Letter Sequence Other |
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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:CORRESPONDENCE-LETTERS
MONTHYEARML20205G8771999-03-26026 March 1999 Forwards Copy of Cover Page from Fort St-Vrain Welding Manual,Which Had Been Listed as Encl on Page 4 of 990325 Reply to EA 98-081.Cover Page Had Been Inadvertently Left Out with Original Reply ML20197H8811998-12-0101 December 1998 Forwards Proposed Change to Fsv ISFSI Physical Protection Plan in Which Commitment Is Made to Provide Feature to Security Posture for Facility ML20236R9191998-07-20020 July 1998 Ltr Contract:Mod 4 to Task Order 27, Task Area No 4 of Basic Contract - Fort St Vrain Insp Under Contract NRC-02-95-003 ML20199H8141997-11-21021 November 1997 Responds to Requesting Clarification as to Whether Increase in Tritium & Iron-55 Contamination Limits That Were Approved for Plant Apply to All Licensees ML20198K1931997-10-10010 October 1997 Provides Supplemental Info in Support of Util Proposed Rev to Physical Security Plan for Plant Plant Isfsi.Plan Withheld,Per 10CFR2.790(d) & 10CFR73.21 ML20198H5601997-09-16016 September 1997 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20141F3521997-05-14014 May 1997 Forwards Proposed Issue 4 of Physical Security Plan for Fort St Vrain ISFSI for Review & Approval.Encl Withheld,Per 10CFR2.790(d) ML20141C8611997-05-0909 May 1997 Informs of Approval of Fsv Final Survey Rept & Effluent Pathway Survey Plan & Supporting Analysis ML20141K9881997-05-0505 May 1997 Forwards Amend 89 to License DPR-34 & Supporting Safety Evaluation.Amend Designates All Elements of Approved Decommissioning Plan as License Termination Plan ML20138G2701997-04-28028 April 1997 Provides Response to NRC Comments Re Proposed Sampling & Survey Plan for Fsv Effluent Pathway.Response Documents Fsv Liquid Effluent Discharge Pathway Areas Are Acceptable for Release for Unrestricted Use IAW Draft NUREG/CR-5849 ML20148D4651997-04-24024 April 1997 Forwards Revised Interim Ltr Rept Which Describes Procedures & Results of Confirmatory Survey of Group E Effluent Discharge Pathway Areas at Fsv Station NUREG/CR-5849, Requests That Licensee Provide Evidence That Average Contamination Levels in Group E Effluent Discharge Pathway Areas Meet Averaging Criteria in Draft NUREG/CR-58491997-04-23023 April 1997 Requests That Licensee Provide Evidence That Average Contamination Levels in Group E Effluent Discharge Pathway Areas Meet Averaging Criteria in Draft NUREG/CR-5849 ML20138B0511997-04-22022 April 1997 Forwards Copy of Proposed Amend to Fsv NPDES Permit, Wastewater Discharge Permit CO-0001121 Requested to Support Repowering Activities,Iaw Section 3.2.d of Fsv Non-Radiological Ts,App B to License DPR-34 ML20140E1061997-04-10010 April 1997 Forwards Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20137S4481997-04-0808 April 1997 Informs That Decommissioning Activities at Fsv Are Complete & NRC Issued Exemption from Requirements of 10CFR50.54(w) in .Property Damage Insurance Policy Is Maintaned to Protect Fsv balance-of-plant Assets ML20137S0821997-04-0707 April 1997 Forwards Insp Rept 50-267/97-01 on 970310-11.No Violations Noted ML20137S1691997-04-0707 April 1997 Fifth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App K ML20137S5421997-04-0707 April 1997 Forwards Final Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Fort St Vrain Nuclear Station ML20148D5951997-04-0404 April 1997 Forwards Confirmatory Survey for Fsv Nuclear Station, Psc,Platteville,Co, Final Rept ML20137R6921997-04-0404 April 1997 Informs of Approval for Request for Addl 45 Days to Remedy Deficiencies Identified in NRC Re Financial Assurance Mechanism for Fsv Decommissioning Costs ML20137J8051997-03-31031 March 1997 Third Partial Response to FOIA Request for Documents.Records in App F Encl & Will Be Available in Pdr.App G & H Records Withheld in Part (Ref FOIA Exemptions 5 & 7) ML20148D5811997-03-26026 March 1997 Forwards Confirmatory Survey Plan for Group E Effluent Discharge Pathway Areas at Fsv Nuclear Station, Covered in Final Survey Rept,Vol 6 ML20137G7361997-03-25025 March 1997 Requests Addl Time for Util to Respond to NRC Comments in Re Financial Assurance Mechanism for Fort St Vrain Decommissioning Costs ML20137G9521997-03-24024 March 1997 Forwards Quarterly 10CFR50.59 Rept for Period 961201-970228 Re Changes,Tests & Experiments for Fort St Vrain Decommissioning ML20137H1131997-03-24024 March 1997 Second Partial Response to FOIA Request for Documents. Forwards Documents Listed in App D.Documents Also Available in Pdr.Documents Listed in App E Withheld in Part (Ref FOIA Exemption 6) ML20137C0181997-03-18018 March 1997 Documents That No Personnel Has Received Radiation Exposure at Fsv in 1997 or at Any Time Subsequent to ML20137C0061997-03-18018 March 1997 Documents That There Have Been No Activities Involving Release of Radioactive Matls from Fsv Nuclear Station That Potentially Could Have Affected Environ,Subsequent to Previous Radiological Envion Operating Rept ML20136G1201997-03-11011 March 1997 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1996 & Jan-Mar 1997. All Effluent Releases Completed as of 960703.Repts on Activities After 960703 Reflect Disposal of Solid Waste ML20136B1331997-02-28028 February 1997 First Partial Response to FOIA Request for Documents. Documents Listed in App a Already Available in Pdr.Forwards App B Documents.App