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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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hPublic Service ~
2420 W. 26th Avenue, Suite 100D, Denver, Colorado 80211 g;;,$; m ,.
July 14, 1986 Fort St. Vrain Unit No. 1 P-86460 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Mr. H.N. Berkow, Director Standardization and Special Projects Directorate Docket No. 50-267
SUBJECT:
Emergency Response Capabilities Regulatory Guide 1.97
REFERENCES:
- 1) PSC Letter Warembourg to Johnson, dated February 28, 1985 (P-85065)
- 2) NRC Letter Heitner to Walker, dated March 12, 1986 (G-86134)
- 3) PSC Letter Warembourg to Berkow dated May 19, 1986 (P-86378)
- 4) PSC Letter Warembourg !
to Berkow dated 1 June 20, 1986 (P-86435) l
Dear Mr. Berkow:
Reference 1 provided the NRC with Public Service Company's report regarding Regulatory Guide 1.97 (RG 1.97) Instrumentation. Reference 2 identified several open items in an interim report prepared by EG&G 7
e g g 7 2 { g g y $ $ 0 i>
P
P-86460 ,
Page 2 July 14, 1986 Idaho Inc. Due to the integral relationship between RG 1.97 Instrumentation and 10 CFR 50.49 Environmental Qualification (EQ) of Electrical Equipment, the response to these open items has been delayed as indicated in Reference 3 and are provided herein in Attachment 1. The RG 1.97 items that are being upgraded from Category 3 are identified in Attachment 2. The upgraded items are a result of EG&G's comments as well as a review of the High Energy Line Break (HELB) accident in reference to 10CFR50.49. Notes to the table in Attachment 2 identify all the fields and further explains the level of qualification required for each specified accident scenario for the required RG 1.97 items.
As discussed in Reference 4, any RG 1.97 instrumentation upgrade that affects the FSV Master Equipment List (MEL) shall be incorporated into the FSV EQ Program and shall be added to the MEL as it is installed or upgraded per the Fort St. Vrain RG 1.97 implementation schedule (no later than start-up following the fourth refueling).
1 If you have any questions, please' contact Mr. M.H. Holmes at (303) 480-6960.
Very truly yours,
, b W Wuv 2
D.W. Warembourg, Mana r Nuclear Engineering Division DWW/KD:pa Attachments a
t I
Attachment 1 to P-86460 PSC RESPONSE TO EG&G IDAHO, INC.'S PAMI QUESTIONS The following are the responses and the explanations for the exceptions contained in EG&G Idaho, Inc.'s review of PSC's Post Accident Monitoring Instrumentation (PAMI) listing for the Fort St.
Vrain Nuclear Generating Station.
This report is formatted to respond on an item-by-item basis to the thirteen (13) exceptions listed in the " CONCLUSIONS" section of EG&G's report (Section 4, Pages 10 and 11).
- 1. Exception:
Final fission product cleanup system - the licensee should identify the key variable for this instrument group and upgrade the instrumentation for this variable to Category 1 (Section 3.3.2)
Response
Type C variables are those variables that provide information to indicate the potential for being breached or the actual breach of the barriers to fission product release. For light water reactors, these variables are:
(1) fuel cladding; (2) primary coolant pressure boundary, and; (3) containment. The variables at Fort St. Vrain which compare to these three light water reactor variables are:
(1) fuel particle coating . integrity; (2) liner and primary closure integrity, and; (3) PCRV concrete and secondsry closure integrity. The key parameters for these three Fort St. Vrain variables have been identified as Category 1 consistent with RG 1.97. However, since Fort St. Vrain has one additional barrier to fission product release, namely confinement or reactor building, this has also been included. Since this additional group of variables for Fort St. Vrain represents additional margin over these LWR variables, it is considered that upgrade of these three variables (C20, C21 and C22) to Category 2, in addition to the variables for fuel particle coating integrity, liner and primary closure integrity, and PCRV concrete and secondary closure integrity meets or exceeds the intent of RG 1.97.
