Letter Sequence Approval |
---|
|
Results
Other: ML20082E320, ML20093M745, ML20093M749, ML20094A277, ML20100C247, ML20101C284, ML20116G049, ML20198A027, ML20204E694, ML20204E706, ML20205B056, ML20205B071, ML20214R856, ML20214R871, ML20235Z262, ML20236H257, ML20262E589, ML20262E593, ML20262E597, ML20262E601, ML20262E606, ML20262E611, ML20262E615, ML20262E619, ML20262E624, ML20262E629, ML20266F484, ML20266F489, ML20266F494, ML20266F498
|
MONTHYEARML20266F4841983-04-28028 April 1983 Ft St Vrain 2500 Kva Xfmr Foundations & Details. Sheet 1 of 2.No Rev Date Project stage: Other ML20266F4891983-05-0202 May 1983 Ft St Vrain 2500 Kva Xfmr Foundations & Details. Sheet 2 of 2 Project stage: Other ML20266F4981983-06-17017 June 1983 480V Transformer Fire Protection Sys Project stage: Other ML20082E3201983-11-0909 November 1983 Responds to Notice of Deviation Noted in IE Insp on 830801-31.Corrective Actions:Concrete Samples Taken at End of Concrete Pump Discharge Line,Addl Lighting Installed & Number of Concrete Vibrators Increased Project stage: Other ML20262E6111984-01-0404 January 1984 Building 10 Concrete Sections & Details, as-built.Sheet 3 Project stage: Other ML20262E6151984-01-0404 January 1984 Building 10 Steel Framing Plans, as-built Project stage: Other ML20262E6191984-01-0404 January 1984 Building 10 Walk-Thru Structure Floor Plans, as-built Project stage: Other ML20262E6241984-01-0404 January 1984 Building 10 Walk-Over Structure Roof Plan & Details, as-built Project stage: Other ML20262E6291984-01-0404 January 1984 Building 10 Walkover Structure Steel Elevation, as-built Project stage: Other ML20262E5971984-01-0505 January 1984 Building 10 Architectural Elevations & Details, as-built Project stage: Other ML20262E6011984-01-0505 January 1984 Building 10 Concrete Floor Plans, as-built Project stage: Other ML20093M7491984-01-22022 January 1984 Rept of Changes,Test & Experiments Not Requiring Prior Commission Approval Per 10CFR50.59(a) for 840101-22 Project stage: Other ML20093M7451984-07-20020 July 1984 Forwards Rept of Changes,Tests & Experiments Not Requiring Prior Commission Approval for 840101-22.Anniversary Date of Rept Changed to Correspond W/Submittal of Annual Update to Fsar.Future Annual Repts Will Cover Jan 23 - Jan 22 Project stage: Other ML20094A2771984-07-25025 July 1984 Responds to NRC 840625 Concerns Re Bldg 10 Const.Concept of Bldg 10 Finalized to Relieve Crowding Conditions & to Accommodate Equipment Replacements Being Planned.Bldg 10 Constitutes Mod Not Requiring Amend to OL Project stage: Other ML20262E5931984-09-21021 September 1984 Building 10 Site Plan & Caisson Details Project stage: Other ML20262E6061984-09-27027 September 1984 Building 10 Concrete Sections & Details, as-built.Sheet 1 Project stage: Other ML20101C2841984-11-29029 November 1984 Forwards Hl Brey for Redistribution Due to Error in Ltr Date.Correct Date Should Be 831101 Project stage: Other ML20100C2471985-03-11011 March 1985 Advises That Attachments A,B,C & D Re Diesel Generator Loading,Battery Sizing,Listing of Encl Drawings & Partial one-line Diagram Forwarded to J Miller,Per 850227 Telcon Request Project stage: Other ML20116G0491985-04-12012 April 1985 Informs That Listed Electrical Sys Drawings Sent to J Miller of NRR for Review,Per 840410 & 12 Requests.Copy of Logic Diagrams Being Prepared by I Ahmed Requested Project stage: Other ML20133A4141985-07-23023 July 1985 Forwards Request for Addl Info Re Const of Bldg 10 & Associated