C Documents Being Withheld in Entirety (Ref FOIA Exemption 5) ML20135D7891997-02-27027 February 1997 Forwards Responses to Comments Re Fort St Vrain Final Survey Rept ML20135D9531997-02-27027 February 1997 Forwards Copy of Amend to Util Npdes,Wastewater Discharge Permit CO-0001121,which Clarifies That Monitoring of Farm Pond Outlet Required When Industrial Wastewater Being Discharged Through Upstream Goosequill Ditch ML20135A8711997-02-14014 February 1997 Requests That Encl Deficiencies Identified in Financial Assurance Mechanism for Fort St Vrain Decommissioning Cost Be Addressed within 45 Days ML20134D1551997-01-31031 January 1997 Forwards Util Responses to NRC Comments Provided in NRC Ltr Re Sampling & Survey Plan Used for Final Radiological Survey of Liquid Effluent Pathway at Ft St Vrain ML20134C8481997-01-30030 January 1997 Forwards Draft Confirmatory Survey Rept for Fsv Nuclear Station,Psc,Platteville,Co Providing Info on Essap Activities on 960930-1003 ML20133L4961997-01-0707 January 1997 Forwards Comments That Need to Be Resolved Before Final Approval of Util Submittal Entitled, Proposed Sampling & Survey Plan for Effluent Pathway,Ft St Vrain Final Survey Program ML20133E0481997-01-0202 January 1997 Forwards Comments to Fsv Nuclear Station, Decommissioning Project Final Survey Rept (Volumes 4-11), for Consideration ML20132G0421996-12-23023 December 1996 Forwards Insp Rept 50-267/96-05 on 961203-05.No Violations Noted ML20132F2841996-12-19019 December 1996 Forwards Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Plant,Covering Period of 960901-1130 ML20133A8591996-12-16016 December 1996 Forwards Original & Copy Transcripts of Public Hearing,Held on 961203 in Platteville,Co Re Decommissioning & License Termination of Util Ft Saint Vrain Nuclear Generating Station ML20133N0011996-12-0404 December 1996 Recommends That NRC Require License to Modify Submission of Unexecuted Draft Trust Agreement Remaining Decommissioning Costs for Ft St Vrain Nuclear Generating Station in Listed Ways ML20135B3861996-11-25025 November 1996 Informs That NRC Reviewed Util 961114 Submittal (P-96096) Entitled, Fort St Vrain Final Emergency Response Plan, & Meets Requirements of 10CFR50.54(q) ML20135A5861996-11-25025 November 1996 Submits Suppl Info Re Annual Environ Rept for 1995 Operation of Fsv ISFSI ML20135A6361996-11-20020 November 1996 Submits Copy of Describing Discharge Practices for Groundwater Seeping Into Fsv'S Reactor Building Sump ML20134L4721996-11-14014 November 1996 Notifies NRC That Util Adopted Fsv ISFSI Emergency Response Plan to Direct Emergency Response for Radiological Accidents Occuring at Site,Until 10CFR50 License Is Terminated ML20134F4351996-10-30030 October 1996 Forwards Sections 1,2,6 & 8 from Survey Packages F0015, F0039 & F0126 & Sections 1,2 & 6 from Survey Package F0115 to Support on-site NRC Insp ML20134G5991996-10-30030 October 1996 Forwards Volumes 1-12 to Final Survey Rept for Groups A,B,C Rev 1,D Rev 1,E,F Rev 1 & G-J for NRC Approval in Support of Forthcoming Request for Termination of Fsv 10CFR50 License ML20133D7691996-10-22022 October 1996 Forwards Preliminary Rept Re Orise Support of NRC License Insp at Fsv on 960930-1003 ML20136B1411996-10-15015 October 1996 FOIA Request for Documents Re NOV Addressed to Scientific Ecology Group Re NRC Insp Rept 50-267/94-03 & OI Investigation Repts 4-94-010 & 4-95-015 ML20128M6181996-10-0404 October 1996 Forwards Ltr from PSC to Co Dept of Public Health & Environ Describing Monitoring Practices at Plant ML20128G8041996-10-0101 October 1996 Forwards Fsv Decommissioning Fire Protection Plan Update 1999-03-26
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20205G8771999-03-26026 March 1999 Forwards Copy of Cover Page from Fort St-Vrain Welding Manual,Which Had Been Listed as Encl on Page 4 of 990325 Reply to EA 98-081.Cover Page Had Been Inadvertently Left Out with Original Reply ML20197H8811998-12-0101 December 1998 Forwards Proposed Change to Fsv ISFSI Physical Protection Plan in Which Commitment Is Made to Provide Feature to Security Posture for Facility ML20198K1931997-10-10010 October 1997 Provides Supplemental Info in Support of Util Proposed Rev to Physical Security Plan for Plant Plant Isfsi.Plan Withheld,Per 10CFR2.790(d) & 10CFR73.21 ML20141F3521997-05-14014 May 1997 Forwards Proposed Issue 4 of Physical Security Plan for Fort St Vrain ISFSI for Review & Approval.Encl Withheld,Per 10CFR2.790(d) ML20138G2701997-04-28028 April 1997 Provides Response to NRC Comments Re Proposed Sampling & Survey Plan for Fsv Effluent Pathway.Response Documents Fsv Liquid Effluent Discharge Pathway Areas Are Acceptable for Release for Unrestricted Use IAW Draft NUREG/CR-5849 ML20148D4651997-04-24024 April 1997 Forwards Revised Interim Ltr Rept Which Describes Procedures & Results of Confirmatory Survey of Group E Effluent Discharge Pathway Areas at Fsv Station ML20138B0511997-04-22022 April 1997 Forwards Copy of Proposed Amend to Fsv NPDES Permit, Wastewater Discharge Permit CO-0001121 Requested to Support Repowering Activities,Iaw Section 3.2.d of Fsv Non-Radiological Ts,App B to License DPR-34 ML20140E1061997-04-10010 April 1997 Forwards Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20137S4481997-04-0808 April 1997 Informs That Decommissioning Activities at Fsv Are Complete & NRC Issued Exemption from Requirements of 10CFR50.54(w) in .Property Damage Insurance Policy Is