Attachment 1 to P-86460
- 2. Exception:
Radwaste system - the licensee should verify that all their radwaste systems have appropriate instrumentation (Section 3.3.3)
Response
As stated in Section IV 'of the original submittal, the parameters selected for Fort St. Vrain were based upon a
, detailed analysis of the effects and conditions of the accidents delineated in DBA-1 (Permanent Loss of Forced Circulation), DBA-2 (Rapid Depressurization/ Blowdown), the Max 1aum Credible Accident, or the Loss of Normal Shutdown Cooling as defined in the FSAR. Since none of these accidents involve the radioactive liquid waste system or the radioactive gas waste system, parameters associated with these systems are not required for post accident monitoring and therefore they have not been and need not be included in PAM instrumentation.
- 3. Exception:
i Ventilation system - the licensee should provide Category 2 instrumentation for this variable (Section 3.3.3).
Response
PSC concurs with this recommendation and -will upgrade Variables D-31 (Damper Position for Control Room Emer Air Flow) and D-32 (Reactor Building Vent Exhaust Flow)gency from Category 3 to Category 2.
- 4. Exception:
Power supplies - the licensee should provide Category 2 instrumentation for this variable (Section 3.3.3).
Response
PSC concurs with this recommendation and -will upgrade Variables D-33 (Essential 480V Bus Voltage) D-34 (Essential 480V Bus Current) and D-35 (Essential 125V Bus Voltage) from 4
Category 3 to Category 2.
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Attachment 1 to P-86460
- 5. Exception:
Reserve shutdown system - the licensee should identify the key variable for this instrumentation group and upgrade the instrumentation for this variable to Category 2 (Section 3.3.3).
Response
The key variable for monitoring the proper performance of the Reserve Shutdown System is Bottle Pressure (Variable D-18). Per the recomendation, PSC will upgrade this variable from Category 3 to Category 2.
- 6. Exception:
Reactor plant cooling system - the licensee should identify the key variable for this instrumentation group and upgrade the instrumentation for this variable to Category 2 (Section 3.3.3).
Response
The key variables for monitoring the proper performance of the Reactor Plant Cooling System are PCRV Subheader Flows (D-19) and PCRV Bottom Penetrations, Bottom Head, Barrel and Top Head, Circuit Inlet Header Temperature (D-21). Per the recommendation, these components will be upgraded from Category 3 to Category 2.
- 7. Exception:
Purification cooling water system - the licensee should identify the key variable for this instrumentation group and upgrade the instrumentation for this variable to Category 2 (Section 3.3.3)
Response
The key variable for monitoring the proper performance of Purification Cooling Water System is Purification Coolin Water Heat Exchanger Outlet Temperature (Variable D-23)g .
Per the recommendation, PSC will upgrade this variable from Category 3 to Category 2.
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- 8. Exception:
Helium purification system - the licensee should identify the key variable for this instrumentation group and upgrade the instrumentation for this variable to Category 2 (Section 3.3.3).
Response
The key variables for monitoring the proper performance of the Helium Purification System are Helium Purification Dryer Outlet Temperature (D-26) and Helium Purification Low Temperature Adsorber Outlet Temperature (D-27). Per the recommendation, PSC will upgrade this variable from Category 3 to Category 2.
- 9. Exception:
Nitrogen system - the licensee should identify the key variable for this instrumentation group and upgrade the instrumentation for this variable to Category 2 (Section 3.3.3).
Response
The key variable for monitoring the proper performance of the Nitrogen System is Storage Tank Level (Variable D-30).
Per the recommendation, PSC will upgrade this variable from Category 3 to Category 2.
- 10. Exception:
Steam generator pressure -
the licensee should provide Categ ry 2 instrumentation for this variable (Section 3.3.3 .
Response
PSC concurs with this recommendation and will upgrade Variables D-15 (Steam Generator EES Outlet Pressure) and D-16 (Steam Generator HRH Outlet Pressure) from Category 3 to Category 2.
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Attachm:nt 1 to P-86460
- 11. Exception:
Area radiation - the licensee should. provide the recommended instrumentation for the reactor building (Section 3.3.4).
Response
The attached Enclosure A contains the listing of Area Radiatian Monitors that PSC recommends be added to the PAMI listing to resolve this exception. Enclosure A lists the design information for each of the components added via this Variable E.4a. The range of the refueling floor high range area monitor (RT-93250-14) envelopes the maximum expected radiation level in the area as a result of DBA-2. All other area monitors would be used to help evaluate personnel entry following any accident into areas containing safe shutdown equipment.
- 12. Exception:
Environs radiation and radioactivity - the licensee should provide additional information on the instrumentation supplied for these variables (Section 3.3.4).