Walkover Structure,Including Engineering Drawings,Walkover Structure Layout & Spatial Relationship W/Surrounding Bldgs Project stage: RAI ML20262E5891985-08-0808 August 1985 Ft St Vrain Plot Plan. Sheet 1 of 1.Drawing Consists of Two Aperture Cards Project stage: Other ML20137C4011985-11-21021 November 1985 Requests Addl Info Re Bldg 10,including CN-1255 & CN-1332 for Sys 92 & CN-1294 for Sys 92/45.For Each Cn,Safety Evaluation & Design Criteria & Analysis Required.Info Requested within 30 Days of Ltr Receipt Project stage: Approval ML20138P0791985-12-17017 December 1985 Forwards Legible Copy of Safety Evaluation Design Criteria & Design Analysis for Change Notices CN-1255,CN-1332, CN-1294 & CN-1391,per NRC 851121 Request for Addl Info. Future Changes to CN-1391 Cover nonsafety-related Battery Project stage: Request ML20205B0711985-12-31031 December 1985 Rev 0 to Evaluation of Structure-Soil-Structure Interaction Effect Between Bldg 10/Walkover Structure & Main Plant Project stage: Other ML20153H0571986-02-19019 February 1986 Forwards Safety Evaluation Re 850828 Submittal Concerning Bldg 10 & Walkover Structure.Designs Acceptable,Per FSAR Requirements for Category 1 Bldgs.Confirmatory Analysis, Addressing Lack of Clearance Between Structures,Requested Project stage: Approval ML20153H0731986-02-19019 February 1986 Safety Evaluation Supporting Bldg 10 & Walkover Structure Design,Per FSAR Requirements for Category 1 Bldgs.Lack of Clearance Between Structures Should Be Addressed by Util Project stage: Approval ML20266F4941986-03-15015 March 1986 Bus Duct Layout and Location of Bus Duct Supports Project stage: Other ML20204A2161986-05-0101 May 1986 Forwards Request for Addl Info Re Bldg 10 Electrical Mods, Including Confirmation That All Class 1E Power,Control & Instrumentation Cables in Bldg 10 Qualified for Environ of 120 F Project stage: RAI ML20197F6541986-05-0707 May 1986 Summary of 860423-24 Meetings W/Util,Ga Technologies & S&W at Site Re Fuel Block Cracking,Bldg 10 Const,Seismic Instrumentation,Pcrv Tendons & Integrated Leak Rate Testing. Attendance List & Viewgraphs Encl Project stage: Meeting ML20198A0271986-05-12012 May 1986 Responds to NRC 860219 Questions Re Bldg 10 & Walkover Structure.Walkover Structure & Bldg 10 Designed Such That Structural Elements Will Not Impact on Adjacent Bldgs During Seismic Event Project stage: Other ML20204E7061986-06-19019 June 1986 Forwards Addl Info Re Bldg 10 Electrical Mods & Essential Power Bus Upgrades,Per NRC 860501 Request Project stage: Other ML20199J0261986-06-25025 June 1986 Requests Addl Info Re Structural Evaluation of Bldg 10 & Walkover Structure,Discussed at 860423 & 24 Meetings.Ltr Inadequately Addressed NRC Concerns Project stage: Meeting ML20204E6941986-07-25025 July 1986 Forwards Resubmittal of Addl Info Re Bldg 10 Electrical Mods & Essential Power Bus Upgrades to Include Attachments Not Received by NRC Project stage: Other ML20205B0561986-07-28028 July 1986 Forwards Addl Info Re Structural Analysis of Bldg 10 & Walkover Structure,Per 860625 Request,Including Seismic Model Used for Bldg & Rev 0 to SAD-481, Evaluation of Structure-Soil-Structure.. Project stage: Other ML20214R8561987-03-0606 March 1987 Forwards EGG-NTA-7607, Technical Evaluation Rept Evaluation of Bldg 10 Electrical Mods Fort St Vrain Nuclear Generating Station, Informal Rept Project stage: Other ML20205R1561987-03-31031 March 1987 Forwards Request for Addl Info Re Seismic Design of