Maintaned to Protect Fsv balance-of-plant Assets ML20137S5421997-04-0707 April 1997 Forwards Final Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Fort St Vrain Nuclear Station ML20148D5951997-04-0404 April 1997 Forwards Confirmatory Survey for Fsv Nuclear Station, Psc,Platteville,Co, Final Rept ML20148D5811997-03-26026 March 1997 Forwards Confirmatory Survey Plan for Group E Effluent Discharge Pathway Areas at Fsv Nuclear Station, Covered in Final Survey Rept,Vol 6 ML20137G7361997-03-25025 March 1997 Requests Addl Time for Util to Respond to NRC Comments in Re Financial Assurance Mechanism for Fort St Vrain Decommissioning Costs ML20137G9521997-03-24024 March 1997 Forwards Quarterly 10CFR50.59 Rept for Period 961201-970228 Re Changes,Tests & Experiments for Fort St Vrain Decommissioning ML20137C0061997-03-18018 March 1997 Documents That There Have Been No Activities Involving Release of Radioactive Matls from Fsv Nuclear Station That Potentially Could Have Affected Environ,Subsequent to Previous Radiological Envion Operating Rept ML20137C0181997-03-18018 March 1997 Documents That No Personnel Has Received Radiation Exposure at Fsv in 1997 or at Any Time Subsequent to ML20136G1201997-03-11011 March 1997 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1996 & Jan-Mar 1997. All Effluent Releases Completed as of 960703.Repts on Activities After 960703 Reflect Disposal of Solid Waste ML20135D7891997-02-27027 February 1997 Forwards Responses to Comments Re Fort St Vrain Final Survey Rept ML20135D9531997-02-27027 February 1997 Forwards Copy of Amend to Util Npdes,Wastewater Discharge Permit CO-0001121,which Clarifies That Monitoring of Farm Pond Outlet Required When Industrial Wastewater Being Discharged Through Upstream Goosequill Ditch ML20134D1551997-01-31031 January 1997 Forwards Util Responses to NRC Comments Provided in NRC Ltr Re Sampling & Survey Plan Used for Final Radiological Survey of Liquid Effluent Pathway at Ft St Vrain ML20134C8481997-01-30030 January 1997 Forwards Draft Confirmatory Survey Rept for Fsv Nuclear Station,Psc,Platteville,Co Providing Info on Essap Activities on 960930-1003 ML20133E0481997-01-0202 January 1997 Forwards Comments to Fsv Nuclear Station, Decommissioning Project Final Survey Rept (Volumes 4-11), for Consideration ML20132F2841996-12-19019 December 1996 Forwards Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Plant,Covering Period of 960901-1130 ML20133A8591996-12-16016 December 1996 Forwards Original & Copy Transcripts of Public Hearing,Held on 961203 in Platteville,Co Re Decommissioning & License Termination of Util Ft Saint Vrain Nuclear Generating Station ML20133N0011996-12-0404 December 1996 Recommends That NRC Require License to Modify Submission of Unexecuted Draft Trust Agreement Remaining Decommissioning Costs for Ft St Vrain Nuclear Generating Station in Listed Ways ML20135A5861996-11-25025 November 1996 Submits Suppl Info Re Annual Environ Rept for 1995 Operation of Fsv ISFSI ML20135A6361996-11-20020 November 1996 Submits Copy of Describing Discharge Practices for Groundwater Seeping Into Fsv'S Reactor Building Sump ML20134L4721996-11-14014 November 1996 Notifies NRC That Util Adopted Fsv ISFSI Emergency Response Plan to Direct Emergency Response for Radiological Accidents Occuring at Site,Until 10CFR50 License Is Terminated ML20134F4351996-10-30030 October 1996 Forwards Sections 1,2,6 & 8 from Survey Packages F0015, F0039 & F0126 & Sections 1,2 & 6 from Survey Package F0115 to Support on-site NRC Insp ML20134G5991996-10-30030 October 1996 Forwards Volumes 1-12 to Final Survey Rept for Groups A,B,C Rev 1,D Rev 1,E,F Rev 1 & G-J for NRC Approval in Support of Forthcoming Request for Termination of Fsv 10CFR50 License ML20133D7691996-10-22022 October 1996 Forwards Preliminary Rept Re Orise Support of NRC License Insp at Fsv on 960930-1003 ML20136B1411996-10-15015 October 1996 FOIA Request for Documents Re NOV Addressed to Scientific Ecology Group Re NRC Insp Rept 50-267/94-03 & OI Investigation Repts 4-94-010 & 4-95-015 ML20128M6181996-10-0404 October 1996 Forwards Ltr from PSC to Co Dept of Public Health & Environ Describing Monitoring Practices at Plant ML20128G8041996-10-0101 October 1996 Forwards Fsv Decommissioning Fire Protection Plan Update ML20128G0481996-09-30030 September 1996 Submits Rev to Psco Definitions of Contents of Documentation Packages Re Fsv Final Survey Project ML20129C0421996-09-20020 September 1996 Forwards Quarterly Submittal of 10CFR50.59 Rept of Changes, Tests & Experiments for Facility Decommissioning,Covering Period of 960601-0831 ML20133D7601996-09-16016 September 1996 Forwards Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project,First Final Survey Rept Submittal- Vols 1-5.NRC Comments Incorporated.Spending Plan Attached ML20117P0711996-09-13013 September 1996 Describes Util Plans to Remove Bldg 28 from Plant Facility ML20129A4431996-09-11011 September 1996 Describes Util Plans for Demonstrating That Liquid Effluent Pathway & Surrounding Open Land Areas Satisfy 10 Mrem/Yr Criteria Provided in Plant Final Survey Plan ML20117K5291996-09-0404 September 1996 Provides Notification That Util Will Be Revising Financial Assurance Mechanism That Will Be Used to Cover Remaining Costs of Decommissioning Plant ML20117C7281996-08-22022 August 1996 Discusses Impact of Final Decommissioning Rule & Requests NRC Concurrence That Requirements to Submit & Obtain