Letter Sequence Draft Approval |
|---|
|
Administration
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: ML20076E880, ML20079M106, ML20080E109, ML20100G880, ML20100G888, ML20100H212, ML20112G667, ML20127J807, ML20135B301, ML20135D754, ML20137H372, ML20137S741, ML20141P181, ML20154K144, ML20197C598, ML20197G513, ML20205C845, ML20206B459, ML20207K470, ML20211P495, ML20215E408, ML20215G100, ML20235G758
|
MONTHYEARML20076E8801983-05-17017 May 1983
Responds to NRC 830413 Order Re Environ Qualification of safety-related Electrical Equipment,Per 10CFR50.49.Environ Qualification Records Audit Will Be Completed by 831231
Project stage: Other
ML20080E1091983-08-15015 August 1983
Provides Followup to Util Re Environ Qualification of safety-related Electrical Equipment. Justification for Continued Operation W/Components Not Fully Qualified Provided
Project stage: Other
ML20079M1061984-01-0909 January 1984
Advises NRC Re Status of Three Commitments Made in Util Concerning Environ Qualification of safety-related Electrical Equipment.Valve Actuators Tested & Successfully Passed HELB Tests
Project stage: Other
ML20100G8881984-09-11011 September 1984
Four-Minute Isolation of Postulated Steam Line Breaks at Fort St Vrain Nuclear Generating Station
Project stage: Other
ML20112G6671984-12-27027 December 1984
Informs of Efforts to Environmentally Qualify Certain post-accident Monitoring Equipment Per 10CFR50.49.Equipment Identified in Reg Guide 1.97 & Existing in Harsh Environ Will Be Qualified by 850331
Project stage: Other
ML20108A2121985-02-0404 February 1985
Informs of Receipt of Generic Ltr 84-24 on 850121 & Request for Addl Info on Environ Qualification of Electrical Equipment on 850128.Responses to Both Ltrs Will Be Provided by 850328
Project stage: Request
ML20100H2121985-03-25025 March 1985
Forwards Response to NRC 841227 Order Re Certification of Compliance w/10CFR50.49 (Generic Ltr 84-24).Util Previously Submitted Ltrs Re Environ Qualification of safety-related Equipment in Response to IE Bulletin 79-01B
Project stage: Other
ML20100G8801985-03-28028 March 1985
Forwards Addl Info Re Environ Qualification Program. Response to NRC 850128 Concerns & Summary of Completion Schedule for Outstanding Items Encl
Project stage: Other
ML20237L1731985-03-29029 March 1985
Notification of 850403 Meeting W/Util in Bethesda,Md to Discuss Equipment Qualification
Project stage: Meeting
ML20127J8071985-06-11011 June 1985
Maintains Util Position of Full Compliance w/10CFR50.49 in Response to Eh Johnson 850611 Inquiry Re Environ Qualifications of Electrical Equipment Important to Safety. Responses to Each Concern Presented in Encl
Project stage: Other
ML20237L1551985-06-25025 June 1985
Submits Daily Highlight.Notifies of 850702 Meeting W/Util in Bethesda,Md to Discuss State of Compliance of Plant W/ Equipment Qualification Rule 10CFR50.49
Project stage: Meeting
ML20132B9171985-07-11011 July 1985
Discusses Resolution of Technical Issues of Aging & Operability Times Per 850702 Meeting Re Environ Qualification Program.Hold on Reactor Power to 15% Proposed as Initial Limitation
Project stage: Meeting
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
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
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
ML20135B3011985-08-30030 August 1985
Forwards Justification to Operate Facility at Reduced Power Level.Requests That NRC Provide Concurrence for Facility to Be Operated at 8% Power Level for Period of Time Not to Exceed 45 Days.Operation Does Not Pose Undue Safety Risk
Project stage: Other
ML20135D7541985-08-30030 August 1985
Advises That Rev of Emergency Procedures Committed to in Deferred to Coincide W/Final Environ Qualification Program Documentation.Procedure Revs at This Time Will Cause More Confusion than Clarity for Operators
Project stage: Other
ML20205C8451985-09-10010 September 1985
Forwards Info Supporting 850830 Request to Operate at 8% Power to Facilitate Core Dryout for 45 Days,Per 850826,0903 & 04 Telcons.Moisture Removal Needed to Maintain Conditions Prescribed in FSAR & Tech Specs
Project stage: Other
ML20205C4811985-09-11011 September 1985
Provides Commitment That Operating Procedures & Operator Training Described in Providing Addl Info in Support of Request to Operate at Up to 8% Power Will Be Complete Prior to Withdrawal of Control Rods
