Letter Sequence RAI |
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Results
Other: ML20137H372, ML20137L926, ML20137Z363, ML20138B512, ML20138L407, ML20141E527, ML20141H534, ML20141H544, ML20141H549, ML20151R074, ML20154N150
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MONTHYEARML20132E6081985-07-19019 July 1985 Supplemental Safety Evaluation Supporting Licensee CRD Mechanisms & Associated Position Instrumentation,Per 850712 Safety Evaluation & Licensee 850710 & 18 Submittals.Control Rod Program Acceptable for Plant Restart Project stage: Request 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 ML20134M0161985-08-20020 August 1985 Submits Discussion of Technical Issues Re Environ Qualification Program Raised During Meetings W/Nrc.Aging & Operability Time Program Operator Response Time,Temp Profiles & Shutdown Cooling Paths & Equipment Evaluated Project stage: Meeting IR 05000267/19850211985-08-30030 August 1985 Insp Rept 50-267/85-21 on 850721-31.No Violation or Deviation Noted.Major Areas Inspected:Operational Safety Verification Project stage: Request ML20137X1411985-09-30030 September 1985 Safety Evaluation Supporting Util 850830,0910,11 & 23 Requests for Authorization to Operate at Max 8% Power,For Up to 45 Days,To Remove Moisture from RCS Project stage: Approval ML20137X1241985-09-30030 September 1985 Forwards Safety Evaluation Based on Util 850830,0910,11 & 23 Requests for Authorization to Operate at Max 8% Power,For Up to 45 Days,To Remove Moisture from Rcs.Authorization Granted,Subj to Listed Commitments Project stage: Approval ML20138E3921985-10-11011 October 1985 Forwards Request for Addl Info on 850924 Request for Special Consideration & Schedule Extension to Equipment Qualification rule,10CFR50.49.Info Requested within 7 Days of Ltr Receipt Project stage: RAI ML20138C8111985-10-21021 October 1985 Forwards Response to 851011 Request for Addl Info Re 850924 Request for Schedule Extension for Environ Qualification Program Under 10CFR50.49 from 851130 to 860331 Project stage: Request ML20138R7331985-10-31031 October 1985 Summary of 851029 Meeting W/Util & ORNL Re Schedule Extension to Equipment Qualification Rule.List of Attendees, Agenda & Matls Presented by Util Encl Project stage: Meeting ML20209J0821985-11-0505 November 1985 Forwards Request for Addl Info Re Equipment Qualification Program & Request for Extension of Deadline for Compliance W/Equipment Qualification Rule,Per 851029 Meeting Project stage: RAI ML20136F6991985-11-19019 November 1985 Modifies Scheduled Commitment for Submittal of Final Draft Proposal of Upgraded Tech Specs for NRC Comment,Per 851008 Request.Revised Submittal Date of 851130 Approved.Revised Tabulation of Commitments Encl Project stage: Draft Other ML20136J1831985-11-21021 November 1985 Staff Requirements Memo Re Commission 851119 Meeting in Washington,Dc on Licensee Environ Qualification Exemption Request.Recommendation on Extension Request Should Be Provided by 851122 Project stage: Meeting ML20136J0151985-11-22022 November 1985 Notifies of Withdrawal of 850924 Schedule Extension Request for Environ Qualification Program.Approval of Revised Schedule Extension for Implementation of Program Beyond 851130 Under Provision of 10CFR50.49 Requested Project stage: Withdrawal ML20137H3721985-11-26026 November 1985 Memorandum & Order Granting Extension of 851130 Deadline for Environ Qualification of Electrical Equipment to 860531 & Approving Proposal to Allow Operation w/35% Reactor Power Limit During Interim.Served on 851127 Project stage: Other ML20137Z3631985-12-0505 December 1985 Staff Requirements Memo Re Affirmation/Discussion & Vote on Extension of 851130 Deadline for Environ Qualification & Revised Post 851130 Environ Qualification Extension Request Project stage: Other ML20138L4071985-12-10010 December 1985 Rev B to EE-EQ-0019, Engineering Evaluation of Liner Cooling W/Fire Water Following High Energy Line Break from 35% Power Operation at Fort St Vrain Project stage: Other ML20138B5121985-12-10010 December 1985 Forwards Evaluations to Document Completion of Confirmatory Actions Required to Support 35% Power Restriction