completed within 180 Days Project stage: Other ML20214Q9881987-05-29029 May 1987 Forwards Rept GA909438,Issue Nc, Verification Rept for Buckle Computer Program. Edition of Buckle Code Covered by User Manual Validated & Independently Verified by Rept Project stage: Other 1987-02-11 |
| ML20214Q998 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 05/31/1987 |
| From: | Almajan I GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | |
| Shared Package | |
| ML20214Q991 | List: |
| References | |
| 909438, TAC-63576, NUDOCS 8706050290 | |
| Download: ML20214Q998 (674) | |
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