Letter Sequence Other |
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Results
Other: ML20137L915, ML20198K880, ML20198K899, ML20203E922, ML20204C493, ML20204E581, ML20206T869, ML20207Q604, ML20207R069, ML20210F539, ML20210G003, ML20210K842, ML20211B270, ML20211M464, ML20211P598, ML20211P612, ML20212H039, ML20213F038, ML20213F695, ML20213G414, ML20215K603, NL-86-672, Forwards Rev 1 to A-5415, Design Basis Rept, as Requested. Review of Current Emergency Feedwater Initiation & Control Sys Design Should Address Inconsistencies w/1983 SER Not Technical Adequacy
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MONTHYEARML20137L9151986-01-20020 January 1986 Comments on 851028 Commission Policy Statement on Engineering Expertise on Shift,Per NUREG-0737,Item I.A.1.1 Re Shift Technical Advisor.Util Pleased W/Incorporation of Technical Advisor Position in Operating Staff Project stage: Other ML20198K8801986-05-30030 May 1986 Forwards Smud Action Plan for Performance Improvement at Rancho Seco Nuclear Generating Station. Plan Provides Preliminary Results of Util Mgt Review of Implications of 851226 Overcooling Incident.Formal Plan Expected by 860703 Project stage: Other NUREG-0667, Forwards Request for Addl Info Re 860219,24 & 0312 Ltrs on 851226 Overcooling Transients & Corrective Actions.Startup Rept Should Include Info That NRC Identified as Necessary to Conduct Review1986-05-30030 May 1986 Forwards Request for Addl Info Re 860219,24 & 0312 Ltrs on 851226 Overcooling Transients & Corrective Actions.Startup Rept Should Include Info That NRC Identified as Necessary to Conduct Review Project stage: RAI ML20198K8991986-06-0202 June 1986 Smud Action Plan for Performance Improvement at Rancho Seco Nuclear Generating Station Project stage: Other ML20206H3941986-06-20020 June 1986 Summarizes NRC Concerns Expressed at 860610 Meeting Re Preliminary Version of Action Plan for Performance Improvement at Plant.Formal Plan Scheduled for Submittal on or About 860701 Should Resolve Listed Concerns Project stage: Meeting ML20203E9221986-06-30030 June 1986 Forwards Rev 4 to Updated FSAR for Prairie Island Nuclear Generating Plant.Two New Vols Provided for Reprinting of Apps of Original FSAR Project stage: Other ML20202G0431986-07-0303 July 1986 Discusses Systematic Assessment Program Portion of Performance Improvement Program,Per 860617 & 18 Discussions. Little Progress Made to Define & Implement Meaningful Sys Review & Test Program.Review of Program Suggested Project stage: Approval ML20206T8691986-07-0303 July 1986 Forwards Action Plan for Performance Improvement. Plan Addresses 851226 Event & Includes Prioritization Process Which Identifies Actions That Will Be Completed Before Restart.Review Requested Project stage: Other ML20204E5811986-07-17017 July 1986 Rev 1 to Instruction QCI-12, Plant Performance & Mgt Improvement Program Project stage: Other ML20204E5741986-07-21021 July 1986 Forwards Rev 1 to Instruction QCI-12, Plant Performance & Mgt Improvement Program, Per 860717 Meeting Request Project stage: Meeting ML20204C4931986-07-23023 July 1986 Responds to Retrospective Part of Issue 2a Re Completeness of Staff & Licensee Actions Associated W/Control Sys,Per Stello 860313 Memo to Denton in Response to Investigation of 851226 Incident.Issue 2a Closed Project stage: Other ML20212E9511986-07-29029 July 1986 Forwards General Comments on Util 860703 Action Plan for Performance Improvement.Prior to Scheduled 860814 Working Meeting W/Util,Staff Will Provide Addl Comments to Be Addressed in Meeting Agenda Project stage: Meeting ML20214N8311986-09-0505 September 1986 Forwards Request for Addl Info Re Util Action