During Environ Qualification Schedule Extension Period Project stage: Other ML20136C8221985-12-26026 December 1985 Forwards Request for Addl Info to Complete Resolution of Confirmatory Action 6 Re Insp of High Energy Piping.Concerns Include Potential for Inservice Degradation & Exam & Insp Methods Project stage: RAI ML20137L9261985-12-31031 December 1985 Heat Stress Mgt Program for Nuclear Power Industry, Interim Rept Project stage: Other ML20141E5271986-01-0303 January 1986 Forwards Summary of Position on Confirmatory Action 6 Re Insp of Critical Areas of High Energy Piping & Responses to Six Addl Info Requests.Limited Insp Plan Will Be Completed by Middle of Jan 1986.Drawings Encl Project stage: Other ML20141H5341986-01-0808 January 1986 Forwards NDE Procedures,Per DW Warembourg Project stage: Other ML20141H5441986-01-0808 January 1986 Issue 1 to NDE Procedure QCIM-38, Ultrasonic Exam of Class 1 & 2 Piping Welds Joining Similar & Dissimilar Matls Project stage: Other ML20141H5491986-01-0808 January 1986 Issue 5 to NDE Procedure QCIM-30, Radiographic Exam Procedure Project stage: Other ML20137M1091986-01-15015 January 1986 Forwards Addl Info to Support Util Intention to Use Ice Vests to Allow Personnel Access W/Elevated Bldg Temps. T Bernard Prof Opinion Documented in Encl Draft Heat Stress Mgt Program. Rept Available in Central Files Project stage: Draft Other ML20137L9001986-01-21021 January 1986 Forwards EPRI Interim Rept, Heat Stress Mgt Program for Nuclear Power Industry, to Replace Draft Transmitted by Walker ,To Support 35% Power Bldg Access.Rept Will Be Available in Mar as EPRI NP4453 Project stage: Draft Other ML20151R0741986-01-29029 January 1986 Informs That NRR Ltr to Licensee Summarizing Findings Re Environ Qualification Extension Sufficient to Authorize Limited Operation.No License Amend Required to Support Authorization Project stage: Other ML20154N1501986-03-0303 March 1986 Forwards Final Rept on Inservice Insp Program Performed on High Energy Piping.Program Inspected 35 Critical Areas of Piping Per Safety Evaluation of Confirmatory Item 6. Integrity Verified in Support of 35% Power Operation Project stage: Other 1985-12-31
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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:NRC TO UTILITY
MONTHYEARML20058J0121990-11-16016 November 1990 Forwards Insp Rept 50-267/90-20 on 901029-1102.Violations Noted But Not Cited IR 05000267/19900161990-10-30030 October 1990 Discusses Insp Rept 50-267/90-16 on 900928 & 901018 Enforcement Conference & Forwards Notice of Violation ML20062B3971990-10-15015 October 1990 Forwards Insp Rept 50-267/90-14 on 900801-0930.No Violations or Deviations Noted ML20058A0941990-10-12012 October 1990 Confirms 901018 Enforcement Conference in Region IV Ofc Re Violations & Radiation Program Weakness Noted in Insp Rept 50-267/90-16.Proposed Agenda Encl ML20059N8231990-10-0303 October 1990 Forwards FEMA Final Radiological Emergency Preparedness Exercise Rept, for 891115 Exercise.One Deficiency & Several Areas Requiring Corrective Actions Identified ML20059C1381990-08-24024 August 1990 Forwards Notice of Consideration of Issuance of Amend to License DPR-34 & Opportunity for Hearing Re 900605 Application,For Info ML20056B4021990-08-20020 August 1990 Forwards Insp Rept 50-267/90-11 on 900601-0728.No Violations or Deviations Noted ML20058M8681990-08-0808 August 1990 Forwards Insp Rept 50-267/90-13 on 900709-13.No Violations or Deviations Identified.Licensee Commitment to Revise Manual Dose Assessment Procedure to Incorporate Appropriate Unit Conversion Factor,Noted ML20055J3951990-07-31031 July 1990 Ack Receipt of 900713 Request for Exemption from FY90 Annual Fee Requirements of 10CFR171.Annual Fee Will Not Be Billed ML20056A3601990-07-31031 July 1990 Forwards Insp Rept 50-267/90-10 on 900611-15.No Violations or Deviations Noted.Actions Taken Re Previously Identified Insp Findings & Status Examined ML20059D1281990-07-30030 July 1990 Ack Receipt of 900713 Request for Full Exemption from FY90 Annual Fee Requirements of 10CFR171 for Plant.Annual Fee Will Not Be Billed While Request Under Review