Approval of License Termination Plan Have Been Satisfied ML20116P3431996-08-16016 August 1996 Describes Actions to Remove Structures & Equipment Items from Fort St Vrain Facility for NRC Info.Requests That NRC Advise Util of Wishes to Perform Confirmatory Survey of Any Parts of New Fuel Storage Building Before 960903 ML20133D7551996-08-14014 August 1996 Provides Environ Survey & Site Assessment Program'S (Essap) Comments Re Review of Fsv Nuclear Station Decommissioning Project Final Survey Rept ML20116M0771996-08-14014 August 1996 Provides Suppl Response to Re Insp Rept 50-267/96-01 in Jan 1996 Re NRC Concerns About Fsv Final Survey Program.Specifically,Bias in Instrumentation Response Overestimating Amount of Contamination Present ML20116M1841996-08-13013 August 1996 Forwards Util Responses to NRC Comments in Re Use of in-situ Gamma Spectroscopy to Measure Exposure Rates During Plant Final Survey.Approval to Use in-situ Gamma Spectroscopic instrument,Microspec-2,requested ML20116K0061996-08-0909 August 1996 Submits Fort St Vrain Nuclear Station Decommissioning Project Final Survey Rept ML20116M1241996-08-0808 August 1996 Responds to NRC Bulletin 96-004, Chemical,Galvanic,Or Other Reactions in Spent Fuel Storage & Transportation. Informs That Modular Vault Dry Storage Sys Is Not Susceptible to Problems Addressed in Bulletin ML20116F3611996-08-0202 August 1996 Submits Revised Documentation for Fort St Vrain Final Survey Program ML20116F8141996-08-0202 August 1996 Informs of Util Intent to Modify Fort St Vrain Control Room,Which Will Make Certain Final Survey Locations Unavailable for Further Review.Final Survey Efforts Are Complete ML20116A4511996-07-19019 July 1996 Requests NRC Approval of Proposed Method to Fsv Final Survey Plan to Determine Exposure Rates in Prestressed Concrete Reactor Vessel 1999-03-26
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059H9471990-09-14014 September 1990 Forwards Rev to Proposed Physical Security Plan,Per .Encl Withheld (Ref 10CFR73.21) ML20064A6841990-09-14014 September 1990 Notifies That Ms Frazier License OP-5608-1 Terminated Effective 900906,per 10CFR50.74 ML20059K2091990-09-14014 September 1990 Requests That Dj Trumblee Reactor Operator License Be Terminated,Effective 900912 ML20059L5831990-09-14014 September 1990 Forwards Application for Amend to License DPR-34,changing Tech Spec Design Features Section to Remove CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20059D3231990-08-15015 August 1990 Forwards fitness-for-duty Performance Data Rept for Plant ML20058N5661990-08-0808 August 1990 Requests Exemption from 10CFR50.54(w)(1) Requirements for Min Property Insurance Coverage ML20058L8031990-08-0303 August 1990 Forwards GA-C18103, Fort St Vrain Cycle 3 Core Performance, Per Request for Addl Info Re Proposed Amend to Tech Spec Which Would Allow Util to Complete Defueling of Facility ML20058M1931990-07-31031 July 1990 Advises of Termination of Kj Einig Reactor Operator License, Effective 900727 ML20056A1791990-07-30030 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-267/90-07.Corrective Actions:Electrical & Mechanical Craft Personnel Assigned to Planning & Scheduling Organization ML20055H8091990-07-23023 July 1990 Forwards Addl Info in Support of 900622 SAR for Isfsi. Proprietary SAR Withheld (Ref 10CFR2.790) ML20056A1711990-07-20020 July 1990 Discusses Decommissioning Funding for Plant.Util Revised Decommissioning Financial Plan,Based on Safstor,Currently in Effect & Funds Will Be Accumulated Per Plan Provisions ML20055H6571990-07-20020 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Model 1153 or 1154 Transmitters Presently in Use at Plant ML20058P6891990-07-20020 July 1990 Forwards Security Plan for Proposed ISFSI for NRC Review,Per 900622 & 0412 Ltrs.Plan Withheld (Ref 10CFR73.21) ML20055G8601990-07-20020 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-267/90-07.Corrective Actions:Site Mgt Recognized Applicability of 10CFR50.72(b)(2)(vi) Re Previous Day Notification & Immediately Notified NRC ML20055H2811990-07-20020 July 1990 Forwards Rev 4 to Updated Fire Protection Plan ML20055G7061990-07-20020 July 1990 Forwards Application for Amend to License DPR-34,revising Tech Spec 6.1 to Remove Equipment to Support Plant Closure ML20059D1361990-07-13013 July 1990 Applies for Exemption from Payment of Annual Fees for FY90, Per 10CFR171 ML20055E0401990-07-0303 July 1990 Forwards Issue 3 to FPOR-18, Fire Protection Operability Requirements, as Result of Rev 3 to Facility Fire Protection Plan ML20055E0331990-07-0202 July 1990 Informs of Plans to Remove B Helium Circulator from Plant Prestressed Concrete Reactor Vessel in Mannner Similar to Previous Circulator Maint Outages.Requests Timely Ack of NRC Concurrence W/Undertaking ML20055E9171990-06-29029 June 1990 Resubmits Semiannual Radioactive Effluent Release Rept Jul-Dec 1989, as Result of Omitted Tables ML20044A8281990-06-29029 June 1990 Notifies of Termination of Wj Ashmore,License SOP-43244 & Requests That Reactor Operator License Be Terminated Effective 900620,per 10CFR50.74 ML20055D3931990-06-29029 June 1990 Forwards Response to Generic Ltr 90-04,requesting Info on Status of Generic Safety Issues.W/O Encl ML20055D1591990-06-22022 June 1990 Forwards Proposed Change to Updated Fsar,App B Re Use of Controls Other than Change Notice Sys to Implement Mods Such as Cutting & Capping of Piping,In Order to Obtain Positive