Bldg 10, for Nrc/Bnl Review.Site Visit to Review Response to Encl Questions,To Insp Bldg 10 & to Audit Supporting Structural Matl Recommended within 60 Days of Ltr Receipt Project stage: RAI ML20214R8711987-03-31031 March 1987 Technical Evaluation Rept Evaluation of Bldg 10 Electrical Mods Fort St Vrain Nuclear Generating Station, Informal Rept Project stage: Other ML20215F9631987-05-29029 May 1987 Forwards Response to NRC 870331 Request for Addl Info Re Bldg 10,per 870527 Telcon.Supporting Matl for Bldg 10 Structural Analyses Available in Util Ofc for Review Project stage: Request ML20235Z2621987-07-0808 July 1987 Requests Addl Info from Util Re Bldg 10 Seismic Design, Including Descriptive Matl for PILAY2 Computer Code & Sketches or Drawings Showing Caisson/Slab/Wall Configurations Project stage: Other ML20236H2571987-07-28028 July 1987 Requests Addl Info Re Seismic Design of Bldg 10,based on Util 870529 Submittal.Response Requested within 45 Days of Ltr Date Project stage: Other ML20234D8091987-09-0909 September 1987 Responds to NRC 870728 Request for Addl Info Re Bldg 10, Including Descriptive Matl for PILAY2 Computer Code & Sketches or Drawings of Caisson/Slab/Wall Configurations. Sketch of Configuration & Wall Stiffness Calculation Encl Project stage: Request ML20150C4441988-03-10010 March 1988 Forwards Safety Evaluation Re Seismic Analysis of Bldg 10 & Walkover Structure.Seismic Analysis Methods Used Conservative Relative to FSAR & Acceptable Project stage: Approval ML20150C4541988-03-10010 March 1988 Safety Evaluation Concluding That Seismic Analysis Methods for Bldg 10 & Walkover Structure Conservative.Gaps Provided Adequate to Accommodate Relative Motions Which Occur Between Subj Structures & Walkover Structure & Turbine Bldg Project stage: Approval 1985-07-23
[Table View] |
|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20141K9961997-05-0505 May 1997 Safety Evaluation Supporting Amend 89 to License DPR-34 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 ML20246J3261989-08-30030 August 1989 Safety Evaluation Supporting Amend 72 to License DPR-34 ML20245J3781989-08-14014 August 1989 Safety Evaluation Supporting Amend 71 to License DPR-34 ML20245J4511989-08-0808 August 1989 Safety Evaluation Responding to Issues Re Tech Spec Upgrade & Plant Defueling.Stated Tech Spec Sections Should Be Upgraded ML20246J3131989-07-0707 July 1989 Safety Evaluation Concluding That Operators Role in Mitigating High Energy Line Break at Facility Acceptable ML20247R2261989-05-26026 May 1989 Final Safety Evaluation Re LER 87-20 Concerning Interactions Between Steamline Rupture Detection/Isolation Sys,Plant Protective Sys & Control Sys at Facility ML20245C5031989-04-18018 April 1989 Safety Evaluation Supporting Amend 70 to License DPR-34 ML20248D6501989-03-31031 March 1989 Safety Evaluation Supporting Amend 69 to License DPR-34 ML20236A1401989-02-27027 February 1989 Safety Evaluation Supporting Amend 68 to License DPR-34 ML20235T4511989-02-24024 February 1989 Safety Evaluation Re Facility Core Support Flow Vent Sys. Continued Operation of Facility W/Current Core Support Flow Sys Configuration Acceptable ML20235J3421989-02-16016 February 1989 Safety Evaluation Supporting Util Action in Response to Generic Ltr 83-28,item 2.1 (Part 2) Confirming Establishment of Interface W/Either NSSS Vendor or Vendors of Each Component in Reactor Trip Sys ML20235J3841989-02-13013 February 1989 Safety Evaluation Concluding That Continued