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
[Table View] |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20140E1121997-04-10010 April 1997 Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20134D1661997-01-30030 January 1997 Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) ML20137S6111996-12-31031 December 1996 Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G6861996-10-29029 October 1996 Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G ML20134G7271996-10-29029 October 1996 Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results ML20134G6321996-10-26026 October 1996 Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D ML20133D7831996-10-22022 October 1996 Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 ML20116A4661996-07-19019 July 1996 Fsv Final Survey Exposure Rate Measurements ML20112C1531996-05-17017 May 1996 Fsv Final Survey Exposure Rate Measurements ML20101G5521996-03-21021 March 1996 Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept ML20095K9751995-12-15015 December 1995 Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 ML20137H3531994-12-31031 December 1994 Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses ML20137S2331994-12-31031 December 1994 Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 ML20085H6611991-10-10010 October 1991 Assessment of Mgt Modes for Graphite from Reactor Decommissioning ML20091D7671991-10-0101 October 1991 Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change ML20077P9291991-08-15015 August 1991 Final Rept, Verification of Fort St Vrain Activation Analysis ML20072V5031991-04-12012 April 1991 Summary of Existing & Planned Work for Activation Verification,910415 ML20029B6731991-03-0505 March 1991 Nonproprietary Estimated Blast Effect from Ft St Vrain Well 11 Analysis Methods Summary. ML20059L5921990-09-13013 September 1990 Determination of Upper Bounds on Radiation Exposure Rates at Refueling Floor Above Defueled Region W/Crd Orifice Assemblies Radiation Shielding Removed ML20042F9071990-05-0101 May 1990 Conceptual Plan & Cost Estimate for Early Dismantlement of Fort St Vrain Pcrv. ML19332E8181989-12-0101 December 1989 Rev a to Fort St Vrain Site-Specific Decommissioning Cost Estimate Basis for Preliminary Decommissioning Plan. ML19332C2831989-10-0909 October 1989 Fort St Vrain 3-D Neutron Source Analysis Using DIF3D. ML19332E8191989-08-31031 August 1989 Rev a to Fort St Vrain Activation Analysis. ML20245L4061989-08-31031 August 1989 Safety Analysis Rept for Reactor Defueling ML20246K1321989-07-31031 July 1989 Pcrv Tendon Surveillance Rept for Jul 1989.W/four Oversize Drawings ML20245J3261989-06-14014 June 1989 Rev B to Evaluation of Cable/Equipment Separation for Bearing Water Pumps P-2101-S,P-2102 (Train B),P-2102-S (Train B) & P-2107 (Train B) for App R Requirements ML20245C4581989-05-11011 May 1989 CRD Partial Scram Test Results & Max Daily Temp Rept, 890511-0531 ML19332E8211989-02-23023 February 1989 Fort St Vrain Plateout Analysis for Decommissioning Study. ML20206K1111988-11-21021 November 1988 Rev a to Engineering Evaluation of Interaction & Effects of Plant Protection Sys & Steam Line Rupture Detection/ Isolation Sys ML20154E0981988-08-31031 August 1988 Pcrv Tendon Interim Surveillance Rept. W/Four Oversize Drawings ML20077B9091988-05-31031 May 1988 Vols I & II of Activation Analysis ML20154A5451988-04-28028 April 1988 Integrated Sys Study of CRD Mechanism Rod Position Instrumentation ML20154A5501988-04-28028 April 1988 Temp Prediction for CRD Mechanism Motors ML20235A5591988-01-31031 January 1988 Pcrv Tendon Interim Surveillance Rept. W/Four Oversize Drawings ML20148G7941988-01-22022 January 1988 Rept of Helium Circulator S/N C-2101 & Inlet Piping S/N 2001 Repair & Mod Activities ML20148G8511988-01-22022 January 1988 Helium Circulator Insp Schedule ML20195H8731988-01-14014 January 1988 Final Rept on Fort St Vrain 871002-03 Fire ML20236J2911987-10-30030 October 1987 Preliminary Rept on Impact of Fort St Vrain 871002 Fire ML20235H4731987-09-11011 September 1987 Preliminary Rept of Helium Circulator S/N C-2101 Damage & Justification for Returning to Power Operation ML20235K2721987-09-11011 September 1987 Preliminary Rept of Helium Circulator S/N C-2101 Damage Including Licensing Assessment ML20195G9681987-08-11011 August 1987 Analyses Re Fort St Vrain DBA-2 Core Damage Frequency ML20235W6091987-07-31031 July 1987 Pcrv