Equipment Isolation ML20043J0581990-06-15015 June 1990 Forwards Proposed Issue 5 to Fort St Vrain Nuclear Generating Station Defueling Emergency Response Plan, Deleting Offsite Emergency Response Capabilities,Per Util 890816 Defueling SAR & NUREG-0654 ML20043D3291990-05-25025 May 1990 Forwards Response to NRC 900330 Ltr Re Violations Noted in Insp Rept 50-267/90-04.Encl Withheld (Ref 10CFR73.21) ML20055D2051990-05-25025 May 1990 Responds to Violations Noted in Insp Rept 50-267/90-06. Corrective Actions:Extensive Training on Radiological Emergency Response Plan Implementing Procedures Will Be Provided to Operating Crews Beginning in May 1990 ML20043C8981990-05-25025 May 1990 Responds to NRC 900427 Ltr Re Violations Noted in Insp Rept 50-267/90-05.Corrective Actions:Mgt Will Continue to Stress Requirement for Procedural Compliance on Ongoing Basis ML20043B3691990-05-22022 May 1990 Describes Util Current Plans for Removal of Certain Plant Equipment Items.Components to Be Removed Have No Required Nor Useful Function During Planned or Postulated Remaining Defueling or Shutdown Conditions ML20043A9491990-05-11011 May 1990 Forwards Issue 59 to AOP-K-1, Environ Disturbances - Earthquake. ML20042F9771990-05-0404 May 1990 Forwards Assessment of Possible Sources of Water in Plant Core,Means of Detecting Water in Pcrv & Effects of Water Ingress on Reactivity,For Info ML20042F9011990-05-0101 May 1990 Forwards Conceptual Plan & Cost Estimates for Early Dismantlement of Fort St Vrain Pcrv, Per NRC 900315 Request ML20042E8911990-04-27027 April 1990 Requests 30-day Extension to 900529 to Submit Response to Violations Noted in Insp Rept 50-267/90-04 ML20042F3111990-04-26026 April 1990 Forwards Application to Amend License DPR-34,providing Tech Spec Changes Needed to Complete Defueling ML20012D4711990-03-19019 March 1990 Requests Approval of Encl Exemption Request Allowing Util to Accumulate Decommissioning Funds Beyond Termination of Operations ML20012B7541990-03-0707 March 1990 Informs of Electronic Transfer of Fees on 900307 for Invoice IO547 ML20011F4691990-02-22022 February 1990 Responds to NRC 900116 Ltr Re Violations Noted in Insp Rept 50-267/89-23.Violation Re Fire Doors 13 & 9 Between 480-volt Ac Switchgear Room & Bldg 10 Propped Open on 891129 Disputed.Improved Communications Underway ML20006E7821990-02-15015 February 1990 Forwards Responses to 891004 Questions Re Decommissioning Financial Plan ML20011E8941990-02-0707 February 1990 Responds to 890719 NRC Bulletin 89-002 Re safety-related Anchor/Darling Model S350W Swing Check Valves.Licensee Reviewed Plant Data Base & Design Documents & Concludes That No Anchor/Darling Model S350W Valves Installed at Plant ML20011E7861990-02-0707 February 1990 Forwards Overview of Evaluation on Compliance W/Environ Qualification Regulation (10CFR50.49) During Defueling of Facility.During Defueling,Pcrv Will Be Maintained at Nearly Atmospheric Pressures & Rapid Depressurization Not Possible ML20011E5031990-02-0606 February 1990 Notifies of Termination of Ma Rhoton Employment W/Util, Effective 900206 ML20006D6621990-02-0606 February 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Currently Established Preventive Maint & Tech Spec Surveillance Activities on HXs Remaining in Svc Will Continue ML20006B2091990-01-26026 January 1990 Forwards Fire Operability Requirements 3 & 14,Issues 3 & 4, Respectively,To Fire Protection Program Plan,Section FP.6.1. Changes Cover Halon Sys & Basis & Records Ctr Halon Sys ML20006B7791990-01-25025 January 1990 Forwards Application for Amend to License DPR-34,changing Section 7.1 of Tech Specs.Specifically,Senior Vice President,Nuclear Operations Revised to Vice President, Nuclear Operations & Nuclear Training Manager Revised ML20006A5001990-01-19019 January 1990 Notifies of Util Intent to Bore 10 Concrete Core Drills Into Prestressed Concrete Reactor Vessel Barrel Section at Various Elevations Found Necessary for Decommissioning Planning.Drillings Wil Begin on 900205.Assessment Encl ML20006A5041990-01-19019 January 1990 Responds to NRC 891218 Ltr Re Weaknesses Noted in Insp Rept 50-267/89-22.Corrective Actions:During Power Operations Three Licensed Reactor Operators Will Be Present in Control & Short in Emergency Public Address Sys Repaired ML20005G5001990-01-12012 January 1990 Forwards Approved Proposed Change to NPDES Permit to Use Halocide Product for Microbiological Control in Smaller Cooling Tower ML19354D8581990-01-0505 January 1990 Forwards Safety Assessment of Proposed Changes to Fire Protection Program Plan,Per P Erickson Request.Changes Cover Acceptance Criteria for Shutdown Cooling Following Fire & New Fire Protection Cooldown Trains 1 & 2 ML20005F5531990-01-0303 January 1990 Certifies That Util Has Implemented fitness-for-duty Program Meeting 10CFR26 Requirements ML20005D8921989-12-21021 December 1989 Forwards Proposed Change to Plant NPDES Permit ML19354D7441989-12-0808 December 1989 Requests Relief from Requirements of Generic Ltr 89-10 Re motor-operated Valves Since Plant Permanently Shut Down Since 890818 & Defueling Initiated on 891127 1990-09-14
[Table view] |
Text
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Pa."!h h Public Service ~
2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 July 27, 1987 Fort St. Vrain Unit No. 1 P-87269 U. S. Nuclear Regulatory -Commission ATTN: Document Control Desk Washington, D.C. 20555 Attention: Mr. Jose A. Calvo .
