Letter Sequence Approval |
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Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: ML20087D526, ML20091E427, ML20091E667, ML20096C267, ML20101P455, ML20101T673, ML20128N324, ML20128Q523, ML20132D461, ML20133E065, ML20133G264, ML20134E393, ML20135B283, ML20137G089, ML20137M414, ML20138M184, ML20141G663, ML20141P193, ML20148G166, ML20149E148, ML20155G379, ML20197B758, ML20198D937, ML20202F052, ML20204G480, ML20205D265, ML20206B182, ML20207E030, ML20207Q913, ML20209C232, ML20211G583, ML20214P255, ML20214P273, ML20214U381, ML20214U731, ML20214X272, ML20235F214, ML20235G486, ML20236C261, ML20236G303, ML20236H463
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MONTHYEARML20087D5261984-03-0202 March 1984 Requests Exemption from Requirements of Sections Iii.G,J,L & O to 10CFR50,App R.Fire Protection Provisions Believed Adequate to Protect Health & Safety of Public in Event of Accidents Involving Fires.Affidavit Encl Project stage: Other ML20091E6671984-05-10010 May 1984 Forwards List of Correspondence on Fire Protection,Per 840427 Request.List Identifies Ltrs Originated from NRC & Util Relevant to Fire protection,10CFR50,App R,Branch Technical Position 9.5-1,cable Separation & Plant Issues Project stage: Other ML20091E4271984-05-11011 May 1984 Forwards Summary of Fire Protection Review to Determine Conformance of Facility to Section Iii.G of 10CFR50,App R, Per 840427 Commitment.Fire Protection Provisions Adequate Project stage: Other ML20092M5471984-06-22022 June 1984 Responds to 840608 Meeting Re Application of 10CFR50,App R Fire Protection Requirements to Facility.Schedule for App R Review & Submittal & Proposed Fire Protection Regulatory Guidance Resolving HTGR Issues Encl Project stage: Meeting PNO-IV-84-014, on 840623,reactor Tripped on High Pressure Signal & 6 of 7 Control Rod Pairs Failed to Drop.Cause Unknown.Drive Mechanisms Will Be Removed for Exam1984-06-25025 June 1984 PNO-IV-84-014:on 840623,reactor Tripped on High Pressure Signal & 6 of 7 Control Rod Pairs Failed to Drop.Cause Unknown.Drive Mechanisms Will Be Removed for Exam Project stage: Request ML20090C5261984-07-0606 July 1984 Responds to NRC Concerns Re Fire Protection Review,Bldg 10 Licensing Requirements,Control Rod Failure to Scram, Documentation of Disciplinary Actions,Clearance Tags & Radiological Emergency Exercise Scenario,Per 840625 Meeting Project stage: Meeting ML20096C2671984-08-17017 August 1984 Forwards Revised Schedule for App R Review,Submittals,Plant Mods & Fire Protection Safe Reactor Shutdown/Cooldown Capability Incorporating NRC Concerns & Comments Project stage: Other ML20101P4551984-12-14014 December 1984 Advises That Final Installation of Oil Mist Detection Sys Completed Wk of 841105,per 840625 Commitment.Sys Inoperable During Initial Checkout.Manufacturer Repaired & Balanced Entire Sys on 841115,however,on 841121 Sys Inoperable Again Project stage: Other ML20101T6731985-01-25025 January 1985 Forwards Table 5.0.1,omitted from Rept 3 of App R Fire Protection Evaluation,Originally Submitted by Project stage: Other ML20128Q5231985-05-15015 May 1985 Responds to Re Contradictory Statements Submitted in Three Util Ltrs.Circulator Speed Instruments Not Relied Upon in 10CFR50,App R,Re Fire Protection Evaluation Because of Close Proximity Between Loops Project stage: Other ML20128N3241985-05-17017 May 1985 Informs of Completion of Mod Work to Automate G&J Wall Sprinkler Sys,Per 840817 App R Commitment Project stage: Other ML20132D4611985-07-11011 July 1985 Documents 850708 Telcon Re Interim Fire Protection Measures Committed to in or Lee .Fire Watch Frequency Increased.Personnel Will Carry Flashlights at All Times Per Operating Order 85-11,prior to Plant Startup Project stage: Other ML20133G2641985-07-16016 July 1985 Documents 850715 Telcon Re App R Fire Protection Evaluation Schedule.Util Will Complete Mod Item 4.2 Re Penetration Seals by 850717.Revised Completion Date Allows for Installation of Final Seal,Surveillance Testing & Sign Offs Project stage: Other ML20132F0231985-07-19019 July 1985 Forwards Safety Evaluation Re Environ Qualification of Electric Equipment Important to Safety & Authorizes Interim Operation in dry-out Mode at Max 15% of Rated Power,Based on Listed Conditions,Until Technical Review Completed Project stage: Approval ML20132F0721985-07-19019 July 1985 Safety Evaluation Documenting Deficiencies in Licensee Program for Environ Qualification of Electric Equipment Important to Safety.Licensee Response to Generic