Project stage: Withdrawal
ML20137S7411985-09-23023 September 1985
Forwards Addl Calculations,Clarifying Util Re Predicted Fuel/Pcrv Liner Temps Resulting from Design Basis Event from 8% Power & Subsequent Reactor Cooling Utilizing Liner Cooling Sys.Calculations Confirm Original Position
Project stage: Other
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
ML20151N7211985-12-27027 December 1985
Forwards Response to 851105 Request for Addl Info Needed to Determine If Environ Qualification Program Complies W/ Requirements of 10CFR50.49.Sys Description & Temp Profiles Used in Environ Qualification Program Also Encl
Project stage: Request
ML20141P1811986-01-29029 January 1986
Rev 00 to Justification/Analysis:Environ Qualification of Square D Pressure & Temp Switches
Project stage: Other
ML20141M8081986-02-14014 February 1986
Advises That DBAs Re Permanent Loss of Forced Circulation & Rapid Depressurization of Reactor Vessel Must Be Addressed in Equipment Qualification Program.Util Cooperation W/Program Mods Confirmed During 851029 Meeting
Project stage: Meeting
ML20154K1441986-02-28028 February 1986
Forwards Addl Info Re Environ Qualification,Per 851105 Request.Encl Info for Three Line Break Scenarios in Reactor Bldg Will Allow Independent Verification of Temp Profiles Obtained from Ga Technologies Using Computer Programs
Project stage: Other
ML20142A0441986-03-12012 March 1986
Summary of 860221 Onsite Meeting W/Util,Inel,D Benedetto Assoc,S&W,Tenera,Ned & NPD Re Equipment Qualification Program & Steam Line Rupture Detection & Isolation Sys
Project stage: Meeting
ML20141P1771986-03-14014 March 1986
Summary of 860130 Meeting W/Util,Inel,Tenera & Sargent & Lundy Re Equipment Qualification (EQ) Program.List of Attendees,Test Profiles & Review of Sample EQ Package Encl
Project stage: Meeting
ML20205S2591986-04-10010 April 1986
Summary of 860326 Site Meeting W/Util,Dibenedetto Assoc,Inc, Sandia & Sargent & Lundy Re Status of Qualifications of 10CFR50.49 Cables & Maint Records History Review.Viewgraphs & Attendees List Encl
Project stage: Meeting
ML20204A3181986-05-0101 May 1986
Provides Status Summary of Environ Qualification Program. Addl Details on Program Contained in 860501 Draft Environ Qualification Submittal.Major Equipment Replacements Listed
Project stage: Draft Other
ML20197G5131986-05-12012 May 1986
Requests Concurrence Re Inclusion of DBA in Environ Qualification Program Per Berkow .Util Will Not Environmentally Qualify Electric Equipment to Mitigate DBA-1 & DBA-2 Since Equipment Not Exposed to Harsh Environ
Project stage: Other
ML20198H4561986-05-27027 May 1986
Summary of 860505 Meeting W/Util Re Status of Equipment Qualification Program.Considerable Work Remains Before Approval of Full Power Operation Can Be Granted.Staff Recommended Util Continue to Complete Program
Project stage: Meeting
ML20205S2341986-06-0101 June 1986
Summary of 860502 Meeting W/Util & Inel in Bethesda,Md Re Equipment Qualification Program Problem Areas.Attendees List & Supporting Documentation Encl
Project stage: Meeting
ML20206R6241986-06-20020 June 1986
Forwards Environ Qualification Submittal Re Activities to Assure Compliance w/10CFR50.49 & Incorporating Comments on Draft 860502 Submittal.Evaluations Will Be Available for Review Before Request for Release to Full Power
Project stage: Draft Request
ML20203B6181986-07-15015 July 1986
Summary of 860613 Meeting W/Util in Bethesda,Md Re Status of Plant Equipment Qualification Program.List of Attendees, Environ Qualification of Plant Safe Shutdown Cable & Cable Qualification Binders Encl
Project stage: Meeting
ML20204H6531986-07-31031 July 1986
Responds to 860724 Request for Documentation Re Use of Thermal Lag Analysis in Environ Qualification of Electrical Equipment in Plant.Thermal Analysis Will Be Performed Per Rev 3 to CENPD-255-A
Project stage: Request
ML20206P5971986-08-15015 August 1986
Summary of 860724 Meeting W/Util,Inel,Wyle Labs,Sargent & Lundy & Tenera in Bethesda,Md Re Util Draft Documentation to Justify Qualification of safety-related Cabling at Plant. List of Attendees Encl
ML20197C5631986-10-30030 October 1986
Forwards Draft FATE-86-117, Review of Convection Heat Transfer Coefficients Utilized in Fort St Vrain Main Steam Line Break Analyses, Technical Evaluation Rept (Ter).Ter Addresses Details Used in Temp Profile Calculations