Director, Project Directorate IV I Docket No. 50-267
SUBJECT:
Justification for Penetration Seal Surveillance Requirements !
REFERENCE:
- 1) PSC letter, Warembourg to Calvo, dated 7/02/87 (P-87241) 1
Dear Mr. Calvo:
l I
Per our conversation with Messrs. K. Heitner and 0. Kubicki on July l 22, 1987, we have attached additional information concerning PSC's request to revise / clarify the Fort St. Vrain (FSV). penetration seals' surveillance requirements noted in Reference No. 1. The additional information provided for each group of seals includes:
- the location of the seals
- the criteria to be' applied for surveillance
- the Fire Protection Shutdown /Cooldown equipment. located adjacent to the seals
- the original basis for the seal installation
- the PSC written commitments on the seals
- the applicable NRC approval of the seals j l
With the exception of case 3, the penetration seals in question are not relied upon to serve a safety function and need not be classified and surveillance as " fire barrier penetration seals", as explained below:
- 1. The . seals in the floors of the Reactor and Turbine buildings were not required to comply with the NRC's BTP 9.5-1, Appendix A because of the nature of the'FSV open space. design concept of those buildings. A three hour fire rated seal would be of no use i
oo ERS288n8s%[7 F i l
y l
P-87269 Page 2: 1 July 27, 1987 i next to an open grating or discontinuous. floor. The Fire :
Protection Shutdown /Cooldown Trains and the Alternate. Cooling ;
Method equipment, identified in the FSV Ap~pendix-R. Evaluation, is '
separated by distance and does not rely upon these seals to be . -
intact during or after a fire to perform a safety related fire l barrier function.
- 2. The Access Control. Bay seals are not needed as " fire barrier. !
penetration seals" because _the FSV Appendix R Evaluation considers the entire Turbine Bui.1 ding as a single fire area, except for five specific rooms. These seals could not be relied .
upon in complying with the NRC's BTP 9.5-1, Appendix'A criteria because of the nature of the FSV open space design concept in:the Turbine Building, including the AccessLControl Bay.. A rated fire !
seal in this area would be of no use next to a large. opening. ore _;
open grating floor. The Fire Protection Shutdown /Cooldown Trains i and the Alternate Cooling Method equipment, . i_dentified in the Appendix R Evaluation, is separated by distance and does' not rely upon these seals to be intact during or after a fire to perform a safety related fire barrier function.
I
- 3. The Auxiliary Electrical Equipment Room floor seals will be. i maintained as " gas tight" unrated fire seals. and surveillance' H annually, just as PSC had previously committed to the NRC to do. l
! There is no change in the requirements or classification of these i
! seals. In 1978, the NRC and PSC. agreed that these seals are
" equivalent to a 3-hour fire rating." These seals will remain!as 1
" fire barrier penetration seals" and be surveillance under FSV- ;
Technical Specifications LCO 4.10.4 and SR 5.10.4..- ,
- 4. The Analytical Instrument Room seals will:not be considered'"to be installed between vital plant areas" and will not' be surveillance, since the Reactor Building has been considered as a single fire area in the FSV Appendix-R Evaluation. 'PSC elected to define this room as a separate fire area.in the 1978 Fire Hazards Analysis, but did not need to do so to' comply with the.
NRC's BTP 9.5-1, Appendix A. The Fire Protection Shutdown /Cooldown Trains and the Alternate Cooling Method equipment identified in the Appendix R Evaluation, is separated-by distance and does not rely upon~ these seals to be' intact during or after a fire to perform a safety related fire barrier function.
None of the seals in Cases.1, 2 and 4 are considered to be " fire barrier penetration seals installed between. vital plant areas", nor are they needed "to prevent the spread of a fire from one vital area-
P-87269 Page 3 July 27, 1987 to another", per FSV Technical Specifications LC0 4.10.4 anu SR 5.10.4 and need not irivoke the requirements of the LC0 or be surveillance.
On July 25, 1987, the NRC Resident Inspector, Mr. R. E. Farrell and the PSC Fire Protection Engineer, Mr. G. D. Schmalz, walked down i typical penetrations in the general areas in question, and found that i fire penetration seals in the interior floor and walls would not I affect the safety of Fort St. Vrain during or after a fire.
Therefore, PSC requests NRC approval of the particular penetration. !
seal surveillance requirements as noted above, to clarify the proper {
limits of the FSV Technical Specifications. PSC is presently ;
maintaining hourly fire watches on the above affected areas until NRC d concurrence is received on this request.
If you have any questions concerning this matter, please contact Mr. M. H. Holmes at (303) 480-6960.
1 Very truly yours,
.0 /Y Wm / i D. W. Warembourg Manager Nuclear Engineering Division a
DWW/ RAS:bac CC: Regional Administrator, Region IV ATTN: Mr. J. E. Gagliardo, Chief Reactor Projects Branch Mr. Kenneth Heitner Project Manager, NRR Mr. Dennis Kubicki Fire Protection Engineer Plant System Branch, NRR Mr. R. E. Farrell Senior Resident Inspector Fort St. Vrain
Attachment P-87269 s
Page 1 of 10 la. Location:
Reactor Building floors Seal Criteria:
Seals will not be considered to be vital fire area seals and uill notbesurveillapced.
Equipment Adjacent to Seals:
Train A Fire Protection Shutdown /Cooldown model equipment within the reactor building are spatially separated by minimum 50 ft.
horizontally and 30 ft. vertically, from Train B equipment, except for noted exemptions in the Appendix R Evaluation, Vol. A.