ML20055G5921990-07-19019 July 1990 Agrees W/Removal of B Helium Circulator,Per Requesting NRC Concurrence.Solution to Correct Leakage Problem by Removal of Circulator Acceptable ML20055D2031990-06-26026 June 1990 Ack Receipt of 900525 Response to 900402 Emergency Preparedness Insp Rept & 900427 Notice of Violation ML20055C8021990-06-18018 June 1990 Concludes That Financial Info Forwarded by Meets Requirements of 10CFR140.21 ML20248H7751989-10-0303 October 1989 Forwards Insp Rept 50-267/89-19 on 890821-26 & 29-30.No Violations or Deviations Noted IR 05000267/19890171989-10-0202 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-17. Implementation of Corrective Actions Will Be Examined During Future Insps IR 05000267/19890081989-10-0202 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-08. Understands That Revised Flow Test Surveillance Procedures Performed on 890821 & 0921 & cross-connect Valves Stroked ML20248B2971989-09-26026 September 1989 Forwards Insp Rept 50-267/89-16 on 890716-0831 & Notice of Violation IR 05000267/19890121989-09-22022 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-267/89-12 ML20247L1381989-09-19019 September 1989 Advises That Request to Delete Requirement to Provide Status Repts on Performance Enhancement Program Approved.Updated List of Commitments Encl ML20247K7741989-09-15015 September 1989 Informs That Partial Review of 890125 & 0320 Submittals Re Helium Circulators complete.Ten-yr Insp Recently Conducted on Circulator C-2105.Insp Revealed No Defects or Unacceptable Conditions ML20247K4141989-09-15015 September 1989 Advises That Tech Specs Re Upgrade Program,Requested in NRC ,Must Be Approved by NRC Before Defueling ML20247D4691989-09-11011 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-15 ML20247H3431989-09-0808 September 1989 Ack Receipt of Informing NRC of Status of Security Sys Upgrades ML20247H2891989-09-0606 September 1989 Concurs W/Util 890714 Request for Changes to Basis for Limiting Condition for Operation 4.2.2 of Facility Tech Specs Re Statement About Automatic Initiation of Backup Bearing Water Sys ML20247B2661989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executives Meeting on 890818 in Arlington,Tx.Topics Discussed Included, Improving Communications,Salp Process in Region IV & Enforcement.List of Attendees & Agenda Encl ML20246J2911989-08-30030 August 1989 Forwards Amend 72 to License DPR-34 & Safety Evaluation. Amend Imposes Early Shutdown by Limiting Reactor Power to 2% of Full Power After 900630 ML20246E5941989-08-21021 August 1989 Forwards Insp Rept 50-267/89-14 on 890710-14 & Notice of Violation.Two Separate Findings of Missing Info in Semiannual Effluent Rept,Resulting in Failure to Satisfy Tech Spec Administrative Requirements Identified ML20246A2651989-08-16016 August 1989 Forwards Insp Rept 50-267/89-13 on 890626-30.Violations Noted But No Citation Issued.Expresses Concern About Status of Model FSV-1 & FSV-1A Shipping Casks ML20245J3511989-08-14014 August 1989 Forwards Amend 71 to License DPR-34 & Safety Evaluation. Amend Revises Provisions in Tech Specs Re Radiological Effluents ML20246A6841989-08-14014 August 1989 Forwards Exam Rept 50-267/OL 89-02 Administered During Wk of 890710 ML20245J5651989-08-10010 August 1989 Forwards Insp Rept 50-267/89-17 on 890717-21 & Notice of Violation ML20245H3891989-08-0808 August 1989 Forwards Insp Rept 50-267/89-12 on 890601-0715 & Notice of Violation ML20245J4421989-08-0808 August 1989 Forwards Safety Evaluation,Responding to Issues Re Tech Spec Upgrade Program & Defueling of Plant.Requests That Tech Spec Changes Be Requested within 30 Days of Ltr Date ML20248E0041989-08-0303 August 1989 Forwards Team Insp Rept 50-267/89-08 on 890522-26 & Notice of Violation.Response Should Include Corrective Actions Taken or Planned to Ensure That Reactor Water Cooling Sys 46 Operated as Designed IR 05000267/19890071989-07-28028 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-07 ML20247N7581989-07-26026 July 1989 Discusses Licensee 890616 Request Re Changes to Previous Commitments Concerning Plans to Shut Down Plant.Commitment 2c to Be Subj of Separate Correspondence.Commitment 