Tendon Interim Surveillance Rept ML20234C1091987-06-25025 June 1987 Issue B to Effect of Firewater Cooldown Using EES Bundle on Steam Generator Structural Integrity ML20214Q9981987-05-31031 May 1987 Verification Rept for Buckle Computer Program 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 ML20214P3381987-04-30030 April 1987 Rev 3 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 4, Exemptions & Mods ML20214P3141987-04-30030 April 1987 Rev 5 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 2, Electrical Reviews ML20214P3061987-04-30030 April 1987 Rev 7 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 1, Shutdown Model 1997-04-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20196G6731997-07-0101 July 1997 Informs Commission That Decommissioning Process Has Been Completed at PSC of Colorado Fsvngs,Unit 1 Located in Town of Platteville in Weld County,Co ML20141K9961997-05-0505 May 1997 Safety Evaluation Supporting Amend 89 to License DPR-34 ML20140E1121997-04-10010 April 1997 Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20134D1661997-01-30030 January 1997 Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) ML20137S6111996-12-31031 December 1996 Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results ML20134G7271996-10-29029 October 1996 Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J ML20134G6861996-10-29029 October 1996 Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G ML20134G6321996-10-26026 October 1996 Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D ML20133D7831996-10-22022 October 1996 Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 ML20116A4661996-07-19019 July 1996 Fsv Final Survey Exposure Rate Measurements ML20112J6861996-05-31031 May 1996 June 1996 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning.Rept Covers Period of 960216-0531 ML20112C1531996-05-17017 May 1996 Fsv Final Survey Exposure Rate Measurements ML20101G5521996-03-21021 March 1996 Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept ML20097E3201996-01-31031 January 1996 Nonproprietary Fort St Vrain Technical Basis Documents for Piping Survey Instrumentation ML20095K4131995-12-26026 December 1995 Rev 3 to Decommissioning Plan ML20095H7211995-12-20020 December 1995 Revs to Fort St Vrain Decommissioning Fire Protection Plan Update ML20095K9751995-12-15015 December 1995 Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 ML20096C1671995-12-13013 December 1995 Rev 4 to Decommissioning Fire Protection Plan ML20094M1651995-11-30030 November 1995 Nonproprietary Fsv Technical Basis Documents for Piping Survey Implementation ML20092F3461995-09-14014 September 1995 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning, Covering Period of 950516-0815.W/ ML20137H3531994-12-31031 December 1994 Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses ML20137S2331994-12-31031 December 1994 Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 ML20029C6031993-12-31031 December 1993 1993 Annual Rept Public Svc Co of Colorado. W/940405 Ltr ML20058Q3791993-12-21021 December 1993 Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20045B3641993-06-30030 June 1993 June 1993 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning. ML20045A4291993-06-0303 June 1993 LER 93-003-00:on 930505,new Source of Natural Gas Introduced within 0.5 Miles of ISFSI & Reactor Bldg W/O Prior NRC Approval.Caused by Field Routing of Natural Gas Pipe.Well Isolated by Well operator.W/930603 Ltr ML20077D1631993-05-10010 May 1993 Enforcement Conference, in Arlington,Tx ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20128D7191992-12-0101 December 1992 Safety Evaluation Approving Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise at Plant ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20127F5691992-11-0303 November 1992 Informs Commission of Intent to Issue Order Approving Plant Decommissioning Plan & Corresponding Amend to License DPR-34 ML20101E5761992-05-31031 May 1992 Monthly Defueling Operations Rept for May 1992 for Fort St Vrain ML20096E8221992-04-30030 April 1992 Monthly Operating Rept for Apr 1992 for Fort St Vrain.W/ ML20095E9601992-04-17017 April 1992 Rev to Fort St Vrain Proposed Decommissioning Plan ML20100R7431992-03-31031 March 1992 Monthly Operating Rept for Mar 1992 for Fort St Vrain.W/ ML20090L0621992-02-29029 February 1992 Monthly Operating Rept for Feb 1992 for Fort St Vrain Unit 1 