Plan for Performance Improvement & Preliminary List of Issues to Be Resolved in Electrical,Instrumentation & Control Portion of Proposed SER Project stage: RAI ML20210K8421986-09-12012 September 1986 Rev 1 to Design Basis Rept Project stage: Other ML20210G0031986-09-15015 September 1986 Forwards Amend 1 to Action Plan for Performance Improvement. Util Determined Installation of Emergency Feedwater Initiation & Control Sys Prior to Restart Feasible Project stage: Other ML20210G2431986-09-15015 September 1986 Forwards Audit Plan for Safety Evaluation of Facility Action Plan for Performance Improvement of Control Room Design & Spds.Audit Should Be Conducted in Early Oct to Preclude Impact on Proposed Restart Date Project stage: Approval NL-86-672, Forwards Rev 1 to A-5415, Design Basis Rept, as Requested. Review of Current Emergency Feedwater Initiation & Control Sys Design Should Address Inconsistencies w/1983 SER Not Technical Adequacy1986-09-26026 September 1986 Forwards Rev 1 to A-5415, Design Basis Rept, as Requested. Review of Current Emergency Feedwater Initiation & Control Sys Design Should Address Inconsistencies w/1983 SER Not Technical Adequacy Project stage: Other ML20215K6031986-10-16016 October 1986 Submits Results of Survey on Engineering Expertise on Shift. Findings of Survey Include That Plants Utilize Shift Technical Advisors That Are on-call & That Differences from Commission Policy Statement Handled on case-specific Basis Project stage: Other ML20213F6951986-11-0606 November 1986 Forwards non-nuclear Instrumentation & Instrumentation & Control Sys Schematics & Piping & Instrument Drawings,In Response to NRC 860530 Request Project stage: Other ML20213F0381986-11-0707 November 1986 Advises of Revised Schedule for Completion of NUREG-0737, Item III.D.3.4 Re Control Room Habitability.Provisions to Complete Item III.D.3.4 Will Be Implemented Prior to Startup from Current Outage Anticipated in Early May 1987 Project stage: Other ML20214L1841986-11-20020 November 1986 Summarizes 860929-1002 Site Visit to Gather Info for SER Supporting Restart.Util Response to Selected Items Encl. Application to Amend Tech Specs,Covering SPDS & Reg Guide 1.97 Will Be Submitted,Although Unnecessary for Restart Project stage: Request ML20211M4641986-12-0303 December 1986 Advises of Actions Taken in Response to Recent Burnout of Pressurizer Heater Bundle.Sessions Scheduled at Lynchburg Simulator During Feb 1987 to Polish Operator Skills & Awareness,Per Performance Improvement Action Plan Project stage: Other ML20211P7051986-12-11011 December 1986 Forwards Response to Request for Addl Info Re B&W Owners Group I&C Committee Preliminary Integrated Control Sys (ICS) Evaluation List.Loss of ICS/non-nuclear Instrumentation Procedures Will Be Submitted by 861231 Project stage: Request ML20211P5981986-12-15015 December 1986 Forwards Amend 2 to Action Plan for Performance Improvement. Amend Identifies Specific Actions Required for Accomplishment Prior to or During Restart Project stage: Other ML20211P6121986-12-31031 December 1986 Amend 2 to Action Plan for Performance Improvement Project stage: Other ML20212H0391987-01-12012 January 1987 Responds to Questions Discussed During 861216 Telcon Re SPDS & Main Feedwater (MFW) Indication in Control Room.Util Will Revise Action Plan,Section 4B.19 Re MFW Pump Trips Project stage: Other ML20207Q6041987-01-20020 January 1987 Advises of Future Plans to Take Reactor Out of Cold Shutdown & Proceed Through Heatup to Hot Shutdown Conditions,Based on Interpretation of 851226 Confirmatory Action Ltrs for pre-start Activities Project stage: Other ML20210F5391987-02-0303 February 