7 to Be Considered Not Applicable.W/Revised Summary of Commitments ML20247M4281989-07-25025 July 1989 Responds to 890120 & 0616 Requests for Relief from Requirements of Fuel Surveillance Program.Nrc Considers Util Obligations Under Fuel Surveillance Program Will Terminate W/Planned Shutdown of Reactor by 900630 ML20247M4521989-07-25025 July 1989 Forwards Request for Addl Info Re Reactor Defueling.Info Needed within 30 Days of Ltr Date ML20247L9801989-07-14014 July 1989 Discusses 890711 Meeting in Region IV Ofc Re Introduction of AC Crawford & Future Plans for Facility.Slides Presented at Meeting & List of Attendees Encl ML20247L5971989-07-14014 July 1989 Forwards Insp Rept 50-267/89-15 on 890623-27 & Notice of Violation.Response Should Describe Corrective Actions to Assure That safety-related Changes Introduced by Other Parts of Organization Are Properly Incorporated Into Procedures ML20246M6941989-07-11011 July 1989 Forwards Agenda for 890808 Meeting of Senior Util Executives Sponsored by Region IV at Univ of Texas.Map to Facilitate Access to Meeting Room Also Encl ML20246F4851989-07-10010 July 1989 Discusses Util Re Alternative Compensatory Measures Instituted,Per Fire Protection Operability Requirement-16.Proposed Guidance Adequate ML20246J2791989-07-0707 July 1989 Forwards Safety Evaluation Concluding That Operators Role in Mitigating High Energy Line Break at Facility Acceptable. Technical Evaluation Rept Also Encl ML20245G4491989-06-22022 June 1989 Forwards Exam Rept 50-267/OL-89-01 Administered During Wk of 890523 ML20245G4831989-06-20020 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-06 ML20245F8161989-06-20020 June 1989 Proposes Meeting in Region IV to Discuss SALP Process in Region Iv,Improving Communication W/Licensee Mgt,Region IV Enforcement Philosophy,How to Improve Safety Performance & Topics Util Wishes to Discuss ML20245A2201989-06-15015 June 1989 Forwards Insp Rept 50-267/89-10 on 890501-31.No Violations or Deviations Noted ML20244C1221989-06-0808 June 1989 Forwards Insp Rept 50-267/89-07 on 890319-0430 & Notice of Violation ML20248B8741989-06-0505 June 1989 Forwards Draft Reg Guide, Assuring Availability of Funds for Decommissioning Nuclear Reactors, Task CE 025-4,for Use in Preparing Preliminary Decommissioning Plan for Plant 1990-08-08
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20236R9191998-07-20020 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 ML20198H5601997-09-16016 September 1997 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety 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 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 ML20137S1691997-04-0707 April 1997 Fifth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App K ML20137S0821997-04-0707 April 1997 Forwards Insp Rept 50-267/97-01 on 970310-11.No Violations Noted 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) 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) 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) 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 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 ML20132G0421996-12-23023 December 1996 Forwards Insp Rept 50-267/96-05 on 961203-05.No Violations Noted 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) ML20128G1421996-09-25025 September 1996 Advises NRC Approved Decommissioning Plan, Impact Of... Fsv Final Decommissioning, Satisfies All Elements of License Termination Plan as Required by Rev to Reactor Decommissioning Rule 10CFR50.82(a)(9) ML20136B2561996-04-0202 April 1996 Informs That NOV Issued on 951030 Revised to Reflect NRC Reanalysis of Info Re Falsification of Radiation Survey Records.Revised NOV Encl ML20136B2731996-04-0202 April 1996 Informs That NOV Issued on 951030 Revised to Reflect NRC Reanalysis of Info Re Util Failure to Assure Compliance w/10CFR50.9 Concerning Accuracy of Radiation Survey Records. Revised NOV Encl ML20136B3241996-04-0202 April 1996 Informs That NRC Will Be Withdrawing NOV ,based on Reevaluation of Evidence Provided & Response to NOV ML20058G9671993-12-0707 December 1993 Ack Receipt of Ltrs of 931110,responding to Notice of