This separation meets the intent of 10 CFR Appendix R Part III. G with no credit for any floor seal in the Reactor Building.
Original Basis for Seals:
Per Sargent and Lundy Standard EA-176, fire stops were installed at selected locations as designated on construction drawings.
Various ones of these locations are now obsolete based upon the Reactor Building open space design and the current definition of fire areas per the FSV Appendix R Evaluation, Vol 3.
1978 Response to BTP 9.5-1, Appendix A:
, The 1978 FSV Response to BTP 9.5-1, Appendix A on page 3-35 I stated:
" Penetrations within the Reactor Building and Turbine Building between fire areas (floor levels) are not sealed by nature of the open space design concept."
1978 Fire Hazards Analysis:
The 1978 Fire Hazards Analysis transmitted to the NRC via Reference 1 states on page 4-7:
"The building is divided into fire areas by floor level.... The open structure design concept employed in the building consists of open steal floor grating, open stairways, and machinery and personnel access openings in walls and floors.... System piping, electrical cable in trays, risers, conduit, and ventilation ducts penetrate the floors (fire areas) and missile barrier l
Attachment P-87269 Page 2 of 10 I
wall (fire zones) without fire stops or ventilation dampers.... Penetrations without fire rated fire stops or fire dampers are considered acceptable, based on consideration of the fire load calculated for each fire area."
NRC Approval:
The seals to be deleted were never reviewed and formally approved l by the NRC.
i 10 CFR 50, Appendix R Analysis:
The FSV Appendix R Evaluation, Volume 3, pages 2-2 and 2-5, considers the reactor building to be one fire a rea , instead of dividing it by floors.
References:
- 1. PSC letter, Fuller to Gammill, dated October 13, 1978 (P-78167)
- 2. PSC letter, Fuller to Gammill, dated November 13, 1978 (P-78182)
- 3. FSV Appendix R Evaluation, Volumes 3 and 4.
- 4. PSC letter, Warembourg to Calvo, dated July 2, 1987 (P-87241)
~
Attachment P-87269 Page 3 of 10 lb. Location:
l- Turbine Building floors Seal Criteria:
Seals will not be considered to be vital fire area seals and will not be surveillance.
Equipment Adjacent to Seals:
1 Train 'A' Fire Protection Shutdown /Cooldown model equipment.within the reactor building are ' spatially separated by minimum 50 ft. 1 horizontally and 30 ft, vertically, from Train B equipment,: I except for noted exemptions in the Appendix R Evaluation, Vol.'4 This separation meets the intent of 10 CFR Appendix R.Part-III. G with no credit for any floor seal in the ' Turbine Building.
Oriainal Basis for Seals:
Per Sargent and Lundy Standard EA-176, fire stops were installed at selected locations as designated on construction' drawings.
Various ones of these locations are now obsolete based upon the Turbine Building open space design and the current definitier of fire areas per the FSV Appendix R Evaluation, Vol 3.
1978 Response to BTP 9.5-1, Appendix A:
The 1978 FSV Response to BTP 9.5-1, Appendix A on page 3-35 stated:
1
" Penetrations within the Reactor Building and Turbine Building between fire areas (floor levels) are not sealed by nature of the open space design concept."
1978 Fire Hazards Analysis:
The 1978 Fire Hazards Analysis, transmitted to the NRC via ,
Reference 1,. states on page 4-32: j "The building is essentially a three-level structure, except for the access. control bay.... Its physical 3 configuration, also similar to the Reactor Building, is.
~
1 an open structure design consisting of open steel floor grating, open stairways, and, except as noted in the {
fire hazards analysis, contains unsegregated machinery areas. The Turbine Building has been divided into fire i
I j
l f
- _ _ _ _ - _ _ --_ O
l 3
Attachment P-87269 Page 4 of 10 areas by levels and by segregated rooms.... As was done I in the Reactor Building, when considering the effects of the design basis fire, consideration was given to safety related equipment and additional combustibles that could be involved based on proximity to the fire i
area concerned."
NRC Approval:
The seals to be deleted were never reviewed and formally approved <
by the NRC. j 10 CFR 50, Appendix R Analysis:
The FSV Appendix R Evaluation, Volume 3, page 2-6 states: ,
l "Except for the five listed areas in Sections 2.2.12 l
thru 2.2.16, the turbine building is considered one fire area and includes the access control bay."
Sections 2.2.12 through 2.2.16 or, pages 2-6 and 2-7 identify the five areas as being:
Diesel Generator Rooms, Auxiliar Reservoir Room, Turbine Lube Oil Clean(y Boiler Room,
/ Dirty) Turbine Storage Lube aOil Room, Hydrogen Storage Room.
References:
I
}
- 1. PSC letter, Fuller to Gammill, dated October 13, 1978 (P-78167)
- 2. PSC letter, Fuller to Gammill, dated November 13, 1978 (P-78182)
- 3. FSV Appendix R Evaluation, Volumes 3 and 4.
- 4. PSC letter, Warembourg to Calvo, dated July 2, 1987 (P-87241) i 1
I l
l 1
)
Attachment P-87269 Page 5 of 10
- 2. Location:
Access Control Bay Floors , Walls and Ceilings on all levels, (only "J" wall seals will be maintained and surveillar,ced) 1 Seal Criteria:
Seals will not be considered to be vital fire area seals and will not be surveillance.
Fire Protection Shutdown /Cooldown Equipment Adjacent to seals:
l "J" Wall Congested Cable Area, Reactor Building Exhaust Filters )
and Fans. 1 i
Original Basis for Seals:
]
The 1978 Fire Hazards Analysis, (Reference 1) 1978 Fire Hazards Analysis j
)
The 1978 Fire Hazards Analysis, transmitted to the NRC via f Reference 1 discusses this fire area on pages 4-33 through 4-36, and states: I q
"....All fire area boundary doors are non-rated steel doors.... The reinforced concrete floor and fabricated steel walls and doors are considered to be of a fire rating greater than the calculated fire load for this i
area. Ducting penetrating these barriers is not fitted with fire dampers, and several unsealed openings are i provided for piping penetrations." '
_NRC Approval:
The seals to be deleted were never reviewed and formally approved by the NRC.