ML20092D0081992-01-31031 January 1992 Monthly Operating Rept for Jan 1992 for Fort St Vrain Nuclear Generating Station ML20102B2241992-01-22022 January 1992 Fort St Vrain Station Annual Rept of Changes,Tests & Experiments Not Requiring Prior Commission Approval Per 10CFR50.59, for Period 910123-920122 ML20094N6701991-12-31031 December 1991 Public Svc Co Annual Financial Rept for 1991 ML20091J6251991-12-31031 December 1991 Monthly Operating Rept for Dec 1991 for Fort St Vrain.W/ ML20094D6711991-11-30030 November 1991 Monthly Operating Rept for Nov 1991 for Fort St Vrain Unit 1 ML20090M1871991-11-20020 November 1991 FOSAVEX-91 Scenario for 1991 Plant Exercise of Defueling Emergency Response Plan ML20086D6891991-11-15015 November 1991 Proposed Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20085N1451991-11-0505 November 1991 Revised Ro:Operability Date of 910830 for Electric Motor Driven Fire Water Pump P-4501 Not Met.Pump Not Actually Declared Operable Until 911025.Caused by Unforseen Matl & Testing Problems.Equivalent Pump Available ML20086C5451991-10-31031 October 1991 Monthly Operating Rept for Oct 1991 for Fort St Vrain.W/ ML20085H6611991-10-10010 October 1991 Assessment of Mgt Modes for Graphite from Reactor Decommissioning ML20091D7671991-10-0101 October 1991 Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change ML20085D9861991-09-30030 September 1991 Monthly Operating Rept for Sept 1991 for Fort St Vrain.W/ 1997-07-01
[Table view] |
Text
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CP,T Roll 2122 (N/C & A) e OA 1486 (REV.10/92)
GA Technologies inc, 6
ISSUE
SUMMARY
TITLE EFFECT OF INTENTIONAL DEPRESSURIZATION ON O R&D 2 APPROVAL LEVEL C00LDOWN FROM 39% POWER USING 1 REHEATER ODV&S MODULE (1-1/2 HOUR DELAY) O DESIGN DISCIPLINE SYSTEM 00C. TYPE PROJECT ISSUE N0/LTR. I l0OCUMENT NO. '
I 01 CFL 1900 3 909217 A I
QUALITY ASSURANCE LEVEL SAFETY CLASSIFICATION SEISMIC CATEGORY ELECTRICAL CLASSIFICATION I FSV-I FSV-I N/A g PREP ^"
APPROVAL ISSUE ISSUE DATE hg BY ENGINEERING
{
FUNDING PROJECT APPLICABLE PROJECT DESCRIPTION /
CWBS NO.
1 IN/C DEC 0 3 gg:1.B .Richarc s W DMY G.P. Conners Initial Release 9 g4./J - dg. . , up
/
, 2970106 A 1 enoy ~
A J. Kennedy ( 757)
(
9'A a.4/d y DEC 2 2 '986 M.B. Richards Release Basis CN - 005653 2970106 CONTINUE ON GA FORM 1485-1 NEXT INDENTU RED Issue Su= mary = DOCUMENTS 1 3 HOT
- MODULE Comp. Runs = 90 Text 2-6 = 5 (30 pages)
Calc. Review Report ST1582 909113
= 3 ST1483 (30 pages)
Appendix A = 21 ( Pages)
Appendix B = ST1673 2
3 RECA Computer Runs = 764 TOTAL = 885 S!0787 (254 pages)
ST3535 (255 pages) 8701070436 861230 ST8750 (255 pages) PDR ADOCK 05000267 F pop i'
( Cmputer output not distributed)
REV SH REV SH 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 REV SH 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 PAGE 1 0F885
, 909217-A CONTENTS
- 1.
SUMMARY
.................................................. 3
- 2. INTRODUCTION ............................................ 3 3 ANALYSIS ................................................ 4 4
RESULTS AND CONCLUSIONS .................................. 5
- 5. REFERENCES .............................................. 6
- 6. CALCULATION REVIEW REPORT ................................ 7 APPENDIX A. RECA and HOT
- MODULE Results . . . . . . . . . . . . . . . . . . . . . A-1 APPENDIX B. Storage of Computer Analysis .................... B-1 TABLES
- 1. Summary of results ....................................... 5 FIGURES A-1 Results for no depressurization ......................... A-2 A-2 Results for 700 s of depressurization ................... A-7 A-3 Results for 1200 s of depressurization .................. A-12 A-4 Results for 1800 s of depressuri zation . . . . . . . . . . . . . . . . . . A-17 Page 2
909217-A
- 1.
SUMMARY
The effect of an intentional depressurization through the helium purification system (HPS) during a plant cooldown using firewater through one reheater bundle from an operating power level of 395 (355 feedwater flow) was studied using the RECA and HOT
- MODULE codes. Forced cooling was assumed to be unavailable for the initial 1-1/2 h of the transient, which is consistent with the Ref. 1 study. The intentional depressurization is simulated at I h into the transient to initially lower the primary pressure such that the PCRV relief valve setpoints are not exceeded later in the transient when forced cooling is restored.