Violation & Proposed Imposition of Civil Penalty Issued on 931013 IR 05000267/19930021993-09-0303 September 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Deviations Noted in Insp Rept 50-267/93-02. Deficiency Determined to Have Contributed to 930527 Crane Overload Event IR 05000267/19930011993-09-0303 September 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/93-01 ML20056G0041993-06-25025 June 1993 Submits Info Re Implementation of Training Rule 10CFR50.120 for Licensees of Plant in Decommissioning Process ML20128D6931992-12-0101 December 1992 Forwards Exemption from Requirement in 10CFR50,app E,Section IV.F.2 to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise. EA & SE Also Encl ML20198C7511991-06-25025 June 1991 Suggests That Region Iv/Senior Util Executive Conference Be Held During Month of Sept 1991 in Arlington,Tx to Provide Open Forum for Candid Discussions Limited to Topics of General Interest & Not Pertain to Plant Specific Issues ML20058K0231990-11-30030 November 1990 Forwards Insp Rept 50-267/90-17 on 901001-1109.No Violations or Deviations Noted ML20062H8131990-11-29029 November 1990 Forwards Partially Withheld Insp Rept 50-267/90-18 on 901022-26 & Notice of Violation ML20062H2041990-11-21021 November 1990 Forwards Insp Rept 50-267/90-19 on 901015-19.No Violations or Deviations Noted ML20058J0121990-11-16016 November 1990 Forwards Insp Rept 50-267/90-20 on 901029-1102.Violations Noted But Not Cited IR 05000267/19900161990-10-30030 October 1990 Discusses Insp Rept 50-267/90-16 on 900928 & 901018 Enforcement Conference & Forwards Notice of Violation ML20062B3971990-10-15015 October 1990 Forwards Insp Rept 50-267/90-14 on 900801-0930.No Violations or Deviations Noted ML20058A0941990-10-12012 October 1990 Confirms 901018 Enforcement Conference in Region IV Ofc Re Violations & Radiation Program Weakness Noted in Insp Rept 50-267/90-16.Proposed Agenda Encl ML20059N8231990-10-0303 October 1990 Forwards FEMA Final Radiological Emergency Preparedness Exercise Rept, for 891115 Exercise.One Deficiency & Several Areas Requiring Corrective Actions Identified ML20059C1381990-08-24024 August 1990 Forwards Notice of Consideration of Issuance of Amend to License DPR-34 & Opportunity for Hearing Re 900605 Application,For Info ML20056B4021990-08-20020 August 1990 Forwards Insp Rept 50-267/90-11 on 900601-0728.No Violations or Deviations Noted ML20058M8681990-08-0808 August 1990 Forwards Insp Rept 50-267/90-13 on 900709-13.No Violations or Deviations Identified.Licensee Commitment to Revise Manual Dose Assessment Procedure to Incorporate Appropriate Unit Conversion Factor,Noted ML20056A3601990-07-31031 July 1990 Forwards Insp Rept 50-267/90-10 on 900611-15.No Violations or Deviations Noted.Actions Taken Re Previously Identified Insp Findings & Status Examined ML20055J3951990-07-31031 July 1990 Ack Receipt of 900713 Request for Exemption from FY90 Annual Fee Requirements of 10CFR171.Annual Fee Will Not Be Billed ML20059D1281990-07-30030 July 1990 Ack Receipt of 900713 Request for Full Exemption from FY90 Annual Fee Requirements of 10CFR171 for Plant.Annual Fee Will Not Be Billed While Request Under Review ML20055G5921990-07-19019 July 1990 Agrees W/Removal of B Helium Circulator,Per Requesting NRC Concurrence.Solution to Correct Leakage Problem by Removal of Circulator Acceptable ML20055D2031990-06-26026 June 1990 Ack Receipt of 900525 Response to 900402 Emergency Preparedness Insp Rept & 900427 Notice of Violation ML20055C8021990-06-18018 June 1990 Concludes That Financial Info Forwarded by Meets Requirements of 10CFR140.21 ML20248H7751989-10-0303 October 1989 Forwards Insp Rept 50-267/89-19 on 890821-26 & 29-30.No Violations or Deviations Noted IR 05000267/19890081989-10-0202 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-08. Understands That Revised Flow Test Surveillance Procedures Performed on 890821 & 0921 & cross-connect Valves Stroked IR 05000267/19890171989-10-0202 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-17. Implementation of Corrective Actions Will Be Examined During Future Insps ML20248B2971989-09-26026 September 1989 Forwards Insp Rept 50-267/89-16 on 890716-0831 & Notice of Violation IR 05000267/19890121989-09-22022 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-267/89-12 ML20247K9051989-09-19019 September 1989 Advises That 890726 Request for Approval of Route to Transport Spent Reactor Fuel Approved.Route,From Facility to DOE Inel in Idaho,Encl ML20247L1381989-09-19019 September 1989 Advises That Request to Delete Requirement to Provide Status Repts on Performance Enhancement Program Approved.Updated List of Commitments Encl 1998-07-20