Ltr 84-24 Inadequate.However,Operation at 15% Power Authorized Project stage: Approval ML20133H5331985-08-0202 August 1985 Requests Assessment of Consequences of Loss of Shutdown Sys Due to Fire in Bldg 10,as Part of Review of Fire Protection Features at Plant.Evaluation Requested within 30 Days of Ltr Date Project stage: Approval ML20134E3931985-08-0505 August 1985 Submits Info on Status of Mods Proposed in 850401 Rept 4 Re Exemptions & Mods to App R Fire Protection Evaluation.Listed Mods Complete Project stage: Other ML20137G0891985-08-0808 August 1985 Notifies of Delay in Obtaining All Replacement Fire Door Matls,Per ,Due to Door to Hardware Compatibility Problems W/Facility Security Sys.Matls Will Be Delivered by 851015 Project stage: Other ML20135B2831985-08-30030 August 1985 Provides Info to Resolve Questions & Concerns Identified in Review of Repts 1-4 for App R Evaluation & Rept 5 for Branch Technical Position 9.5-1,App a Evaluation of Bldg 10.Page Changes for Repts 1-5,incorporating Resolutions,Encl Project stage: Other ML20205D2651985-09-0303 September 1985 Informs of Fire Detection Sys Design Status.Initial Change Notice Providing Detection Device Design & Location Issued on 850901,per 850401 Commitment.Installation Expected by 860201 Project stage: Other ML20133E0651985-09-10010 September 1985 Responds to NRC Re Violations Noted in Insp Rept 50-267/85-16.Corrective Actions:Design for New Storage Ctr Initiated Project stage: Other ML20138M1841985-10-14014 October 1985 Clarifies Commitment Dates in Util Re Proposed Mods Per 10CFR50,App R Fire Protection Evaluation.Remaining Mods Expected to Be Completed During Refueling Outage Project stage: Other ML20136J3161985-11-0101 November 1985 Forwards Questions Re Manual Operations & Instrumentation Based on Review of 841116-1217 & 850117 & 0401 Submittals of App R Safe Shutdown Models.Addl Info Requested within 30 Days of Ltr Receipt Project stage: Approval ML20138P3311985-12-20020 December 1985 Forwards Response to 851101 Request for Addl Info Re App R Safe Shutdown Model.Steps Included in Fire Protection Shutdown Procedure for Operators to Properly Position motor- Operated Valves Project stage: Request ML20137M4141986-01-21021 January 1986 Informs of Updated Efforts to Implement Fire Detection Sys. Completion Anticipated by 860601.As Result of extension,24 H Fire Watch Will Continue as Stated in Interim Measures of Rept 4 Project stage: Other ML20141P1931986-03-14014 March 1986 Forwards Info/Clarification for Open Items & Revised App R Fire Protection Evaluations (Repts 1-4) & Fire Hazards Analysis & Evaluation of Bldg 10 (Rept 5) Project stage: Other ML20202F0521986-04-0404 April 1986 Forwards Valve Position & Alignment Justification & Revs to App R Repts 1 & 3 Incorporating Manual Pressurization Sys for Helium Circulator Brake & Seal Sys Into Shutdown Model, Per 860314 Commitment Project stage: Other ML20141G6631986-04-17017 April 1986 Requests Util Evaluate Encl NRC 851222 Press Release Re New Criteria for Granting Exemptions from 10CFR50 to Determine If Exemptions from App R Fire Protection Requirements Still Required.Info Requested within 60 Days Project stage: Other ML20155G3791986-04-28028 April 1986 Requests That 850401 Exemption from Sections Iii.G & Iii.J of App R & 10CFR50.12(a) Re Fire Protection Be Granted.List of Exemptions Encl Project stage: Other ML20198D9371986-05-15015 May 1986 Forwards App R Evaluation Re Valve Position & Alignment,As Encl to Walker ,Per Request Project stage: Other ML20202G6441986-07-10010 July 1986 Informs of Plans to Submit Documentation Re Results of CRD Improvements Integrated Sys Study by 860815.Requests NRC Confirmation of Submittal Date Project stage: Request ML20207F3771986-07-15015 July 1986 Forwards Supplemental Info to 860314 & 0404 Submittals Re Local Manual Operations Required for Fire in Each Area & Assessment of Adequacy of Present Staffing Levels to Accomplish Fire Protection Shutdown Project stage: Supplement ML20204C1671986-07-22022 July 1986 Responds to 860428 Request for Exemption from Fire Protection Requirements,Per 10CFR50.12.Although Technical Review Not Completed,Submittals Adequately Address Criteria. Request for Relief from 10CFR50.48 Cannot Be Acted Upon Project stage: Approval ML20204G4801986-07-31031 July 1986 Informs That 860710 Request for Delay of Submittal of Integrated Sys Study Until 860815 Acceptable.Revised Listing of Commitments,Updated to Reflect Completion of Items 11 & 16b,encl Project stage: Other ML0311502641986-08-20020 August 