Depressurization times of 700, 1200, and 1800 s were considered in this study.
Results show that depressurizing for 700 s will. keep the peak primary pressure about 20 psi below the relief valve setpoint of 832 psia assumed in the Ref. 1 study and depressurizing for 1800 s will keep the peak primary pressure about 100 psi below this setpoint.
Relief can be initiated as low as 804 psig due to rupture disk limits being exceeded. The loss in helium inventory from intentional depressurization lowers the heat removal capability which results in somewhat higher core region exit temperatures. The maximum economizer tube temperature varies from 1312*F for no intentional depressurization to 1323*F for 1800 s-of depressurization, which is still below the 1350*F limit determined from stress analysis (Ref. 3) on the economizer tube bundle.
- 2. INTRODUCTION The Ref. 1 study considered a plant cooldown using firewater through one reheater bundle after a 1-1/2 h interruption of forced cooling. A single flooded reheater was used for cooldown with the'five remaining reheaters and the six EES bundles assumed to be empty. The other loop was assumed to be unavailable (isolated). The Ref. I study considered Page 3
l
. 909217-A l l
1 operating power levels of 28.6%, 39.25, and 54.15. Power levels below approximately 40% yielded economizer tube temperatures below the maximum allowed value of 1350'F. Specifically, for the 39.2% power case the maximum economizer tube temperature was 1312'F. However, the primary coolant pressure reached a maximum of 832 psia for that case, which results in an opening of the PCRV relief valve and a venting of about 10% of the primary coolant inventory.
The purpose of this study was to consider an intentional, operator controlled depressurization through the HPS for a sufficient period of time (within the 1-1/2 h delay) such that the primary coolant pressure remains below the PCRV relief valve set point for all times later in the transient when forced cooling is restored.
3 ANALYSIS The RECA code was used to determine the core region exit temperatures and flow rates. The HOT
- MODULE code, described in Appendix B of Ref. 1, was then used to determine the temperature distribution among the six operating steam generator modules. As discussed in Ref. 1, the gas entering a given module is well mixed by the time it reaches the economizer tube bundle. The hot module temperature can thus be used as an estimate for the maximum economizer tube temperature.
The RECA runstream for the Ref. 1 39.2% power case was modified to allow for an intentional depressurization through the HPS during the 1-1/2 h delay period before forced cooling is restored. Data for fractional inventory remaining as a function of depressurization time was derived from the Ref. 2 RATSAM analysis and incorporated into the RECA AVGFLO subroutine. For this analysis the depressurization was assumed to start at 1 h and depressurization times of 700, 1200, and 1800 s were considered.
l l
, Paga 4
i l
909217-A 4 RESULTS AND CONCLUSIONS The sequence of events and operating conditions used for this analysis was the same as that fc' the Ref.1 study except that an intentional, operator controlled depressurization through the HPS was simulated for depressurization times of 700, 1200, and 1800 s beginning at 1 h into the 1-1/2 h delay prior to return of forced cooling. The RECA and HOT
- MODULE transient plots are shown in Appendix A. Results are summarized in Table 1.
TABLE 1
SUMMARY
OF RESULTS Intentional % Primary Pressure at end of Peak Peak Depressurization Inventory Depressurization, Pressure Economizer Time, seconds Released psia psia Tube Temp. 'F 0 to ---
832 1312 700 4.8 571 813 1314 1200 9 35 347 771 1318 1800 14.5 519 732 1323 As seen from the above results, the loss in inventory from an intentional depressurization prior to restoration of forced cooling prevents the PCRV relief valve from opening but also lowers the initial heat removal capability somewhat, which in turn results in slightly higher peak economizer tube temperatures. However even for 1800 s of depressurization the peak tube temperature is below the 1350*F limit determined from stress analysis calculations for the 39.25 power level considered in this study.
The start time for depressurization was arbitrarily selected at a point in time during the 1-1/2 h delay (1 h) for this analysis so that available data from Ref. 2 for inventory lost as a function of time would be applicable. If more time is needed to provide cooling water for HPS components, then intentional depressurization initiated at a point in time after forced cooling has been restored but before the l
Page 5
909217-A l
1 primary pressure has peaked could also be effective in preventing 1
relief, provided there is sufficient time during this period to remove j enough helium. For a given amount of helium removed, the depressuriza-tion time will decrease as the primary pressure increases. The heat removal will be somewhat better for intentional depressurization during the forced cooling period since more helium is available for a longer period of time.
