Letter Sequence Meeting |
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Results
Other: ML20082A843, ML20082S949, ML20083F063, ML20084J011, ML20091E302, ML20095A385, ML20125D934, ML20202E952, ML20212G878, ML20214W452, ML20216H730, ML20236U722, ML20237E005
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MONTHYEARML20082A8431983-11-0707 November 1983 RO 83-43:on 831011,util Notified NRC of Various Nonconservative Errors Made in Original Analyses Which Constitute Basis of Tech Spec 4.1.9.GA Technologies Provided Interim Curves Which Corrected Deficiencies Project stage: Other ML20082S9491983-11-30030 November 1983 Forwards Figure for Limiting Condition for Operation 4.1.9-1 Re Circulation Flow/Core Power,To Replace Figure Submitted w/831107 Ltr.Portions of Less Conservative Figure Deleted. Limit Will Be Observed Until Tech Spec Changed Project stage: Other ML20083F0631983-12-15015 December 1983 Proposed Tech Specs Revising Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise Project stage: Other ML20083F0611983-12-15015 December 1983 Application for Amend to License DPR-34,revising Tech Spec Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise,Per Previous Commitments.Class III Amend Fee Encl Project stage: Request ML20086R7281984-02-24024 February 1984 Responds to Request for Addl Info Re Proposed Amend to Limiting Condition for Operation 4.1.9 Re Average Core Temp During Shutdown Project stage: Request ML20084J0111984-04-0606 April 1984 ORNL Assistance in Evaluating Licensing Request - Fsv Limiting Condition for Operation 4.1.9, Monthly Rept for Mar 1984 Project stage: Other ML20091E3021984-05-0909 May 1984 Interim Rept on ORNL Assistance in Evaluating Licensing Request - Amend of Fort St Vrain Reactor Tech Spec Limiting Condition for Operation 4.1.9 Project stage: Other ML20095A3851984-08-14014 August 1984 Forwards Response to ORNL Concerns & Proposal Identified in NRC .Basis for Discussion of Ornl/Util Concerns & Resolution of Issues Delaying Implementation of Revised Limiting Condition for Operation 4.1.9 Discussed Project stage: Other ML20098H1721984-08-21021 August 1984 Provides Replies & Comments to Util Re Tech Spec Limiting Condition for Operation 4.1.9 in Advance of 840823 Meeting W/Util in Arlington,Tx Project stage: Meeting ML20099H7931984-11-20020 November 1984 Submits Addl Info Requested by NRC During 840823 Meeting Re Proposed Amend to Limiting Condition for Operation 4.1.9 Concerning Automated Orifice Valve Adjustments.Work Continuing on Listed Remaining Issues Project stage: Meeting ML20125D9341985-05-20020 May 1985 Submits Current Status of Work on Tech Spec Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise. Calculational Differences Between Thermal/Hydraulic Analyses Being Investigated.Summary of Open Items Provided Project stage: Other ML20133K6751985-10-17017 October 1985 Notifies That Draft Proposed Rev to Tech Spec Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise Will Be Submitted for Review by 851122 Project stage: Draft Other ML20137E4941985-11-22022 November 1985 Forwards Draft Rev to Tech Spec Limiting Condition for Operation 4.1.9 Re Min Helium Flow/Core Region Temp Rise for Review.Formal Request for Amend to License DPR-34 Will Be Submitted Upon Resolution of NRC Comments Project stage: Draft Request ML20141B7451986-03-28028 March 1986 Summary of 860313 Meeting W/Util in Arlington,Tx Re Tech Spec Limiting Condition for Operation 4.1.9 Covering Frequency of Manipulation of Reactor Controls.Supporting Documentation Encl Project stage: Meeting ML20211E9171986-06-13013 June 1986 Advises That Formal Application for Tech Spec Rev Re Limiting Condition for Operation 4.1.9, Min Helium Flow & Max Core Region Temp Rise, Will Be Submitted by 860703. Extension Required for Resolution of NRC 860606 Comments Project stage: Request ML20202E9521986-07-0909 July 1986 Proposed Tech Specs,Incorporating Min Helium Flow & Max Core Region Temp Rise Surveillance Requirements Project stage: Other ML20202E9371986-07-0909 July 1986 Application for Amend to License DPR-34,changing Tech Specs to Incorporate Helium Flow & Max Core Region Temp Rise Surveillance Requirements Project stage: Request ML20202E9261986-07-0909 July 1986 Forwards Application for Amend to License DPR-34,changing Tech Specs to Incorporate Min Helium Flow & Max Core Region Temp Rise Surveillance Requirements.Fee Paid Project stage: Request ML20237E0051986-10-16016 October 1986 Forwards Final Version of Facility Limiting Condition for Operation 4.1.9 Technical Evaluation Rept for Review & Approval.Related Info Encl Project stage: Other ML20214W4521986-10-16016 October 1986 Review of Proposed Tech Spec Change:Core Inlet Orifice Valves/Min