Operation of Facility Not Affected by Steam Generator Tube Failures Experienced by Advanced gas-cooled Reactors ML20195D3911988-10-27027 October 1988 Safety Evaluation Supporting Corrective Actions of LER 86-017 ML20205G0021988-10-24024 October 1988 Safety Evaluation Supporting Amend 65 to License DPR-34 ML20154J8021988-09-15015 September 1988 Safety Evaluation Supporting Amend 64 to License DPR-34 ML20154J4621988-09-15015 September 1988 Safety Evaluation Supporting Amend 63 to License DPR-34 ML20207F0571988-08-10010 August 1988 Safety Evaluation Supporting Util 870206 Submittal Re Safe Shutdowns During Postulated Accident Conditions ML20207F0431988-08-0505 August 1988 Safety Evaluation Supporting Amend 61 to License DPR-34 ML20207F2411988-08-0505 August 1988 Safety Evaluation Supporting Amend 62 to License DPR-34 ML20151M1601988-07-21021 July 1988 Safety Evaluating Supporting Requirements for Redundancy in Responding to Rapid Depressurization Accident ML20151A9961988-06-20020 June 1988 Safety Evaluation Supporting Amend 60 to License DPR-34 ML20195K0651988-06-15015 June 1988 SER Concurring W/Util Proposed Corrective Actions in Engineering Rept Entitled, Rept of Helium Circulator S/N 2101 Damage & Inlet Piping S/N 2001 Repair & Mod Activities ML20195F9661988-06-15015 June 1988 Safety Evaluation Re Destructive Exam Rept for Fuel Test Assembly-2.Fuel Represented by Fuel Test Assembly-2 Predicted to Be Safe for Operation in Facility for 1,800 EFPDs ML20154F8891988-05-10010 May 1988 Safety Evaluation Re Proposed Safe Shutdown Sys & Exemption Requests Concerning 10CFR50,App R.Licensee Request for Exemptions in Listed Areas Should Be Granted.Concept for Providing post-fire Shutdown Acceptable ML20148S6031988-04-0707 April 1988 Safety Evaluation Supporting Amend 59 to License DPR-34 ML20151B6651988-04-0101 April 1988 Supplemental Safety Evaluation Supporting Util Compliance w/10CFR50.App R Re Safe Shutdown DHR Capacity ML20150C4541988-03-10010 March 1988 Safety Evaluation Concluding That Seismic Analysis Methods for Bldg 10 & Walkover Structure Conservative.Gaps Provided Adequate to Accommodate Relative Motions Which Occur Between Subj Structures & Walkover Structure & Turbine Bldg ML20147C8181988-02-25025 February 1988 Safety Evaluation Supporting Changes to Interim Tech Specs 3/4.1.7, Reactivity Change W/Temp NUREG-1220, Safety Evaluation Accepting Plant Special Senior Licensed Fuel Handler Initial & Requalification Operator Training Program,Per NUREG-1220, Training Review Criteria & Procedures1988-01-13013 January 1988 Safety Evaluation Accepting Plant Special Senior Licensed Fuel Handler Initial & Requalification Operator Training Program,Per NUREG-1220, Training Review Criteria & Procedures ML20237D7631987-12-18018 December 1987 Safety Evaluation Updating 861118 Fire Protection Sys Safety Evaluation.Util Alternate Fire Protection Configuration Acceptable ML20149E1621987-12-18018 December 1987 Marked-up Safety Evaluation Re Proposed Safe Shutdown Sys & Exemption Requests Concerning 10CFR50,App R ML20236U6961987-11-23023 November 1987 Safety Evaluation Supporting Amend 57 to License DPR-34. Addendum to Review of Proposed Tech Spec Change:Core Inlet Valves/Min Helium Flow & Max Core Region Temp Rise,Limiting Condition for Operation..., Technical Evaluation Rept Encl ML20236U5761987-11-20020 November 1987 Safety Evaluation Re Helium Circulator S/N C-2101 Damage. Util Corrective Action Program Initiated ML20236R3001987-11-13013 