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'/ UNITED STATES
[ g, NUCLEAR REGULATORY COMMISSION t, a wAsHWGTON, D. C. 20655
,,,, December 26, 1985 Docket No. 50-267 Mr. R. F. Walker President
. Public Service Company of Colorado i Post Office Box 840
- Denver, Colorado 80201
Dear Mr. Walker:
SUBJECT:
CONFIRMATORY ACTION 6 - INSPECTION OF HIGH ENERGY PIPING t
j We are reviewing your submittal dated December 10,1985(P-85460)
- containing the confirmatory actions in support of our approval of Fort St. Vrain's operation at up to 35 percent of full power. Confirmatory i Action 6 states
- " Submit a plan and perform inservice inspections on several critical areas of Fort St. Vrain's high energy piping to verify the:
j integrity of this piping, prior to returning the plant to operation." We have reviewed your submittal and relevant information in your updated FSAR.
i You have stated that the objective of your program is to verify the
! integrity of the Main Steam, Hot Reheat, Cold Heat, and Feedwater Systems and proposed the following actions to revolve ~this confirmatory action:
- 1) Perfonn volumetric examination of three (3) butt welds (8" pipe to 2
fitting, 8" pipe to elbow and 20". pipe to fitting),
l ~) 2 Perform volumetric examination of the base metal at the mid-point of
- the 8" elbow and, 1 i
i 3) Use the inspection methods and analysss of the original plant piping construction code, ANSI B31.1.
In telephone discussions with the staff, subsequent to your submittal, your
~
staff proposed four additional examinations of the Hot and Cold Reheat Systems. After due consideration of this additional proposal the staff concludes that Confirmatory Action 6 still remains to be satisfied for the following reasons: (1) There is the potential for inservice degradation, i
such as thermal fatigue, mechanical fatigue and creep-rupture phenomena in the materials of construction, and (2) The examinations you have proposed do not constitute a significantly representative sample of the number of
~
material specifications, diameters and wall thicknesses of the piping systems accessible for inspection.
4
. In addition to the two reasons stated above, you will likely encounter limitations to volumetric examination at the selected locations because of the geometric configuration of the fittings. Also, your proposed inspection ;
, methods and acceptance criteria may.not be effective for the detection of inservice degradation, if present.
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- PDR ADOCK 05000267
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, , December 26, 1985 In order to resolve these questions, the staff has prepared the enclosed request for~ additional information that defines the documentation needed to complete the resolution of Confirmatory Action 6.
Please advise the assigned Project Manager, Kenneth L. Heitner (301) 492-7364, of your schedule for.a response so that we may-pursue i resolution of this issue in a timely manner.
Sincerely, Original signed by Herbert N. Berkow, Director Standardization and Special
, Projects Directorate i
Division of PWR Licensing-B, NRR I
Enclosure:
As stated cc w/ enclosure:
See next page 1
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In order to resolve these questions, the staff has prepared the enclosed request for additional information that defines the documentation needed to complete the resolution of Confirmatory Action 6.
Please advise the assigned Project Manager, Kenneth L. Heitner (301) 492-7364, of your schedule for a response so that we may pursue resolution of this issue in a timely manner.