1 l
1 I
l l
i I
l j
Attachment ,
P-87269 Page 6 of 10 10 CFR 50, Appendix R Analysis:
The FSV Appendix R Evaluation, Volume 3, page 2-6 states:
"Except for the five listed areas in Sections 2.2.12 thru 2.2.16, the turbine building is considered one fire area and includes the access control bay."
Sections 2.2.12 through 2.2.16 on pages 2-6 and 2-7 identify the j five areas as being- l l
Diesel Generator Rooms, Auxiliar /
Reservoir Room, Turbine Lube Oil Clean(y Boiler Room,
/ Dirty) Turbine Storage Lube Room and Oil Hydrogen Storage Room.
References:
- 1. PSC letter, Fuller to Gammill, dated November 13, 1978 (P-78182)
- 2. Appendix R Evaluation, Volume 3
- 3. PSC letter, Warembourg to Calvo, dated July 2,1987 (P-87241) l l
t l
i
)
I
_ _ _ _ _ _ _ _ b
m.
. Attachment P-87269 4 Page 7 of 10
- 3. Location: i Auxiliary Electrical Equipment Room Floor l
Seal Criteria.
Seals will be maintained as " gas tight" unrated fire seals and I surveillance annually.
Fire Protection Shutdown /Cooldown Equipment Adjacent to Seals:
480 Volt Switchgear Room equipment including: 480 V switchgear ,
Trains A & B (non ACM) and station battery chargers; Train A and !
B Auxiliary Electrical instrument / control cabinets.
Original Basis for Seals:
}
See references for historical information, as listed below. The '
final basis of these seals may be found in Reference 5, which states:
"PSC maintains that this modification offers a significant improvement to these floor seals that, based on comparison with other floor seal designs that !
have been fire tested, makes the modified floor seal equivalent to a 3-hour fire rating."
}
BTP 9.5-1, Appendix A Analysis- 1 The FSV 1978 Response to BTP 9.5-1, Appendix A transmitted to the NRC via P-78167, states on page 3-65:
"The Fire protection provisions in these areas have ,
been reviewed, upgraded, and approved by the NRC." i NRC Approval: i NRC letter, Denise to Fuller, dated March 31,1978(G-78029), l states:
"We find that the proposed floor penetration seal l design using Dow Corning silicone foam material is an acceptable three hour fire barrier to be used in the Fort St. Vrain three-room complex."
Attachment P-87269 Page 8 of 10 10 CFR 50, Appendix R Analysis:
The FSV Appendix R Evaluation, Volume 3, page 2-5, states:
"Within the three room control building, the three rooms are, in fact, considered by the NRC to be i separate fire areas; however, it is not necessary to evaluate them as being so for the purposes of Appendix R."
The Auxiliary Electric Equipment Room is considered a part of the i congerted cable areas. For major fires in congested cable areas, the Alternate Cooling Method would be used per FSV Appendix R Evaluation, Volume 1, Appendix A (PSC letter to NRC dated August 17, 1984 (P-84281)). '
References:
i
- 1. PSC letter, Walker to Clark, dated June 18, 1976 (P-76135) i
- 2. PSC letter, Walker to Clark, dated August 2,1976 (P-76172)
- 3. PSC letter, Fuller to Denise, dated September 19,1977(P-77194) )
- 4. NRC letter, Denise to Fuller, dated March 31, 1978 (G-78029)
- 5. PSC letter, Fuller to Gammill, dated October 13, 1978 (P-78167)
- 6. PSC letter, Lee to Johnson, dated August 17, 1984 (P-84281)
- 7. PSC letter, Warembourg to Calvo, dated July 2,1987 (P-87241) ]
I
i
' Attachment P-87269 l Page 9 of 10 J
- 4. Location:
J Analytical Instrument Room (Reactor Building Level 7, el. 4829')
Seal Criteria:
Seals will not be considered vital area fire seals and will not I be surveillance. ]
1 Fire Protection Shutdown /Cooldown Equipment Adjacent to Seals:
"J" Wall Congested Cable Area (has detection and suppression). J Reactor Plant Cooling Water Pumps (has detection) {
l Original Basis for Seals:
The 1978 Fire Hazards Analysis, (Reference 1) ]
1 1978 Fire Hazards Analysis The 1978 Fire Hazards Analysis, submittad to the NRC via Reference 1, does not define the Analytical Instrument Room as a separate fire area, but includes it as part of the "PCRV and auxiliary Equipment Area" on page 4-17 through 4-18, which states:
....The Instrumeat Room, enclosed by concrete walls, floor and ceiling, contains no safety related equipment.... Penetrations into the Instrument Room for piping, cable and ventilation ducting are sealed for air tightness. The room is maintained at a small negative pressure relative to Reactor Building pressure."
NRC Approval:
The seals to be deleted were never reviewed and formally approved by the NRC.
i j
Attachment P-87269 Page 10 of 10 10 CFR 50, Appendix R Analysis:
The FSV Appendix R Evaluation, Volume 3, pages 2-2 and 2-5, considers the Reactor Building to be one fire a rea , instead of dividing it by floors, PCRV, etc.
References:
4
- 1. PSC letter, Fuller to Gammill, dated November 13,1978(P-78182) j
- 2. FSV Appendix R Evaluation, Volume 3 l
- 3. PSC Telecopy to Heitner, dated July 8, 1987 l
- 4. PSC letter, Warembourg to Calvo, dated July 2, 1987 (P-87241) l l
1 l
l l
l l
L . . . . _ _ . . . . . - . . . .