November 1987 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components ML20238C7621987-09-0202 September 1987 Safety Evaluation Concurring W/Util 870702 & 27 Ltrs & 870818 Telcon Re Elimination or Reduction of Maint Requirements on Certain Fire Seals ML20235N6491987-07-13013 July 1987 Safety Evaluation Supporting Amend 56 to License DPR-34 ML20235F5281987-07-0202 July 1987 Safety Evaluation Re Safe Shutdown of Steam Generator Matls. Under Severe Transient Conditions,Fuel Temp Can Be Maintained Under Accepted Temp Limits & Plant Can Be Safely Shutdown ML20235F5151987-07-0202 July 1987 Safety Evaluation Re Safe Emergency Shutdown of Reactor Sys. Operation at 82% Acceptable ML20235F5441987-07-0202 July 1987 Safety Evaluation Re Effect of Firewater Cooldown on Steam Generator Structural Integrity.All Tests Acceptable ML20235E5281987-06-29029 June 1987 Safety Evaluation Supporting Amend 55 to License DPR-34 ML20216G9511987-06-24024 June 1987 Revised Safety Evaluation Re Steam Line Rupture Detection & Isolation Sys (Slrdis).Slrdis Meets Requirements of 10CFR50, App A,Gdc 20 & GDC 4 ML20216G9911987-06-24024 June 1987 Supplemental Safety Evaluation Supporting Application for Amend to License DPR-34 Re Tech Specs for Steam Line Rupture Detection & Isolation Sys ML20215J5401987-06-22022 June 1987 Draft Safety Evaluation Re Safe Emergency Shutdowns.Facility Operation at 82% Power Acceptable ML20216J1921987-06-17017 June 1987 Safety Evaluation Re Mods to Reduce Moisture Ingress Into Reactor Vessel.Periodic Insps & Preventive Maint Should Be Performed on Pertinent Components.Operational Performance Should Be Continuously Upgraded ML20214M4681987-05-20020 May 1987 Safety Evaluation Supporting Amend 54 to License DPR-34 ML20215J8271987-05-0505 May 1987 Safety Evaluation Supporting Amend 53 to License DPR-34 ML20209D7561987-04-22022 April 1987 Safety Evaluation Supporting Util 870211 Submittal Re Performance Enhancement Program,Finding 4-10 ML20206J9331987-04-0606 April 1987 Safety Evaluation Supporting Amend 52 to License DPR-34 ML20205S1141987-03-31031 March 1987 Safety Evaluation Accepting Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability On-Line Testing. Facility Designed to Permit on-line Functional Testing,Including Testing of Reactor Trip Contactors 1997-05-05
[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
.
Enclosure FORT ST. VRAIN BUILDING 10
, SAFETY EVALUATION Building 10 at Fort St. Vrain is a 4 story nuclear Class 1 safety related reinforced concrete structure which houses a battery room, electrical equipment, two computer rooms, an office and a training room. The building is located about 10 feet east of the Turbine Building and about 10 feet south of the Technical Support Building. The space between Building 10 and the Turbine Building is bridged by a Walkover Structure along a portion of the Building 10 west wall. Building 10 is 30 by 41 feet in plan and is 63 feet tall. The outer walls are 12 inch thick reinforced concrete. The structure is founded on 6 reinforced concrete caissons 4 feet in diameter and approximately 58 feet long. The caissons are keyed into the underlying rock a minimum of 6 feet. The floors are 6 inch thick reinforced concrete slab supported by steel beams, except for the top floor slab, which is I foot 3 inches thick. The roof slab is 1 l
foot thick reinforced concrete also supported by steel beams. The first
~
floor is a reinforced concrete slab on grade.