- 5. REFERENCES
- 1. Potter, R. C, " Firewater Cooldown Using One Reheater Module (1-1/2 Hour Delay)," CFL 909113- 6 , ocu d e .7.L 1986.
- 2. Silady, F. A. to W. H. Clarke, " Technical Memo of FSV LTA Analyses for Two-Stage Depressurizatibn After LOFC of an Equilibrium Core,"
SAM:255:FAS:77, October 13, 1977.
3 Nichols, M., "FSV Calculations for Circulator Temperature-Related Operating Limits," CFL 908861-N/C, November 13, 1986.
1 Page 6
GA1563mEV.11/80) 4 0 y 2. / "f - A ,
CALCULATION REVIE1N REPORT TITLE: Eppge7 of: jgw y7 o af A f, pepps sy o af g/477sv APPROVAL LEVEL _2r._
dA/ COOL. DO Al Al Fgo nt a b u t K r o - % us c At J 4 */. [#82A.
a uuJ 1 MS/ AJ K / A'E 4fAh QAL LEVEL I DISCIPLINE SYSTEM 00C TYP( PROJECT 00CUMENT NO. ISSUE N0s LTR.
L 01 cFL 1900 9 0 Sal l Ul C INDEPENDENT REVIEWER:
NAME di* C# M b ORGANIZATION d' *di REVIEWER SELECTION APPROVAL: BR MGR DATE /#' N A . S t+e u o'Y REVIEW METHOD: YES NO ERROR DETECTED t
ARITHMETIC CHECK X LOGIC CHECK N ALTERNATE METHOD USED 5 SPOT CHECK PERFORMED I I" COMPUTER PROGRAM USED A NEM Ar f isk V %e Afr t.i /
REMARKS: (ATTACH LIST OF 00CUMENTS USE0 IN REVIEW)
J, ,peju.ssact:.tirber a time us inis,,irt efric ted 0:m E ' .2.(%e t 171.nc ..aa 2~' ;..n'>
/afer.) 77' esc' da se:; are iiO, fi dy ./d('rn.surorhn < v* 5's li'*',a sil?-: -
[*
St.trtisj a f %* C Suetsk dis e, fr e u . r~ ik hof aI5tr Wl2f'*>^'"'"'l be a h ir v es .crq a s,1) .upsid .w i,,, J n.w .it m/ .,~ dep o s u" ' : '*]' ' ^ '
O N a. Minor ~)'erturkh r?, Jc eur'helfa / di/">'m > -
A. Bc;.ui.,,ng HPs in.~ps%n L Erc % ha :< s .r. c' c':s twiri ; c'y d
4*'**
3pc,a/J kas t' .4 trin'tM! t + tc-ci".;n A/H
\
l l
CALCULATIONS FOUND TO BE VAll0 AND CONCLUSIONS TO BE CORRECT:
O' INDEPENDENT REVIEWER 2 '/ ./[-INabuS/d < - DATE /'/?Nd
./ SIGNATURE ' '
Page 7
GA1543(REU.11/80)
CALCULATION REVIEW REPORT TITLE: EF(cr o s xd rsar tod,4 L BE*85m&f-& rod M coo'# " d APPROVAL LEVEL J Mon as Y. saaex usrso i tene trex ,Mosure
( s '/4 #ou,< etc4r) QAL LEVEL I ,
DISCIPLINE SYSTEM 00 C. TYPE PROJECT 00CUMENT NO. ISSUE N0/LTR.
2 $O N A $I l oi C F L., / 1 00 k l
INDEPENDENT REVIEWER:
NAME #- "G ORGANIZATION 45/W EM"W #M REVIEWER SELECTION APPROVAL: BR MGR b - DATE A 'I 'f*'
- 4. S he m y /)
REVIEW METHOD: YES NO ERROR DETECTED X
ARITHMETIC CHECK LOGIC CHECK de ALTERNATE METHOD USED X
SPOT CHECK PERFORMED T
COMPUTER PROGRAM USED X huhm ekk V s-u & br/w REMARKS: (ATTACH LIST OF DOCUMENTS USED IN REVIEW) y o,'a d g h y 7 Q ye p t
}\lt. k Thib revoE4 tb fsf<rr~ek h N !"l- N cadL}w& w&swA % L. Ed ava e sn . n,'<n .
fc@h visa-t. s s- M C & fu. ..
l l
l l
CALCULATIONS FOUNO TO BE '/All0 AND CONCLUSIONS TO BE CORRECT:
INDEPENDENT REVIEWER DATE e O w uRe y , , , , 1
909217-A APPENDIX A RECA AND HOT
l Page A-1
e l 909217-A Fig. A-1. Results for No Depressurization Sheet 1 of 5 mun.st34ss :,esees sateessa naca asa ru rtou m cootape no stretss.