1986 Withdrawn NRC Generic Letter 1986-014: Operator Licensing Examinations Project stage: Request ML20212N4761986-08-26026 August 1986 Safety Evaluation Approving Licensee 850401 Exemption Request from Requirements in 10CFR50,App R,Section Iii.J Re Emergency Lighting Project stage: Approval ML20212N4711986-08-26026 August 1986 Forwards Safety Evaluation Approving Util 850401 Exemption Requests from Requirements in 10CFR50.40 & 10CFR50,App R, Section Iii.J Re Emergency Lighting Project stage: Approval ML20197B7581986-10-16016 October 1986 Notifies of Development of Fire Protection Program Plan at Plant in Accordance W/Requirements of 10CFR50.48(a),per 860314 Commitment.Plan Includes Updated Fire Hazards Analysis for Each Plant Fire Area 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 ML20214G1091986-11-18018 November 1986 Forwards Draft Fire Protection Safety Evaluation Supporting Util 850401 Request for Exemption from 10CFR50,App R Requirements & Proposed Safe Shutdown Sys.Status Rept on Listed Items & Comments Re Draft Evaluation Requested Project stage: Draft Approval ML20214G1411986-11-18018 November 1986 Draft Safety Evaluation Supporting Util 850401 Request for Exemption from 10CFR50,App R Requirements Re Fire Protection & Proposed Safe Shutdown Sys.Related Info Encl Project stage: Draft Approval ML20214P2551986-11-20020 November 1986 Forwards Updated & Condensed Version of Const Schedule for Proposed App R Mods,Per Request Project stage: Other ML20207E0301986-12-29029 December 1986 Forwards Corrected Schedule of Proposed App R Mods Noted in .Mod Re Emergency Lighting Will Be Completed,As Discussed in 860826 Ser,Within 12 Months Following NRC Approval Project stage: Other ML20235J4001987-01-16016 January 1987 Forwards Comments on Draft Fire Protection SER Project stage: Draft Other ML20209C2321987-01-23023 January 1987 Advises Util to Complete App R Mods to Facility Expeditiously.Staff Considers Dates in 861120 & 1229 Ltrs as Commitments.Nrc Considering Rev to Listing of Util Commitments Re Operation of Facility Project stage: Other IR 05000267/19870011987-02-27027 February 1987 Insp Rept 50-267/87-01 on 870202-06.No Violations or Deviations Identified.Major Areas Inspected:Fire Protection/Prevention Program & Implementation Project stage: Request ML20207Q9131987-02-27027 February 1987 Requests Concurrence to Reduce Roving Fire Watch,Committed to in Util ,To Hourly Fire Watch for Turbine Water Removal Pumps Effective on 870325.New Fire Detection Sys Described in Util Installed Project stage: Other ML20206B1821987-04-0202 April 1987 Advises That Util 870227 Request to Reduce Level of Roving Fire Watches,Acceptable.Maintain Hourly Fire Watch in Current Turbine Water Removal Pumps.Change May Be Implemented Upon Completion of New Fire Protection Sys Project stage: Other ML20214P2731987-05-15015 May 1987 Forwards Revs to App R Evaluations for Shutdown Model, Electrical Reviews, Fire Protection Reviews & Exemptions & Mods, to Show Consistency W/Safe Shutdown Trains Project stage: Other ML20214U7311987-06-0101 June 1987 Requests Exemption from 10CFR50,App R Requirements,Except Sections Iii.G & Iii.J Under 10CFR50.12,establishing Unambiguous Regulatory Criteria for High Temp Gas Cooled Reactor.History of Correspondence on Issue Encl Project stage: Other 1985-09-03
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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
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Text
_ _ - - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _
je b UNITED STATES
- n NUCLEAR REGULATORY COMMISSION
- h. -,$ WASHINGTON, D. C. 20555 e
0 ,
Enclosure SAFETY EVALUATION CONCERNING APPENDIX R EXEMPTION REQUESTS PLANT ELECTRICAL, INSTRUMENTATION, AND CONTROL SYSTEMS BRANCH FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET N0. 50-267 1 l
l
1.0 INTRODUCTION
By letter dated April 1, 1985, the licensee submitted Appendix R Evaluation Report No. 4, which contained exemption requests and i proposed fire protection and systems-related modifications. Eleven I exemptions from the technical requirements of Section III.G. and one I exemption from Section III.J. of Appendix R to 10 CFR 50 were '
requested. This evaluation only discusses one of those requests concerning emergency lighting. l 2.0 EXEMPTION REQUESTED l' The licensee requested an exemption from the technical requirements of Section III.J of Appendix R to 10 CFR 50 to the extent that it
.; requires emergency lights to be powered by individual 8-hour battery
- l packs.