1987 Confirms Telcon Re Arrangements for Evaluation of Requalification Program.Evaluation Visit Scheduled for Wk of 870504.Ref Matl Requirements for Program Evaluation & Requirements for Administration of Written Exams Encl Project stage: Other ML20211B2701987-02-11011 February 1987 Forwards Target Nuclear Organization for Restart (Transition Plan) for Review.Plan Provided to Facilitate Transition from Interim (Prestart) to Ultimate Nuclear Organization. Organizational Chart,Resumes & Position Descriptions Encl Project stage: Other ML20213G4141987-02-26026 February 1987 Advises That All Steps Necessary to Ensure That Reorganizational Efforts Do Not Adversely Impact Restart Schedule Taken,Per 870205 Request Project stage: Other ML20207R0691987-03-0303 March 1987 Advises That Plans to Proceed W/Sys Testing Program & Precriticality Startup Program,Including Hot Shutdown, Consistent W/Confirmatory Action Ltrs for Prestartup Activities.W/O Rept Project stage: Other ML20214L0191987-05-13013 May 1987 Forwards Request for Addl Info on Section 3.2.4 of Facility Restart Rept Re Steam Generator Overfill & Flooding of Main Steam Headers to Complete Review Project stage: RAI NUREG-1286, Forwards SER Re Restart Following 851226 Event (NUREG-1286). Requests Response to 870814 Request for Addl Info to Resolve Restart Issues1987-10-0707 October 1987 Forwards SER Re Restart Following 851226 Event (NUREG-1286). Requests Response to 870814 Request for Addl Info to Resolve Restart Issues Project stage: Approval ML20055C2051988-02-12012 February 1988 Forwards Safety Evaluation Supporting Util 871223 & 880211 Submittals Re Proposed Amends to Tech Specs (PA 155,Rev 2) for Plant.Salp Input Also Encl Project stage: Approval 1986-07-23
[Table View] |
Comments on 851028 Commission Policy Statement on Engineering Expertise on Shift,Per NUREG-0737,Item I.A.1.1 Re Shift Technical Advisor.Util Pleased W/Incorporation of Technical Advisor Position in Operating StaffML20137L915 |
Person / Time |
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Site: |
Fort Saint Vrain |
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Issue date: |
01/20/1986 |
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From: |
Gahm J PUBLIC SERVICE CO. OF COLORADO |
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To: |
Berkow H Office of Nuclear Reactor Regulation |
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References |
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RTR-NUREG-0578, RTR-NUREG-0660, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-660, RTR-NUREG-737, TASK-1.A.1.1, TASK-TM P-86047, TAC-61635, NUDOCS 8601280136 |
Download: ML20137L915 (4) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20205G8771999-03-26026 March 1999 Forwards Copy of Cover Page from Fort St-Vrain Welding Manual,Which Had Been Listed as Encl on Page 4 of 990325 Reply to EA 98-081.Cover Page Had Been Inadvertently Left Out with Original Reply ML20197H8811998-12-0101 December 1998 Forwards Proposed Change to Fsv ISFSI Physical Protection Plan in Which Commitment Is Made to Provide Feature to Security Posture for Facility ML20236R9191998-07-20020 July 1998 Ltr Contract:Mod 4 to Task Order 27, Task Area No 4 of Basic Contract - Fort St Vrain Insp Under Contract NRC-02-95-003 ML20199H8141997-11-21021 November 1997 Responds to Requesting Clarification as to Whether Increase in Tritium & Iron-55 Contamination Limits That Were Approved for Plant Apply to All Licensees ML20198K1931997-10-10010 October 1997 Provides Supplemental Info in Support of Util Proposed Rev to Physical Security Plan for Plant Plant Isfsi.Plan Withheld,Per 10CFR2.790(d) & 