9 TEMPERATURES 2000
- TINPOS
$ 8 ,..... ,
TINFOS - Core Inlet Temperature ATOUTF = Average Cor. Outlet Temperature gyggyp 1500 - TAVOTF - Averese 5.G. Inlet Temperature _ ,,,,,,g.,,,,,
- m - ><-= Core Temperature E
D
s TAUOTF
- -4.-
o 7 ...,,,
R y X--X U "
M Z D ,--- - . . . . - - - - TMAX 1000 #
E -
~,,-__ . _.u --
' ~
S -
F $ OOO see 0I -,
0' 2 4 6 8 19 TIME, HOURS Page A-2
4 909217-A Fig. A-1. Results for No Depressurization Sheet 2 of 5 IBUM*Sf 3469 t t/99eM 18ee6113 IIILCA 354 FW FLW llM C00 LIMO MO MPMSS.
HEAT GENERATI0H AND REMOUAL RATES 60 =
SUMQ O
HEATR 40 - - - X --
M E .
mm - rocal c r H. e c.a.cated, w G HEATR - Total Cor. Heat Removed. W A h U 20 - r A , , $.
T T l\\
S s
- 3 ...'X--.... 7_....# ,
- y. . .. y.. . ._ ,,._.._,y,,,_,
-20 , , , , ,
0' E 4 6 8 10
- TIME, HOURS Page A-3
-. - _ , , , - ,,, _ -. ~ - - - , - -
909217-A I
Fig. A-1. Results for No Depressurization Sheet 3 of 5 1
m smes si,es,se is,,,,,3 ,ge,3,, ,, ,g,, ,, ,,,L,,, ,, ,t,,$s.
PRIMARY SYSTEN PRESSURE 900 PHPSI
- m.
800-P '
S 700-N 5 : u- -
4 600- - ,
! se0 I , , . ,
8' 2 4 6 8 10 TINE, HOURS 4
l l
I l
l i
Page A-4
l 909217-A 4
Fig. A-1. Results for No Depressurization Sheet 4 of 5' i
r l
- stues : <es.se saiesen weg mo re rtov = coeu e o span.
i CIRCULATOR HELIUM FLOW RATE 49 y( _ m
~
m ,,
FLOHTX i f O
! 39 -
~
- L B
i S -
/ 29
) 9
( E -
, C .
19 -
s .
9 CO,O , ,
9' 2 4 6 8 19
, TIME, HOURS i
)
i i
i Page A-5
, _ _ - - _ . - _ _ _ . _ - , - - _ _ . . _ _ _ _ _ _ _ _ ~ .. _ .,_
909217-A 1
Fig. A-1. Results for No Depressurizaticn Sheet 5 of 5 1
l
)
4
.I i 8.8. latt? tres. ass ru rLov ** coouns - untu e.o espeess.
! Legend I
. Hot Module 1300 ' ' -- -
+
8 . Avg Module a . .
p -
e r '
a 1200 -
L -
l '.
u r
U. '.
e . .
1100 i '.
D 5 .
e - ;
g -
F 1000 A
1 .
W 900 '
i , ,
] ,
' E 4 6 8 10 ta i Time, Hours i
l Page A-6 l
909217-A Fig. A-2. Results fo." 700 s of Depressurization Sheet 1 of 5 l
PUM*910?17 llells94 00:34:34 atCA 354 rit FLOW IM toot!Ne 7te SEC ptPetSS.
TEMPERATURES 2000-TINPOS
.' TINFOS - Core Inlet Temperature O pa U.....N,
' ATotTIF - Averese Core Outlet Temperature ATOUTP
~ ,
TAvorF - Averese s.c. .talet Temperature - - X ---
1500 - ', THAt - Max w Core Temperature TAVOTF
's
D . '''''''
E
N'# %
G 'W,'E'-D- TNAX W -XX- S R : , - -~ W = A'::t = - . . , .
.e ---.
1000 - _
E , , "
C E -
S .
F $ OOO 500 -
i 0j . , , ,
0' 2 '4 6 8 10 TIME, HOURS j
l Page A-7
. 909217-A Fig. A-2. Results for 700 s of Depressurization Sheet 2 of 5 see.stete7 tisteres tes34 34 sten see FW FLOW RM C00 LIMO Tee SEC MPRESS.
