Letter Sequence Other |
---|
|
|
MONTHYEARML20083M9351984-04-12012 April 1984 Discusses Problems W/Pcrv Prestressing Sys & Resultant Insp Test Results.Liftoff Tests Show Tendon Sys Operable.Nrc Permission to Return to Power Operation from Present Refueling Outage Requested by 840418 Project stage: Other ML20084C5891984-04-16016 April 1984 Provides Advance Notification of Intent to Propose Tech Spec Changes to Circulation speed-high Trip Setting Listed in Table 4.4-3 & Surveillance Requirement SR 5.3.7 for Secondary Coolant Monitoring Project stage: Other ML20084H4571984-04-25025 April 1984 Forwards Relaxation Curves for Prestressed Concrete Reactor Vessel Tendon Sys,In Response to 840419 Request.No Immediate Mechanism for Controlling Sleeve Atmosphere Provided.Areas W/Indicated Corrosion Regreased Project stage: Other ML20084P5941984-05-0707 May 1984 Forwards Pcrv Tendon Sys Relaxation Curves Containing Min Design Lines,Per H Polk 840503 Telcon Request Project stage: Other ML20084Q4441984-05-10010 May 1984 Proposed Tech Spec Table 4.4-3, Instrument Operating Requirements for Plant Protective Sys,Circulator Trip. Significant Hazards Considerations Encl Project stage: Other ML20084Q4361984-05-10010 May 1984 Application to Amend License DPR-34,revising Tech Specs to Change Circulator speed-high Steam Trip Setting.Change Would Increase Circulator Availability While Providing for Initiation of Protective Actions Project stage: Request ML20084Q4221984-05-10010 May 1984 Forwards Application to Amend License DPR-34,revising Tech Specs to Change Circulator speed-high Steam Trip Setting (Table 4.4-3).Change Would Increase Circulator Availability While Providing for Initiation of Protective Actions Project stage: Request ML20092D9271984-06-15015 June 1984 Responds to Requesting Details of Proposed Tendon Surveillance Program.Program Consists of Load Cell Data & Visual Insps.Surveillance Started on 840601.Program Developed Using Reg Guide 1.35 as Ref Project stage: Other ML20092P6261984-06-26026 June 1984 Confirms Util Commitment to Fully Investigate 840623 Event in Which Six Control Rod Pairs Failed to Insert Into Core Under Automatic Velocity Limited free-fall Sys.Nrc Approval of Resolutions Will Be Obtained Prior to Reactor Startup Project stage: Other ML20090C5261984-07-0606 July 1984 Responds to NRC Concerns Re Fire Protection Review,Bldg 10 Licensing Requirements,Control Rod Failure to Scram, Documentation of Disciplinary Actions,Clearance Tags & Radiological Emergency Exercise Scenario,Per 840625 Meeting Project stage: Meeting ML20094D7741984-07-18018 July 1984 Informs of Control Rod & CRD Insp & Testing in Response to NRC 840709 Insp.Major Power Consumption & Scram Verification of All 37 CRD & Orifice Assemblies Completed & Insp Underway.Plan for Further Action Described Project stage: Other ML20093J1171984-07-20020 July 1984 Forwards Rev 2 to Updated FSAR for Fort St Vrain.Rev Includes Safety Evaluations Either in Support of License Amends or in Support of Conclusions That Changes Did Not Involve Unreviewed Safety Question Project stage: Request ML20094R4001984-08-0909 August 1984 Confirms 840806 Telcon on Tech Spec Change Request Re Tendon Corrosion & Anchor Assembly Surveillance.Tech Spec Change Request Will Be Submitted by 840930 Project stage: Other ML20096C9081984-08-20020 August 1984 Responds to Re Possible Design Mods to Pcrv Tendons & Details of Evaluations & Schedule of Completion of Repts Detailing Results of Metallurgical Exams.Actions Necessary to Evaluate Design Mods for Pcrv Listed Project stage: Other ML20096C0321984-08-21021 August 1984 Provides Findings & Positions