The Walkover Structure provides access from the Turbine Building into Building 10 at two floor levels. The Walkover Structure is approximately 10 by 20 feet in plan dimension and'is approximately 52 feet tall. The l
building is constructed of braced structural steel with metal siding on the north and south walls. The east and west walls are provided by Building 10 and the Turbine Building respectively. Thestructurfhastwo
~
5602280598 86021927 l DR ADOCK O
intermediate reinforced concrete floor slabs and a reinforced concrete roof supported on steel beams. The steel columns that suppoit the structure are founded on reinforced concrete footings that are in turn '
supported by the soil. The first floor is a reinforced concrete slab on grade.
The licensee stated in a letter (Lee to Hunter dated August 28,1985) that the two structures were designed and constructed in accordance with the following building codes.
- 1. AISC Manual of Steel Construction; 8th edition 1980
- 2. Uniform Building Code (UBC) 1979
- 3. ACI 318 1977
- 4. ACI 349 1976
- 5. AWS D1.1
~
The results of the seismic analysis of Building 10 and the Walkover Structure were reported by the licensee in the August 28, 1985 letter.
The response spectrum technique was used where the north-south and vertical direction or the east-west and vertical direction motions are combined using the absolute sum method. The stresses that result from earthquakes are combined with loads from other sources according to the combination equations described in the FSAR. The stresses computed using the load combination equations were compared with the allowa61( stresses and were reported to be below these allowables.
i 3-The deflections of the Turbine-Reactor Building and the Walkover Structure and Building 10 were provided by the Licensee in the August 28, 1985 letter. The largest computed absolute differential displacement in the direction of concern (east-west) was 0.81 inches for the Design Basis Earthquake (DBE). It is not clear from the information provided whether the licensee means that this is the sum of the deflections for the Turbine Building - Walkover Structure or the Walkover Structure -
Building 10 movements or the relative movements of the building pairs.
This item should be clarified in responding to our question below.
l The detailed sections on the drawings provided show a 1 inch clearance at the foundation and a 2 inch clearance at the roof of the Walkover Structure.
4 The information provided on drawing B-453 Section L shows the clearance of the checkered plate on the intermediate floors in the Walkover Structure to be 1/4 inch. This is less than the calculated required clearance of 0.81 inches. Therefore, it is possible to have collision between the Walkover Structure and Building 10 at elevations 4811 and
- 4829 feet and collision between the Walkover Structure and the Turbine
- Building at the same elevations.
l The licensee stated in the August 28 letter that both structures were designed to withstand the tornado specified in the FSAR. The tornado missile used for the design was a 4 x 12 inch by 12 feet fir plank weighing 105 pounds. The licensee also reported that an impact analysis of the Building 10 walls was performed which indicated that they could 4
resist the postulated missiles without penetration or spalling of the concrete. The metal siding on the Walkover Structure was qualified by.a l topical report by H. H. Robertson, the manufacturer of the siding. (The final acceptance of this topical report is still pending.) Building 10 was designed to withstand an external pressure drop of 3 psig in 3 seconds.
4 The Walkover Structure was qualified by the licensee by showing that the building would depressurize in 0.2 seconds by venting the internal air )
through openings in the corners of the structure, and the siding could
, withstand the reduced pressures. ;
EVALUATION The staff has examined the information provided in the FSAR Section 1.2.2.2 and in a Public Service Company of Colorado letter from Lee to Hunter, NRC, Region IV, dated August 23, 1985 with attached drawings.
The staff finds that Building 10 and the Walkover Structure were designed
~
- in accordance with the requirements specified in the FSAR for Category I buildings. However, the staff is concerned about the apparent lack of clearance between the Walkover Structure and Building 10. It appears that these two structures could impact each other during the postulated i earthquake. This apparent impact potential should be addressed by the .
utility. :
1 Reviewer: H. Polk l
l l
1