I HEAT GENERATION AND REMOVAL. RATES 60 SUMQ O
HEATR y.
4g N strito - Total core n.ac cen.cated, w E ,
HEATR - Total Core Heat Removed, W 0
' A ,g W 20 -- :
A ' X.t-
\
T *
\
T S o, a'~.X---- 3 .. ..y . . . .. , . .y.._..,..__..y___
g=.gy Y' i i . . . .
6 8 10 0' 2 4 TIME, HOURS I
Page A-8 wm.
909217-A Fig. A-2. Results for 700 s of Depressurization Sheet 3 of 5
?
EH.S19787 11/18/06 e3:34:34 R(CA 254 FU FLOU RM C00Lif90 700 SEC CEPetSS.
t i CIRCULATOR HELIUM FLOU RATE 40
- - - FLOHTX
_ _-c - - '
g f
30 -
( _
B S
/ 20 -
S -
E -
C -
10-0- % 0. O > > ' '
0' 2 4 6 8 10 TIME, HOURS Page A-9
909217-A Fig. A-2. Results for 700 s of Depressurization Sheet 4 of 5 nun.steter tiensies eensassa aca ssa rv stou nu coot:He too uc uruss.
PRIMARY SYSTEM PRESSURE 900 PHPSI
~
A 800 I
p
% w -.
S 700-I -
A -
600 500 . . . . .
' 6 8 10 0 2 4 TIME, HOURS i
I Page A-10 l 1
l 1- -
909217-A i
Fig. A-2. Results for 700 e of Depressurization l Sheet 5 of 5 '
i i
?
i s.s. Inst tanes. ass ru rtou . me cootins . uttu too set osmss. ;
f400 Legend i
- I
- Hot Module ,
7 1300 ^ Avs Module j
=
(
i C ~
r a 1200 ,' .
t .
u j
e -
1100 D - .
e -
g - * .., ...
A '
1000 F -
ggg i i e i e 0 2 4 6 8 10 12 Time, Hours Page A-11
, 909217-A Fig. A-3 Results for 1200 s of Depressurization Sheet 1 of 5 espe.stign ::.se es es:Hele sten 355 Fw rtou me toottne teos ste MPMSS.
e TEMPERATURES 2000 -
TINPOS
~
.q "
~
[,,g. ' TINFOS - Core talet Temperature
~
' ATOUTF - Average Core Outlet Temperature giggyp TAY0TF - Average S.C. Inlet Temperature _ ,,,,,,g.,,,,,,
1500- ,
\ N - ""*"'s Core Temperature
~
TAVOTF D
E
- % _ . _ 4. . .
7 g .
4 --X. g *' . Y,,, I * ' U -- - ...,.
TNAX R
1999-yX- X Il ,
C 1--- ..
- ~ ~ - -
' - --- o---.
E '
E -
S -
F $ 00 O see- -
i 9- , , . . .
0' 2 4 6 8 19 TIME, HOURS Page A-12
9092f7-A Fig. A-3. Results for 1200 s of Depressurization Sheet 2 of 5 i
sun.etww stessess esseeste Mca Nt PW FLOW SM C00tlHS late 9tt DEPMSS.
HEAT GENERATION AND REMOVAL RATES 69 --
SUNQ
. O l
HEATR 4, _ .X -
l N
E ..
smig - totet Core u.at c.n. rat.4, w MEATR - Total Core Heat Removed, W 89 -
U A , , ;'g\
T \
T k ...~y*~---
$ %n .
- a ,...--..v.........,.......y......,r. . _ y..
(
q_ -g .u - _,
t i
1 9' 2 4 6 8 19 TIME, HOURS ,
i Page A-13
, 909317-A Fig. A-3 Results for 1200 s of Depressurization Sheet 3 of 5 sL90.gtNN listeits teeMelt Atte M4 fW Plow see teettMe teet MC Mpette.
CIRCULATOR HELIUM FLOW RATE 40
. *
- /
39- -
~
L, ..
~
5
/ 20 =
S 1 E -
C -
l .
19
= = ^ ^
j 0-9 e 2 4 6 8 it TIME, HOURS 1
l l
i Page A-11 t
4 1
~
909217-A ]
2 Fig. A-3 Results for 1200 s of Depressurization Sheet 4 of 5 suee stan ti,isen esiseine a ca ni av rtou m con m : = ne u m n. .
PRIMARY SYSTEM PRESSURE 809-PHPSI
~
i
- N A 799- g P -
S .
I
. - A .