Re Investigation of 840623 Failure of Six Control Rods to Automatically Insert Upon Scram.Summary of Work on Four CRDs & Description of Tests Encl.Corrective Actions Listed Project stage: Other ML20098B3051984-09-0707 September 1984 Ro:On 840904,while Removing CRD & Orifice Assembly,Motor Overcurrent Condition on Auxiliary Transfer Cask Shutters Occurred,Preventing Full Closure.Caused by One Control Rod String Not Fully Retracted.Work Temporarily Discontinued Project stage: Other ML20093K1941984-09-24024 September 1984 Submits Info Re Status of Damaged Control Rod Removal on Fuel Deck.Related Info Encl.Possibly Caused by Absorber Strings Not Fully Retracted,Despite Full Retract Limit Switch Indication Project stage: Other ML20107K2301984-10-18018 October 1984 Updates Tendon Investigations & Corrosion Prevention Programs.Efforts Concentrated on Corrosion Prevention Methods Rather than Detailed Moisture Measurements Project stage: Other ML20099K7271984-11-0808 November 1984 Provides Status of Control Rod Drive & Orificing Assembly (Crdoa) Refurbishing Efforts.Further Investigation of Crdoa Determined That Cause of Inability of Absorber String to Fully Retract Was Cable Failure Project stage: Other ML20112D7361984-12-14014 December 1984 Forwards Tendon Accessibility Info,Rationale for Tendon Surveillance & Info Re Corrosion Mechanism in Response to 840720 & 1029 Requests for Addl Info.Tendons Considered Acceptable If No Major Mods Necessary Project stage: Other ML20112C0491984-12-27027 December 1984 Responds to NRC 841025 Request for Addl Info Re 840510 Application for Amend to License DPR-34,revising Tech Spec Re Helium Circulators Overspeed Trip Setpoint.Analysis Value Encl Project stage: Request ML20112G5061985-01-0404 January 1985 Forwards Status of Planned Audit Response to NRC July 1984 Audit of Plant Operations,Per Denton .Repts Covering Technical Details of Listed Subjs Will Be Provided by 850131,per 841128 & 29 Meetings Project stage: Meeting ML20106B5311985-01-25025 January 1985 Advises That Util Will Perform Turbine Load Rejection from Full Load Test at End of Cycle 4.Tech Spec Amend Will Be Submitted Project stage: Other 05000267/LER-1984-008, Forwards Addl Info Re Three CRDs & Orifice Assemblies That Failed to Scram During in-core back-EMF Testing,Per 850122 Telcon.Suppl to LER 84-008 Will Be Provided1985-01-28028 January 1985 Forwards Addl Info Re Three CRDs & Orifice Assemblies That Failed to Scram During in-core back-EMF Testing,Per 850122 Telcon.Suppl to LER 84-008 Will Be Provided Project stage: Other ML20106B6131985-01-31031 January 1985 Discusses Visual Insp of Top Longitudinal Tendons,Per 850115 Meeting Request.Visual Insp of 30% of Longitudinal Tendons for Buttonheads Noted.Inconsistency Exists Between Last Mapping of Raised Buttonheads & Current Insp Results Project stage: Meeting ML20106B5791985-01-31031 January 1985 Submits Plans for Implementing Interim Tendon Surveillance Program,In Response to Concerns.Surveillance Program Will Be Based on Proposed Tech Spec SR 5.2.2,submitted in DW Warembourg Project stage: Other ML20106B5331985-01-31031 January 1985 Forwards Investigation Into Sources of Chloride in Fort St Vrain Primary Circuit. Rept Re Investigations of Effects of Chlorides on Major Components in Primary Circuit Will Be Sent by 850228 Project stage: Other ML20132G5021985-03-12012 March 1985 Evaluation of CRD Mechanism & Reserve Shutdown Sys Failures & Pcrv Tendon Degradation Issues Prior to Fort St Vrain Restart Project stage: Other ML20112G4631985-03-18018 March 1985 Forwards Ga Technologies,Inc Rept 907838, Investigation Into Sources of Chloride