3.0 DISCUSSION The plant is presently equipped with hard-wired, essential / emergency back-up lighting systems powered from the standby diesel generators ,
and the plant DC system. However, these systems are not sufficiently I independent such that they would be available in the event of fire. !
1 In Appendix R Evaluation Report No. 4, the licensee committed to l install a new system for the Reactor and Turbine Buildings. Outlying I
- structures requiring access for safe shutdown functions that are not ,
l covered by ACM powered light will be covered by 8-hour battery l lights. The new emergency lighting system will have the following !
attributes:
- 1. Wiring and lights ecnfigured such that multiple physically separate systems would result with each e 4cem covering a zone or -
qua hant. Lighting equipment in each zone will be separated by a minimum of 30 feet from that of another zone. Loss of any one zone due to a postulated fire would be compensated for by the lights in the adjacent zones, including permanently installed but movable " extension lights" where necessary; 8608280247 860826 PDR ADOCK 05000267 F PDR
- 2. Separate and independent power feeds for each zone covered;
- 3. Electrical power supplied from the ACM diescl;
- 4. Breaker coordination such that only one circuit would fail given the loss of any one individual light unit, or a single fault such as due to a fire;
- 5. A minimal number of lights per circuit so that the lighting availability loss would be minimized given a circuit loss;
- 6. A mix of local area lights and spot flood beams plus extension lights where necessary;
- 7. Receive a field check /walkdown to confirm adequate numbers, locations, and positioning of lights. -
i Essential valves or equipment components requiring manual operator ,
action (s) would be covered by local zone lighting plus spot beams from l adjacent zones. Therefore, if a fire failed the lectl circuit, the .
spot beams from a distance greater than 30 feet would still be functional. In addition, extension lights will be available in selected areas where valves are located in upper galleries.
l The licensee justifies this exemption on the bases that the proposed 4
new lighting system provides an equivalent level of emergency lighting as individual 8-hour battery packs.
4.0 EVALUATION l
The technical requirements of Section III.J are not met in the Reactor !
and Turbine Buildings because the new emergency lights are not powered !
by individual 8-hour batteries. -
We had two concerns with the proposed emergency lighting system in these buildings. The first was that a sufficient number of lights would not be installed so as provide an adequate level of illumination. However, all essential valves and equipment components requiring manual operator actions, and access and egress routes thereto, will be covered by the local zone lighting plus spot beams from adjacent zones. In addition, at our request, the licensee in kepcrt No. 4, comitted to verify the adequacy of the illumination by conducting a field walkdown with plant operators to confirm the adequacy of the numbers, locations and positioning of the lights.
The second concern was that a fire could damage the power supply to the emergency lighting. However, the new system is designed in such a manner that a fire in any one zone would not affect the emergency lighting in adjacent zones. Therefore, individual 8-hour batteries for each emergency light are not necessary to provide us with reasonable assurance that sufficient emergency lighting would be available to complete safe shutdown functions. ~
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5.0 CONCLUSION
Based on our evaluation, we concludd that the licensee's alternate configuration will achieve an acceptable level of safety, equivalent to that achieved by compliance with Section III.J. Therefore, the licensee's request for exemption for individual 8-hour battery powered emergency lighting in the Reactor and Turbine Buildings should be granted.
Principal Contributor: D. Kubicki, DPWRL-8/PEICSB Dated: August 26, 1986 e
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