Project stage: Draft Approval
IR 05000267/19860251986-10-30030 October 1986
Insp Rept 50-267/86-25 on 860816-0930.Violations Noted: Failure to Follow Procedures,To Review Mod Control Procedures & to Sufficiently Document Design Verification
Project stage: Request
ML20197C5981986-10-31031 October 1986
Review of Convection Heat Transfer Coefficients Utilized in Fort St Vrain Main Steam Line Break Analyses, Technical Evaluation Rept
Project stage: Other
ML20214Q0951986-11-25025 November 1986
Summary of 861027 Meeting W/Util to Discuss Schedule for Ie/Nrr Insp of Equipment Qualification Program.Attendance List & Viewgraphs Encl
Project stage: Meeting
ML20214U7071986-12-0202 December 1986
Summary of 861120 Meeting W/Util,Ornl,Ga Technologies & Eg&G Re Temp Profiles for Equipment Qualification.List of Attendees & Viewgraphs Encl
Project stage: Meeting
ML20215E4081986-12-12012 December 1986
Forwards Analyses of Three Steam Line Break Scenarios for Reactor Bldg & Three Scenarios for Turbine Bldg Using Convective Heat Transfer Coefficient of 1.0,per NRC 861120 Request
Project stage: Other
ML20215G1001986-12-19019 December 1986
Forwards Second Formal Submittal Re Turbine Bldg Temp Profiles Resulting from Steam Line Breaks,Per 861120 Request.Composite Temp Profile Curves Originally Submitted as Basis for Environ Qualification Program Appropriate
Project stage: Other
ML20207K4701986-12-31031 December 1986
Final Review of Convection Heat Transfer Coefficients Utilized in Fort St Vrain Main Steam Line Break Analysis, Technical Evaluation Rept
Project stage: Other
ML20207K4021987-01-0202 January 1987
Forwards Final FATE-86-117, Review of Convection Heat Transfer Coefficient Utilized in Fort St Vrain Main Steam Line Break Analysis, Technical Evaluation Rept,For Info
Project stage: Approval
ML20207Q4431987-01-16016 January 1987
Confirms 870126-30 Equipment Qualification Insp,Per 870113 Meeting at Region IV Ofcs.Mgt Entrance Meeting Scheduled for 870126 at Site Visitors Ctr & Exit Meeting Tentatively Scheduled for 870130 at Plant Site
Project stage: Meeting
ML20210P5241987-01-29029 January 1987
Forwards Draft Evaluation of Confinement Environ Temps Following High Energy Line Breaks Proposed for Fort St Vrain Environ Qualification Program, Technical Evaluation Rept,In Response to Util 861212 & 19 Submittals
Project stage: Draft Other
ML20210P6451987-01-31031 January 1987
Draft Evaluation of Confinement Environ Temps Following High Energy Line Breaks Proposed for Fort St Vrain Environ Qualification Program, Technical Evaluation Rept
Project stage: Draft Other
ML20211P4951987-02-25025 February 1987
Informs of Present Status & Plans Re Completion of Environ Qualification Program,Per Open Items Identified During 870130 Site Insp.Program & Implementing Procedures to Assure Environ Qualification in Place.Status of Open Items Encl
Project stage: Other
ML20212J2931987-02-26026 February 1987
Forwards Amend 50 to License DPR-34 & Safety Evaluation. Amend Changes Tech Specs Re Steam Line Rupture Detection/ Isolation Sys
Project stage: Approval
1986-11-25
[Table View] |
|
|---|
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
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
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
ML20247K4141989-09-15015 September 1989
Advises That Tech Specs Re Upgrade Program,Requested in NRC ,Must Be Approved by NRC Before Defueling
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
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
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
ML20245H3891989-08-0808 August 1989
Forwards Insp Rept 50-267/89-12 on 890601-0715 & Notice of Violation
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
ML20247M4521989-07-25025 July 1989
Forwards Request for Addl Info Re Reactor Defueling.Info Needed within 30 Days of Ltr Date
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
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
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
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
[Table view] |
Text
. _ _ _ . _ _
l o October 30, 1986 j Docket No. 50-267 DISTRIBUTION:
Mr. R. O. Williams, Jr. Docket File -
Vice President, Nuclear Operations ' NR C ' PDR " ~ ~
Public Service Company Local PDR of Colorado PBSS Rdg.