in Fort St Vrain Primary Circuit, Re Effects of Chloride on Major Components in Primary Circuit.Final Review & Clearance to Be Forwarded by 850326 Project stage: Other ML20100H1121985-03-26026 March 1985 Forwards Evaluation of Fort St Vrain Metallic Components Exposed to Primary Coolant Chloride Contamination, Per 850318 Commitment Project stage: Other ML20117M1211985-04-22022 April 1985 Amends 1,080 Amp/H Ref in to 1,058 Amp/H of Required Battery Capacity to Satisfy Load Profile Project stage: Other ML20117M0591985-04-26026 April 1985 Expresses Appreciation for Opportunity to Discuss Quality Aspects of CRD & Orifice Assembly (Crdoa) Refurbishment Program on 850424 in Arlington,Tx.Discusses 850418 Audit to Confirm 18 Crdoas Completed W/High Quality Project stage: Other ML20132C9781985-05-17017 May 1985 Safety Evaluation Re CRD Instrumentation Project stage: Approval ML20128N2861985-05-20020 May 1985 Informs of Intent to Conduct Addl Insps of Random Sample of Pcrv Bottom Head Longitudinal Tendon Anchor Assemblies. Thirty-four Longitudinal Bottom End Caps Accessible.Ten End Caps Will Be Removed & Inspected Project stage: Other ML20126B6291985-05-20020 May 1985 Responds to Commitment Log Item CL-1055 Re Verification of Operability of Surge Diodes on CRD Brake & Limit Switch Relays.Diodes & Functions Listed.Action Request DCAR-704 Initiated to Provide Relocation of Diodes Project stage: Other ML20128P6271985-05-23023 May 1985 Summary of 850516 Meeting W/Util Re Emergency Electrical Power Sys Concerns Resulting from Staff Evaluation of Problems from Testing Emergency Diesel Generators on 841218. Justification for Continued Operation Requested Project stage: Meeting ML20126C5211985-05-23023 May 1985 Discusses Investigation of Methods to Control Tendon Corrosion Involving Establishment of Nitrogen Blanket on Pcrv Tendon Sys.Establishing & Maintaining Overall Nitrogen Blanket Sys for Tendons Highly Questionable Project stage: Other ML20133E7491985-05-28028 May 1985 Requests Interim Evaluation Re Acceptability of Automatic & Manual Control of Emergency Electrical Power Sys by 850607, Per 850516 Meeting W/Util.Summary of Meeting Encl.W/O Encl Project stage: Meeting ML20127K1371985-06-0707 June 1985 Discusses Insp of 10 Bottom Longitudinal Tendon End Caps. Tendons Visually & Magnetic Particle Inspected for Evidence of Corrosion,Concavity,Water,Apparent Failures & Cracking.No Raised Buttonheads Found.All Tests Negative Project stage: Other ML20127K6371985-06-0707 June 1985 Forwards Interim Tech Specs for Control Rods for Use During Plant Startup.Specs Describe Program to Assure Control Rod & Reserve Shutdown Sys Reliability.Operating Limit of 250 F Max on Control Rod Motor Temp Anticipated Project stage: Other ML20127J8221985-06-0707 June 1985 Informs of Acceptability of Devcon 5-minute Epoxy for Use in Cementing Resistance Temp Detector Temp Sensors to CRD Cavity & Motor,Based on Test & Inservice Exposure of Epoxy to High Temps Project stage: Other ML20127L8851985-06-13013 June 1985 Forwards Results of Engineering Evaluation of Design Changes Introduced in CRD & Orifice Assembly Bearings.Physical Comparison Testing of Original & Replacement Shim Motor Bearings Underway to Establish Operating/Design Margins Project stage: Other ML20127N6551985-06-14014 June 1985 Responds to Concerns Raised During 850516 Meeting in Bethesda,Md Re Review of Emergency Electric Power Sys. Response Addresses Independence of Redundant Emergency Power Trains,Rapid Transfer Sys Testing & Switchgear Control Sys Project stage: Meeting ML20127N6951985-06-14014 June 1985 Elaborates on Util Commitments to Listed Plant