600 -+
S00- . . .
2 4 6 8 19 9'
TINE, HOURS Page A-15
909217-A Fig. A-3 Results for 1200 s of Depressurization Sheet 5 of 5 J
1 s.o. tutet tems ase rv atou au cootter. - vitu saes sse espotss.
Legend T 0 Hot Module e 1300 .
e .f ,
r '
a 1200 '
L -
u -
0 '.'.
r e
l*
1100 '
~
D .
e -
g 1000
- F .
A 4
l i
900 - '
i , ,
9 2 4 6 8 10 12 I . Time, Hours l
l i
1, 1
l I
l 1
Page A-16
. 909217-A Fig. A-4 Results for 1800 s of Depressurization Sheet 1 of 5 i
PUN.$tgiS9 33/37,33 33880889 MCA 355 FW Ft0W AM C00LjNG 1990 SEC MPet!S.
TEMPERATURES 2000 TINPOS 9
-f..e..
. TINF0S - Core Inlet Temperature O ATOUTF - Average Core Outlet Temperature
,,' ATOUTP 1500 - , TAVOTT - Average S.C. Inlet Temperature _
D
- ' nsAt - u==4-= core Temperature , , , , , ,,_
E u , 7AVOTF G
7 a -
R y X-Xh ,
Y-E'* -
2)p.:g- ,-g . .
TMAX S
.- -l F c=cc 500 -
9 - i i
0' 2 4 6 8 10 TIME, HOURS 1
Page A-17
- 909217-A Fig. A-4. Results for 1800 s of Depressurization Sheet 2 of 5 IRM.9ft?Se Stel?/06 18129899 #tCA 354 Fu FLOW Rs4 C00 Lites 1000 SEC MPetSt.
HEAT GENERATI0H AND REMOVAL RATES 60 SUMQ m
- v HEATR 40 - - X-- --
N sum - Teest core u. e cen. raced, m E _
G REATR - Total Core Heat Removed, W A ,
W 20 A
~
, h s
S F0 3 ..M ----
g - - - -- x . . .. . . .,__.__...y......,_.._,y,,_,,,_,
_. u .v - - ;
0 __ MV4 0' 2 4 6 8 10 TIME, HOURS i
l l
l l
l l
Page A-18
. . l
- 909217-A Fig. A-4. Results for 1800 s of Depressurization Sheet 3 of 5 SUM *$f8790 ll/87eM 18880889 9tte Me PJ FLOW 1I84 C00LIPet 1800 SCC MParggg, i
CIRCULATOR HELIUM FLOW RATE 40 FLOHTX C C t C A
~
f 30 -
L -
B S
/ 20 -
S -
E -
C -
10 -
0-- --,m , , , ,
e' 2 4 6 8 10 TIME, HOURS ,
1 Page A-19
- a. .
~
. 909217-A Fig. A-4. Results for 1800 s of Depressurization Sheet 4 of 5
,we.stene :, sues seiaein uca 35 Su 'Lov m cootim isu sac unuss.
PRIMARY SYSTEM PRESSURE 800--
. PHPSI O
I W -
vee-P L 1 g --
I A -
600 --
See- i i i * '
' 10 g 2 4 6 8 :
TIME, HOURS .
Page A-20
909217-A i Fig. A-4. Results for 1800 e of Depressurization Sheet 5 of 5 i
s.e. Inutt tenps ses rv rtov . au cootino - witu tsee uc paretss.
1400 Legend
~ Hot Module T
, 1300 1% -- -- - ---
Avg Module
~ f m -
T p .
/
e
1200 u ll r : .,
e - '
1100 '
j o . .
. .4. . .
i e .
- l. '* ..,
g 1000
.. A F -
900 ' ' i i i 0 2 4 6 8 le 12 Time, Hours l
Page A-21
909217-A APPENDIX B STORAGE OF COMPUTER ANALYSIS l
I 1
i 1
)
Page B-1
909217-A APPENDIX B STORAGE OF COMPUTER ANALYSIS The results presented in Appendix B were generated with the RECA and HOT
- MODULE codes. These codes and the runstreams are stored in archive file SYSD4040. The computer runs was made for this study are identified as follows:
Depressurization Time RECA HOT
- MODULE 700 s ST0787 ST1582 1200 s ST3535 ST1483 1800 s ST8750 ST1673
(
Page B-2
,y,- . ._ g .J s . ...w -. - --- - - - - - - - - - - - - - - - - - - - - - ' - - - -
6 J
s 1
ATTACHMENT 11 4
h