Response
Enclosure B contains a list of the various portable radiation monitors that PSC will utilize following the Design Basis Accidents. Note that this instrumentation is designated as Category 3.
- 13. Exception:
Estimation of atmospheric stability - the licensee should install instrumentation with the recommended ran or justify the use of the existing instrumentation (ge Section 3.3.4)
Attachment 1 to P-86460
Response
PSC has previously installed atmospheric stability instrumentation to comply wit.h RG 1.23. The existing temperature differential instrumentation measures the temperature between 10m and 58m with a range of -5 degrees F to +5 degrees F.
RG 1.23 requires that differential temperature instrumentation is capable of adequately measuring temperature changes with height to determine the atmospheric stability per table 1 of RG 1.23. The bounding parameters are listed below.
Stability Pasquill Temperature Change Classification Categories with Height Extremely Unstable A <-1.9 degrees C/100m =
-3.42 degrees F/100m Extremely Stable G > 4.0 degrees C/100m =
7.2 degrees F/100m Considering that the temperature differential measurement is taking place over a vertical tower length of 48m (meters),
this translates into a maximum span of -1.64 degrees F to
+3.46 degrees F. With the appropriate accuracy of +.9 degrees F, the range of -5 degrees F to +5 degrees F is considered adequate.
! ENCLOSURE A AREA RADIATION MONITORS -
FOR POST ACCIDENT MONITORING (VARIABLE E-4a) .
INSTRUMENT CTL ROOM CAT NO RANGE DISPLAY EOF /TSC VARIABLE (NOTE 2) (NOTE 3) (NOTE 4) .(NOTE 5) (NOTE 6) PURPOSE COMMENTS E.4a.1 Rx Plant Exhaust 3 RT-93251-1 .1R to 1E+4R RIS-93251-1 No Verify significant High Range Monitor Filter Rm - Tb releases and local Turbine Building magnitudes E.4a.2 South Stairwell-Rx 3 RT-93252-2 .1 mR to IE+4mR RIS-93252-2 Reactor Building E.4a.3 Mn Ctl Rm-Tb 3 RT-93250-5 .1 mR to 1E+4mR RIS-93250-5 Turbine Building E.4a.4 Gas Waste Filters 3 RT-93251-5 .1 mR to 1E+4mR RIS-93251-5 Reactor Building E.4a.5 South Stairwell-Rx 3 RT-93252-6 .1 mR to IE+4mR RIS-93252-6 Reactor Building E.4a.6 Valve Oper Stat - 3 RT-93251-7 .1 mR to IE+4mR RIS-93251-7 Reactor Building West - Rx E.4a.7 Valve Oper Stat - 3 RT-93252-7 .1 mR to 1E+4mR RIS-93252-7 Reactor Building East - Rx E.4a.8 NE Walkway - Rx 3 RT-93250-8 .1 mR to 1E+4mR RIS-93250-8 Reactor Building E.4a.9 Buffer Hel Dry 3 RT-93251-9 .1 mR to 1E+4mR RIS-93251-9 Reactor Building Stairwell Loop 1 -
Rx E.4a.10 Condensate Demin. - 3 RT-93250-13 .1 mR to IE+4mR RIS-93250-13 Turbine Building Tb-E.4a.11 E. Wall Refueling 2 RT-93250-14 .1 mR to 1E+4R RIS-93250-14 High Range Monitor j Floor - Rx Reactor Building
- Notes apply to original PAM submittal, Reference 1. r3
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ENCLOSURE B-PAMI PORTABLE RADIATION MONITORS INSTRUMENT CTL ROOM CAT NO RANGE DISPLAY EOF /TSC VARIABLE (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE E5 Portable Radiation 3 R0-5 ImR-200R No No Verify significant Instrumentation / R0-7 200R-20,000R No No releases and local Sensors SAM-II 1E-10 to No No magnitudes SE-5 micro Ci/cc Iodine i
i o Notes' apply to original PAM submittal, Reference 1.
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Attachment 2 to P-86460 ATTACHMENT 2 PAMI CATEGORY 2 UPGRADE MATRIX DEFINITION OF FIELDS ITEM N0.: This field lists the variable number for the PAMI parameter as it appears on FSV RG 1.97 PAMI Table.
INSTRUMENT NO.: Self explanatory.
VARIABLE: This field provides the description of the PAMI variable listed.