Activities, Including CRD Mechanism Temp Recording,Requalification, Surveillance & Preventative Maint,Backup Reactor Shutdown Procedure,Tendons & Pcrv Integrity & Electrical Sys Project stage: Other ML20209E8991985-06-25025 June 1985 Discusses Status of CRD & Orificing Assembly (Crdoa) Refurbishment Efforts.First 37 Crdoas Refurbished & Installed.Summary of Design Changes & Test Results Encl Project stage: Other ML20132C9481985-07-0101 July 1985 Evaluation of CRD Orifice Assembly Bearing Rept from Public Svc Co of Co Project stage: Other ML20138A8071985-07-0202 July 1985 Forwards Updated Safety Evaluation Accepting Util Commitments Re Tendon Surveillance as Basis for Restart. Util Will Incorporate Modified Tendon Surveillance Program Into Tech Specs & Provide Results 6 Months After Restart Project stage: Approval ML20138A8551985-07-0202 July 1985 Safety Evaluation Accepting Util Tendon Surveillance Proposal.Proposal Will Lead to Maintaining Structural Integrity of Reactor Vessel.Plant Structurally Ready for Restart Project stage: Approval ML20132E6231985-07-0303 July 1985 Forwards Interim Tech Specs for Reactivity Control Sys.Tech Specs Will Provide Basis for Program to Assure CRD & Reserve Shutdown Sys Reliability.Specs Include Change to Criteria for Insertion of Reserve Shutdown Matl Project stage: Other ML20133D0241985-07-0505 July 1985 Safety Evaluation Supporting Emergency Electrical Sys,Per Problems Encountered During 841218 Testing of Emergency Diesel Generator Sets Project stage: Approval 1985-01-25
[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: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] |
Text
,_
PublicService reuo s.. .
Company of Colorado June 14, 1985 Fort St. Vrain Unit No. 1 P-85199 Regional Administrator Region IV lW@]Q@
y
]
U.S. Nuclear Regulatory Commission
)'
611 Ryan Plaza Drive, Suite 1000 R N I B 155 '
Arlington, Texas 76011 ?
d L ..._ .
Attention: Mr. Eric H. Johnson _J Docket No. 50-267
SUBJECT:
Additional Comitment Information
REFERENCES:
(1) NRC Letter, Denton to Walker, dated 10-16-84 (G-84392)
(2) PSC Letter, Lee to Johnson, dated 1-4-85 (P-85003)
(3) NRC Letter, Martin to Lee, 8507020085 850614 dated 1-17-85 (G-85024)
PDR ADOCK 05000267 F PDR (4) PSC Letter, Lee to Johnson dated 1-28-85 (P-85030)
Dear Mr. Johnson:
References (1) through (4) identify the NRC Assessment Report findings and the various PSC activities and comitments that must be completed in response to the Assessment Report.
Based on recent contacts with the NRC staff, PSC's comitments related to several Fort St. Vrain plant acti"ities require elaboration. Attachment 1 to this letter consolidates PSC's comitments related to the following areas: -
A. CRDM Temperature Recording and Requalification,
(
B. CRDM Surveillance and Preventive Maintenance, (W1 f g C. Backup Reactor Shutdown Procedure, c g D. Tendons and PCRV Integrity, t 7 E. Electrical Systems, and )
[]
m -
. *r .
F. Long Ter.n Issues.
If you have any questions concerning these issues, please contact Mr. M. H. Holmes at (303) 571-8409.
Very truly yours, H. L. Brey, Manager Nuclear Licensing and l Fuels Division i
, , /
HLB /MRS/sem l
J t
. Attachment 1
, , Page 1 of 4 ADDITIONAL COMMITMENT INFORMATION Note: References for this attachment are listed on page 4.
A. CRDM Temperature Recording and Requalification Per the interim Fort St. Vrain Technical Specifications for control rods, (reference 1), CRDM motor temperatures will be monitored to insure CRDM motor temperatures are less than 250 degrees Fahrenheit. In the event CRDM motor temperatures exceed l 215 degrees Fahrenheit, the temperatures will be recorded.