Helium Flow & Max Core Region Temp Rise, Technical Evaluation Rept Project stage: Other ML20214W4361986-12-0505 December 1986 Forwards Review of Proposed Tech Spec Change:Core Inlet Orifice Valves/Min Helium Flow & Max Core Region Temp Rise. Requests Submittal Addressing Staff Concerns within 45 Days of Ltr Date Project stage: Approval ML20212G8781987-01-14014 January 1987 Advises That Util Will Submit Revised Proposal for Tech Spec 4.1.9 Re Min Helium Flow & Max Core Region Temp Rise by 870225.Util Finalizing Curves That Determine Allowed Outage Times for DHR Equipment for Inclusion in Tech Specs Project stage: Other ML20216J4731987-06-25025 June 1987 Forwards Application for Amend to License DPR-34,changing Tech Spec Limiting Condition for Operation 4.1.9 to Reduce Potential for Flow Stagnation & Prevent Excessive Fuel Temps in Core & Spec 5.1.8 to Incorporate Requirements.Fee Paid Project stage: Request ML20216H7301987-06-25025 June 1987 Proposed Tech Specs,Adding Definition of Calculated Bulk Core Temp & Core Average Inlet Temp for Determination of Core Temp Project stage: Other ML20216H7221987-06-25025 June 1987 Application for Amend to License DPR-34,changing Tech Spec Limiting Condition for Operation 4.1.9 to Reduce Potential for Flow Stagnation & Prevent Excessive Fuel Temps in Core & Spec 5.1.8 to Incorporate Associated Requirements Project stage: Request ML20236U7221987-08-0606 August 1987 Addendum to Review of Proposed Tech Spec Change:Core Inlet Valves/Min Helium Flow & Max Core Region Temp Rise, Limiting Conditon for Operation 4.1.9, Technical Evaluation Rept Project stage: Other ML20236U5041987-11-23023 November 1987 Forwards Amend 57 to License DPR-34 & Safety Evaluation. Amend Revises Tech Specs to Ensure Sufficient Helium Coolant Flow to Prevent Overheating of Fuel While in Low Power or Shutdown Modes Project stage: Approval 1985-11-22
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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:RESEARCH INSTITUTION/LABORATORY TO NRC
MONTHYEARML20235Z2621987-07-0808 July 1987 Requests Addl Info from Util Re Bldg 10 Seismic Design, Including Descriptive Matl for PILAY2 Computer Code & Sketches or Drawings Showing Caisson/Slab/Wall Configurations ML20237E0051986-10-16016 October 1986 Forwards Final Version of Facility Limiting Condition for Operation 4.1.9 Technical Evaluation Rept for Review & Approval.Related Info Encl ML20197A7701986-05-0202 May 1986 Forwards Technical Assistance to Region IV (Fort St Vrain), Monthly Progress Repts for Feb & Mar 1986 ML20098H1721984-08-21021 August 1984 Provides Replies & Comments to Util Re Tech Spec Limiting Condition for Operation 4.1.9 in Advance of 840823 Meeting W/Util in Arlington,Tx ML20138A6241984-06-19019 June 1984 Submits Description of Method Used to Estimate Release of Respirable Radioactive Matl & Brief Comparison of Release from LWR Fuel to That Expected from HTGR Fuel ML20039F6711982-01-0505 January 1982 Forwards Review of PSC of Co Proposed Inservice Insp Program. Milestones on Inservice Insp Have Been Met ML20004F9021981-06-16016 June 1981 Summarizes Implementation & Progress of Review of Fort St Vrain Items & Applicability to Htgrs. ML20004F6101981-05-12012 May 1981 Submits Monthly Repts for Tasks Initiated on 810417 Re NUREG-0737, Applicability of TMI Action Plan Requirements to Fort St Vrain & Htgrs, for Period Ending 810515 ML19257C7431979-04-24024 April 1979 Forwards Rept to NRC on Effect of Installing Core Region Constraint Devices on Seismic Response of Plant Core. ML19260E1891979-04-24024 April 1979 Forwards Final, Rept to NRC on Effect of Installing Core Region Constraint Devices on Seismic Response of Facility Core. Unchanged from Draft Version.Submits Response to Structural Engineering Branch Comments ML19289C3761978-12-21021 December 1978 Responds to NRC 781121 Request for Aid W/Licensing Review Re Postulated Dbda & Loss of Forced Circulation Accidents. Concludes Each of the New Postulated Cases Results in Max Temp No Greater than FSAR-assumed Worst Case ML20062G2281978-12-19019 December 1978 Summary of 781215 Meeting of Tech Review Comm for Review of Temp Fluctuations in Subj Facil.Topics Discussed Incl Comparison of Displacement Probe & Nuc Detector Signals & Info on Core Status ML19289C3741978-12-13013 December 1978 Forwards Rept to NRC on the PSC Document Entitled Core Fluctuation Investigation Status & Safety Evaluation Rept. Concludes It Is Unlikely That Fluctuation Problem Is Causing Serious Structural Damage as Result of Core Motion 1987-07-08
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OAK RIDGE NATIONAL LABORATORY post omcE sox v CAN RIDGE. TENNESSEE 37831 orERaTEo av wmN MNETTA ENER0v SYSTEMS. NC.