Sincerely, k
erbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B, NRR
Enclosure:
As stated cc-w/ enclosure:
e See next page 9
Mr. O. R. Lee Public Service Company of Colorado Fort St. Vrain cc:
C. K. Millen Albert J. Hazle, Director Senior Vice President Radiation Control Division Public Service Company 4210 East lith Avenue of Colorado Denver, Colorado 80220 P. O. Box 840 Denver, Colorado 80201 J. W. Gahm Nuclear Production Manager Mr. David Alberstein, 14/159A Public Service Company of Colorado GA Technologies, Inc. P. O. Box 368 P. O. Box 840 Platteville, Colorado 80651 Denver, Colorado 80201 J. K. Fuller, Vice President Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Senior Resident Inspector U.S. 9" clear Regulatory Commission a
P. 0. Box 640 Platteville, Colorado ~ 80651 Kelley, Stansfield & 0'Donnell Public Service Company Building Room 900 550 15th Street Denver, Colorado 80202 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1800 Lincoln Street Denver, Colorado 80651 l
i
1 1
Fort St. Vrain (FSV)
Public Service Company of Colorado Docket-No. 50-267 Request for Additional Information
References:
- 1) Licensee's December 10, 1985 submittal, Attachment 1, Confirmator Action Item 6, Inservice Inspection (ISI) of high energy piping. y
- 2) FSV Updated FSAR.
j
Background:
1 i
Based on Reference 1, the licensee's inspection program is intended to verify the integrity of the Main Steam (MS), Hot Reheat (H. RT), Cold 1
Reheat-(C. RT), and Feedwater (FW) system prior to startup.
Staff Evaluation and Reouest for Information The licensee has not provided suf.ficient information in References 1 and 2 to reach a decision on confirmatory Action Item 6.
Soecif_ic infornation is reouired about the licensee's proposal and ISI parameters in the ioentified systems.
L Information about the licensee's proposal:
Ouestion 1.
Describe the criteria used to determine the critical areas selecteo for inservice inspection in the steam, feedwater, and cold and hot reheat lines. In particular, how are the effects of phenomena such as thermal and mechanical fatigue, creep-rupture,. corrosion and erosion considered in this selection?
' Question 2.
Provide the bases for the sample size selected considering that the sample size must be sufficient to detect inservice de examination methods must be effective to identify servicegradation present. inducedand theif flaws, Information about the high energy piping systems:
^
The PowerFSAR has Figure Conversion System". 10.1-1 "Overall Flow Diagram, Secondary Coolant and For the Main Steam, Hot Reheat, Cold Reheat and 6
-- - s-.~ - , - - . . . , - . , -, ,-e v---. ,,m----~s--, --,----,---,-r,-,,a .- , . - -v. -g,,, , ,~,r-~
i Feedwater Systems, define the regions of these systems that are physically accessible for RT or UT if insulation were removed. The piping in the turbine crossover lines and the piping and vessels in the turbine by pass lines (desuperheaters and flash tank) should be included.
In the regions following that are physically accessible for inspection, provide the information:
A) Isometric drawings and tables showing the identification of circumferential and longitudinal welds, the diameter and wall thickness of the piping runs, and the material specification of the pipe and~ vessels (desuperheaters and flash tank).
B) General description of the . insulation, i.e., lagging or removable.
C) 1.ocation of RT or UT to be conducted.
D) General description of the weld crowns, i.e., "as welded" or ground.
The objective of the staff's question is to identify welds and base metal in accessible locations with similar material _ properties, configurations and operating conditions as in inaccessible locations.
Question 3.
Define the specific nondestructive methods that will be used on tne locations selected for inspection, i.e., radiography (RT), ultrasonic testing (UT), and/or surface examination and provide a copy of the criteria. Aprocedure examination including calibration standards and accentance summary of maintenanca record data should be provided where additional information supports the inspectior, proposal.
I Ouestion 4.
For locations that involve the examination of pipe fittings, provide tne technical basis that demonstrates that the examination procedures will detect inservice deoradation, i.e., cracks, corrosion and erosion, if present on tne fitting sice of the butt welds and the inside/outside radius of the elbow.
Question 5. Provide an engineering drawing for each of the locations selected showing dimensions and material specifications and,whether the welds are "as-welded" or prepared for.ISI.
Define the volume or surface of each location subject to ISI with the examination method superimposed, i.e.,
double-wall RT, angle-beam UT, straight-beam UT, PT, or MT.
Ouestion 6. In the MS welding of piping or co,mponents 4 inch or greater.H. RT, C. RT anc FW system A brief description should be provided of the mechanism of failure and the method of detection.
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Identify inch andany inservice failure of bolted connections with bolt diameters 1/2 greater.
4 The inspection of these systems 'should include any known degradation mechanism'in these systems.
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