REQUIRED TO This Field notes ("X") which of the following MONITOR accident (s) that the PAMI variable is required FOLLOWING to monitor:
ACCIDENT (S):
- DBA Design Basis Accident 1
- DBA Design Basis Accident 2
- LNSC - Loss of Normal Shutdown Cooling
- MCA - Maximum Credible Accident
- HELB - High Energy Line Break PLANT This field defines the physical location in the plant in which the SENSOR and CABLE are located:
RB - Reactor Building TB - Turbine Building OS - Outside the RB or TB SWR - Switchgear Room AX - Aux. Electric Room EQ REQUIRED This field denotes the Environmental Qualification FOR MONITORING (EQ) level required (HARSH / MILD) to ensure the ACCIDENT (S): (HARSH / MILD) to ensure the operability of the variable sensor and cable during the accident it is required to monitor. An 'X' in the HARSH column denotes that both the sensor and cable require EQ qualification per 10 CFR 50.49. The word CABLE in the HARSH column denotes mild EQ of the sensor but harsh EQ of the cable.
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Attachment 2 to P-86460 1.97 CATEGORIES: This field notes the requirement to upgrade each Category 3 variable listed to Category 2 per the guidelines contained in Reg. Guide 1.97.
UPGRADE BASIS: This field denotes the basis for the upgrade from Category 3 to Category 2. An X in the KEY VARIABLE column identifies the upgrade resulting from the response to Reference 2. An X in the HARSH ENVIRONMENT column identifies the upgrade based on the need for equipment operability in a harsh environment (for HELB or DBA 2 accidents). In some cases, both columns have an X. ,
NOTE: Variable D37 has been revised from the original PAM
< submittal per Reference 1 as follows:
Control Room Instrument No. Range Display EOF /TSC PT-91141 2000-3500 PSIG PI-91141 NO PT-91142 2000-3500 PSIG PI-91142 N0 I
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PAMI ChTEGORY 2 VARIABM UPGRADES EQ RIQUIRED REQUIRED TO MOKITOR PIJuff FOR MONITORING 1.97 FOLIntrING ACCIDElft(S) IDCATION M MHr(S) CATEGORY UPGIRADE IIASIS ITEM KEY BARSH NO. IIIS11ttBEDrr MO. VARIABLE DBA1 DBA2 IMIC BECA BELB SENSOR ChBIE EARSE MIID WIGIIIAL UPGRADE VARIABIJE EBR4N E3 PT-2409 Reserve Shutdown X RB RB X 3 2 X System Bottle (For D18)
Pressure B4 TE-11101-1,2,3,4 Core Outlet X X X X RB RB X 3 2 X thru Temperature TE-11137-1,2,3,4 M TE-1171 He Circulator X X X X RB RB X 3 2 X thru Inlet Temperature TE-1378 E26 TE-11101-1,2,3,4 Core Outlet X X X X RB RB X 3 2 X thru Temperature TE-11137-1,2,3,4 C2 RT-9301 Reactor Coolant X X X X X RB RB X 3 2 X System Activity C4 TE-11101-1,2,3,4 Core Outlet X X X X RB RB X 3 2 X thru Temperature TE-11137-1,2,3,4 C5 TE-1171 Helium Circulator X X X X RB RB X 3 2 X thru Inlet Temperature TE-1178 N