August 21, 1984 Mr. Philip Wagner, Project Manager U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 70611 Doar Mr. Wagner: ;
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Subject:
Initial Response to PSC Letter on LCO 4.1.9 (P-84223, dated j August 14, 1984)
I expect that a lot of the questions and differences between the ORNL and PSC views can be resolved at the August 23 meeting at Region IV in Arlingtoni however, I thought it might be useful to write down my replies and comments in advance. The itam numbers correspond to those in the attachment to P-84223.
- 1. Our understanding of LCO 4.1.9 is that it limits the core conditions such that the region outlet thermocouples can be relied upon i to give an adequate astimate of maximum core temperatures. If any region flows were stagnated or reversed, the outlet temperature measurements l would not be able to indicate the status of the region fuel temperaturac.
The name of the LCO implies that it provides operating restrictions to limit " core temperatura rise", which is misleading. ORNL comments about "nonconservative-features" are covered in item 3.
- 2. Our comment that the current approach is " overly conservative" stems from the fact that, according to our calculations with the ORECA code, region flow stagnation is almost impossible to achieve under normal operating conditions. Hence the extra restrictions put on the operation by LCO 4.1.9 appear to be unnecessary. From a safety standpoint, we sculd have no complaints about the current LCO.
It is also our impression that the proposed ORNL scheme would be easier to implement (which is PSC's problem) and enforce (which is NRC's problem), so we would leave that evaluation to others.
PSC notes th - the current scheme minimizes the number of orifice adjustments required in going from low to high power, and that this is desirable. It appears to us that a scheme such as in ORNL's proposal, which starts out going for equal cutlet temperatures at very low powers, would require simpler, if not fewer, mani pul ati ons. In any case, from our experienca with sticking drives, it would seem beneficial to operate them occasionally to keep them limber.
- 3. Our comments about non-conservative features cf tne current LCC 4.1.9 had to do wi th the " hole" in LCO 4.1.7 between TK950F and on-scale on Fig. 4.1.7-1. PSC's proposed fix in their item 0 would cura that crablem. Cur other concern was that since P5C's stagnat;cn analysis was 8409120069 840906 PDR ADOCK 05000267 P PDR
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'Mr. Philip' Wagner 2' August 21, 1984 done:for steady-state equilibrium cases only, it doesn't necessarily
. fellow that it-would be conservativ'e for transients, especially those
\ involving rapid power and flow reductions from full power.
~
Our subsequent analyses of-representative shutdowns using ORECA have
-indicated that this would not be a problem, however.
- 4. The=1ow-flow measurement situation will hopefully be clarified at
!the meeting. From what we have observed, however, it is difficult to tell what the "real" low-range flow is. The plant data logger appears to have several estimates,. and PSC's HISTORY code has an elaborate echeme_for estimating it. Sometimes these estimates vary widely, and sometimes.they are all quite different from " heat balance" estimates of the_ flow. We assume that the plant operators use panel readouts of the low-range d/p cells, which should.give them good estimates. However, f .from the data we obtained, these readings don't necessarily make it to L :- :the DAS,lwhich we understand is what PSC uses to determine if they are h approaching or violating a tech spec limit. A good flow estimate is p important in that :it is a primary parameter in both the old and proposed j"
vsrsions of.LCO 4.1.9. Additionally, estimates of core power in the low range are also subject to. considerable % of reading error. We believe
- that an:" official" estimate of core-power during shutdowns should include calculated afterheat.
- 5. In addition to commenting on the relative merits of the proposed approaches, (which we cover above),JPSC states that ORNL's proposed test to' observe. flow redistributions is unacceptable because stagnation would Loccur'long before it could be detected.- This is contrary by an enormous margin.to what our ORECA code calculations indicate, and is a very important point.to pursue. If PSC has observed such behavior on FSV,
-then-the fidelity of ORECA and GAT's RECA code (which generally " agrees" with'ORECA) is in question. These codes have been used extensively in NRC safety evaluations, and if indeed there is such a discrepancy, some verification tests would be advisable.
Yours truly, S. J. Ball, Manager HTGR Safety Studies for NRC
'cc: -J. C. Cleveland R. B. Foulds DAE/RES R. M. Harrington R. Ireland NRC/RIV
'T. S. Kress
- A. P. Malinauskas D. L. Moses
-Frank Novachek PSC (3)
G. L. Plumlee,-III NRC/FSV P. M. Williams -NRC/NRR
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