Post Office Box 840 PNoonan Denver, Colorado 80201-0840 KHeitner j 0 Lynch
Dear Mr. Williams:
H8erkow JCalvo
SUBJECT:
TEMPERATURE PROFILES FOR EQUIPMENT QUALIFICATION AT FORT ST.
VRAIN 1
~
We have reviewed your submittal dated February 28,1986(P-86120)providing information enabling us to perform independent calculations of the temperature profiles for equipment qualification at Fort St. Vrain (FSV).
4 Discussions were held with your staff via telephone on September 4 and 11, 1 and October 6, 1986 concerning this issue.
Enclosure 1 to this letter is a draft Technical Evaluation Report (TER) from our contractor, Pacific Northwest Laboratory (PNL). This draft TER addresses the specific details used in your calculation of the temperature profiles for FSV. Enclosure 2 contains a comparison of the results of PNL's independent calculations for your information. We have reviewed this draft TER and agree with its conclusions that the methods you used to i calculate the temperature profiles at Fort St. Vrain are not conservative.
! In view of the importance of this matter to the FSV equipment qualification program you should consider alternatives to address this issue. The staff is willing to meet with you in Bethesda, Maryltnd, to further discuss and resolve this issue on .1 priority basis.
4 The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, 1
Original signed by Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate l
Division of PWR Licensing-B Office of Nuclear Reactor Regulation
Enclosures:
As stated f
cc w/ enclosures:
See next page [
Q f Pf PBh g KHait.er:ac B
)Ly(J1ph PB h
HBe kow PBPE [l b JCalvo 86 10 /86 19f/(/86 10/ 7/86 10/fc/86 e611060260 e6103o 2 PDR ADOCK 05000267 P PDR
, n c.er o UNITED STATES g
d, o NUCLEAR REGULATORY COMMISSION
, y aj WASHINGTON, D. C. 20655
%...../ October 30, 1986
~
Docket No. 50-267 Mr. R. O. Williams, Jr.
Vice President, Nuclear Operations Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201-0840
Dear Mr. Williams:
SUBJECT:
TEMPERATURE PROFILES FOR EQUIPMENT QUALIFICATION AT FORT ST.
VRAIN i
We have reviewed your submittal dated February 28,1986(P-86120)providing information enabling us to perform independent calculations of the temperature profiles for equipment qualification at Fort St. Vrain (FSV).
Discussions were held with your staff via telephone on September 4 and 11, and October 6, 1986 concerning this issue.
Enclosure 1 to this letter is a draft Technical Evaluation Report (TER) from our contractor, Pacific Northwest Laboratory (PNL). This draft TER addresses the specific details used in your calculation of the temperature profiles for FSV. Enclosure 2 contains a comparison of the results of PNL's independent calculations for your information. We have reviewed this draft TER and agree with its conclusions that the methods you used to j calculate the temperature profiles at Fort St. Vrain are not conservative.
In view of the importance of this matter to the FSV equipment qualification program you should consider alternatives to address this issue. The staff is willing to meet with you in Bethesda, Maryland, to further discuss and resolve this issue on a priority basis.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, i
/ '
nn ch L. H tner, Project Manager btandardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosures:
See next page
0* .
Mr. R. O. Williams Public Service Company of Colorado Fort St. Vrain
- cc:
Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nuclear Engineering Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Colorado 80201 i Mr. David Alberstein,14/159A Mr. J. W. Gahm, Manager GA Technologies, Inc. Nuclear Production Division
- Post Office Box 85608 Public Service Company of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Mr. H. L. Brey, Manager
- Nuclear Licensing and Fuel Division Mr. L. W. Singleton, Manager i Public Service Company of Colorado Quality Assurance Division P. O. Box 840 Public Service Company of Colorado
- Denver, Colorado 80201 16805 Weld County Road 19-1/2 i Platteville, Colorado 80651 l Senior Resident Inspector
] U.S. Nuclear Regulatory Commission Mr. R. F. Walker i P. 0. Box 840 Public Service Company of Colorado Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 92138 Kelley, Stansfield & 0'Donnell Public Service Company Building Comitment Control Program Room 900 Coordinator 550 15th Street Public Service Company of Colorado Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-D Denver, Colorado 80211 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 i
Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300
- Denver, Colorado 80202-2413 4
- . . - - ,, .- - - . . . , . ,