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i PANI CATEGORY 2 VARIABIR UPGRADES NQ REQUIRED REQUIRED TO NDNITOR PLANT POR NOMITEEtING 1.97 FOLIDWING ACCIDENT (S) IaCATION ACCIDENT (S) CATEGORY UPGRADE BASIS ITEBt REY EARSH NO. INSTRIBEENT NO. VARIABI2 DBA1 DBA2 IMIC BACA HEIA SENSOR CABIA MARSH MIIa ORIGINAL UPGRADE VARIABIE ENVIFM C30 PS-7377-1 thru -20 Louver Position X X RB RB X 3 2 X PS-7382-1 thru -20 via Pressure Indication C21 PT-73335 Reactor Building X X RB RB X 3 2 X PT-73440 Pressure thru PT-73452 C32 PDT-7319-1 Refueling Floor to X X RB RB X 3 2 X thru Ambient Differen-PDT-7319-4 tial Pressure D4 PDT-2147 Bearing Water Surge X X X X RB RB X 3 2 X PDT-2148 Tank to PCRV Differ-ential Pressure D3 LT-21135 Bearing Water Surge X X X X RB RB X 3 2 X LT-21136 Tank Level D6 FT-21833 FT-2184 Bearing Water Flow X X X X RB RB X 3 2 X FT-21853 FT-2186 D8 LT- 4102-1,2 Storage Basin Level X X OS TB Cable X 3 2 X D12 TE-22121 Steam Generator EES X X X X RB RB X 3 2 X TE-22122 Outlet Temperature N
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b PANI CATurzwY 2 VARIAn;2 UFCRADES EQ W RED REQUIRED TO SONITOR PLAarr Pm NOIEITGtING 1.97 POLIEBfING ACCIDBart(S) IDCATION ACCIDIDft(S) CATEGORY UP(HADE BASIS 3T33: KEY HARSS NO. INSTRIBIEIrr MD. VARIABI2 DBA1 DBA2 IMIC IOCR EERIA muuasnR CABIE HARSH MIID MIGIIIAL UFCRADE VARIABIJ: EBfVI N D15 PT-22129-1 Steam Generator EES X X X X RB RB X 3 2 X X PT-22130-1 Outlet Pressure D16 PT-2267 Steam Generator HRH X X X PT-2268 Outlet Pressure D17 LT-4102-1,2 Storage Basin Ievel X X OS TB Cable X 3 2 X D18 PT-2409 Reserve Shutdown X RB RB X 3 2 X System Bottle Pressure D19 36 FTs PCRV Subheader X RB RB X 3 2 X Flows D31 TE-4637-1 PCRV Bottom X RB RB X 3 2 X TE-4638-1 Penetrations Bottom Head, Barrel & Top Head, Circuit Inlet Header Temperature D33 TE-2321-1 Purification X RB RB X 3 2 X TE-2321-2 Cooling Water Heat Exchanger Outlet Temperature N
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2 PANI CATEGORY 2 VARIABIR UPGRADES BQ REQUIRED REQUIRED TO MONITOR FIANT FOR MONITORING 1.97 FOLIONING ACCIDENT (S) IOCATION ACCIDENT (S) CATBGuaY UPGRADE BASIS ITFE KEY BAkSH NO. IMB11t0NENT NO. VARTAP.IR D8A1 DBA2 Ymmr* MCA BEIR SM CABIR MARSE MIID ORIGIMAL UPGItADE VARIABIE ENWIR(MEBPF D36 TE-23105 Helium Purifica- X RB RB X 3 2 X TE-23106 tion Dryer Outlet Temperature D37 TE-2322-3 Helium X RB RB X 3 2 X TE-2322-4 Purification Low Temperature Adsorber Outlet Temperature D29 PT-4229 Service Water Pump X X X X X TB TB X 3 2 X Header Discharge Pressure D30 LT-2519-1 Nitrogen Storage X RB RB X 3 2 X Tank Iavel D31 See Note 9 Damper Position X X X X TB TB X 3 2 X of PAMI for Control Room Submittal Emergency Air Flow D33 FT-7320 Reactor Building X X TB TB X 3 2 X Ventilation Exhaust Flow r+
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4 PANI CATMQ(EtY 2 VARIABIR UPGRADES no RaQUIRED REQUIRED TO BEMiI10R PIJurr FOR N0EITORING 1.97 FOLIDf1NG JWXIIDigrt(S) IDCATION ACCIDEBrt(S) CATEGORY UPGBADE HASIS ITEst REY HARSH NO. IMSTRIBEIBrr 30. VARIABIE DBA1 DBA2 IMIC IER REIA famMM CARIA BARSH MIID MIGIHAL UPGRADE VARIARIA DVIROmegrF D33 PT For Essential 480V Bus X X X X X SWR TB Cable X 3 2 X X EI-9273A Voltage EI-9274 EI-9275A D34 CT For Essential 480V Bus X X X X X TB TB Cable X 3 2 X X II-9244 Current 11-9248 D35 ET-92220 Essential 125V Bus X X X X X SWR AX X 3 2 X ET-92221 Voltage (DC)
D36 PT-8212 Instrument Air X X X X X TB TB X 3 2 X PT-8254 Receiver Pressure D37 PT-91141 Hydraulic Icop X X X X RB RB X 3 2 X PT-91142 Pressure
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