PSC has installed a multipoint recording device which provides frequent monitoring (at least one reading per minute) for each CRDM assembly motor temperature. Presently, PSC has a program underway to requalify CRDM motors for operating temperatures to 300 degrees Fahrenheit, (reference 2).
B. CRDM Surveillance and Preventive Maintenance l Current CRDM Surveillance and Preventive Maintenance Programs at l Fort St. Vrain are described in reference 3.
( Detailed CRDM curveillances and preventive maintenance l requirements have been included in the interim Fort St. Vrain l
I Technical Specifications for control rods, (reference 1). These surveillance actions will provide assurance that necessary Rod Position Indicators are operable and accurate.
In addition, PSC is determining the feasibility of developing enhanced surveillance tests and preventive maintenance practices.
This development effort will review CRDM surveillances and maintenance / overhaul experiences and results, and determine whether surveillance activities, schedules, or acceptance criteria can be improved. PSC's plans for developing enhanced surveillance tests and preventive maintenance practices will be submitted for NRC review within 6 months of plant restart.
. Attachment 1
, . Page 2 of 4 C. Backup Reactor Shutdown Procedure The requirements outlined in reference 1 will be incorporated into appropriate plant operating procedures including the necessary steps to be taken for reserve shutdown system (RSD) actuation. These procedures will require insertion of sufficient RSD material to achieve the required Shutdown Margin within one hour after determination that adequate Shutdown Margin does not exist, if the situation cannot be otherwise rectified within the one hour period.
D. Tendons and PCRV Integrity The current interim Fort St. Vrain revised Tendon Surveillance Program is outlined in reference 4. This program changes the previously proposed 18 month frequency for visual inspection to a six month frequency. The proposed program also establishes a control group of tendons to permit a aetter assessment of corrosion rate.
Additional inspections consist of examining the tendon end caps, prestressing anchor assembly stressing washer, shims, bearing plate, and buttonheads for evidence of general corrosion, concavity, water or other apparent failures. Recent examination results are described in references 5 and 6. Liftoff tests measuring the amount of load in the tendons are also being performed as described in reference 7.
PSC will provide the NRC with the results of the interim surveillance program every six months after plant restart.
Additionally, as part of the Technical Specification Upgrade Program, the requirements of the interim Tendon Surveillance Program will be incorporated into the Technical Specifications.
E. Electrical Systems Reference 8 contains PSC responses to NRC concerns from the recent electrical system review including 1) 4kV Rapid Transfer System, 2) Independence of Redundant Trains, 3) Testing of the 4kV Rapid Transfer System and 4) Switchgear Powering.
- Attachment 1
- Page 3 of 4 F. Long Term Issues Reference 9 contains PSC responses to the long term issues identified in the NRC Assessment Report of October 16, 1984.
Some of these issues have been completed, (e.g., CRD motor temperatures and Watt meter testing). The remaining issues are in progress and PSC will submit a schedule for their completion within two months of restart.
1 j
i
-l
,,-- - ---,,----,,--,-,--,,,,,,n,.---.-------v g
. Attachment 1
'. a. . Page 4 of 4 REFERENCES FOR ATTACHMENT 1
- 1. PSC Letter, Lee to Johnson, dated 6-7-85 (P-85180)
- 2. PSC Letter, Lee to Johnson, dated 1-30-85 (P-85032)
- 3. PSC Letter, Lee to Johnson, dated 1-31-85 (P-85040)
- 4. PSC Letter, Warembourg to Johnson, dated 3-5-85 (P-85071)
- 5. PSC Letter, Warembourg to Johnson, dated 5-20-85 (P-85176)
- 6. PSC Letter, Warembourg to Johnson, dated 6-7-85 (P-85193)
- 7. _PSC Letter, Warembourg to Johnson, dated 3-18-85 (P-85084)
- 8. PSC Letter, Warembourg to Johnson, dated 6-14-85 (P-85208)
- 9. PSC Letter, Lee to Johnson, dated 1-4-85 (P-85003) l
__ __ _-- _ --_-. _ _ ._ _ _- _ _ _ ___ __ _ ._ _ _ . - -_,