10CFR73.21 ML20198H5601997-09-16016 September 1997 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20141F3521997-05-14014 May 1997 Forwards Proposed Issue 4 of Physical Security Plan for Fort St Vrain ISFSI for Review & Approval.Encl Withheld,Per 10CFR2.790(d) ML20141C8611997-05-0909 May 1997 Informs of Approval of Fsv Final Survey Rept & Effluent Pathway Survey Plan & Supporting Analysis ML20141K9881997-05-0505 May 1997 Forwards Amend 89 to License DPR-34 & Supporting Safety Evaluation.Amend Designates All Elements of Approved Decommissioning Plan as License Termination Plan ML20138G2701997-04-28028 April 1997 Provides Response to NRC Comments Re Proposed Sampling & Survey Plan for Fsv Effluent Pathway.Response Documents Fsv Liquid Effluent Discharge Pathway Areas Are Acceptable for Release for Unrestricted Use IAW Draft NUREG/CR-5849 ML20148D4651997-04-24024 April 1997 Forwards Revised Interim Ltr Rept Which Describes Procedures & Results of Confirmatory Survey of Group E Effluent Discharge Pathway Areas at Fsv Station NUREG/CR-5849, Requests That Licensee Provide Evidence That Average Contamination Levels in Group E Effluent Discharge Pathway Areas Meet Averaging Criteria in Draft NUREG/CR-58491997-04-23023 April 1997 Requests That Licensee Provide Evidence That Average Contamination Levels in Group E Effluent Discharge Pathway Areas Meet Averaging Criteria in Draft NUREG/CR-5849 ML20138B0511997-04-22022 April 1997 Forwards Copy of Proposed Amend to Fsv NPDES Permit, Wastewater Discharge Permit CO-0001121 Requested to Support Repowering Activities,Iaw Section 3.2.d of Fsv Non-Radiological Ts,App B to License DPR-34 ML20140E1061997-04-10010 April 1997 Forwards Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20137S4481997-04-0808 April 1997 Informs That Decommissioning Activities at Fsv Are Complete & NRC Issued Exemption from Requirements of 10CFR50.54(w) in .Property Damage Insurance Policy Is Maintaned to Protect Fsv balance-of-plant Assets ML20137S0821997-04-0707 April 1997 Forwards Insp Rept 50-267/97-01 on 970310-11.No Violations Noted ML20137S1691997-04-0707 April 1997 Fifth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App K ML20137S5421997-04-0707 April 1997 Forwards Final Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Fort St Vrain Nuclear Station ML20148D5951997-04-0404 April 1997 Forwards Confirmatory Survey for Fsv Nuclear Station, Psc,Platteville,Co, Final Rept ML20137R6921997-04-0404 April 1997 Informs of Approval for Request for Addl 45 Days to Remedy Deficiencies Identified in NRC Re Financial Assurance Mechanism for Fsv Decommissioning Costs ML20137J8051997-03-31031 March 1997 Third Partial Response to FOIA Request for Documents.Records in App F Encl & Will Be Available in Pdr.App G & H Records Withheld in Part (Ref FOIA Exemptions 5 & 7) ML20148D5811997-03-26026 March 1997 Forwards Confirmatory Survey Plan for Group E Effluent Discharge Pathway Areas at Fsv Nuclear Station, Covered in Final Survey Rept,Vol 6 ML20137G7361997-03-25025 March 1997 Requests Addl Time for Util to Respond to NRC Comments in Re Financial Assurance Mechanism for Fort St Vrain Decommissioning Costs ML20137G9521997-03-24024 March 1997 Forwards Quarterly 10CFR50.59 Rept for Period 961201-970228 Re Changes,Tests & Experiments for Fort St Vrain Decommissioning ML20137H1131997-03-24024 March 1997 Second Partial Response to FOIA Request for Documents. Forwards Documents Listed in App D.Documents Also Available in Pdr.Documents Listed in App E Withheld in Part (Ref FOIA Exemption 6) ML20137C0181997-03-18018 March 1997 Documents That No Personnel Has Received Radiation Exposure at Fsv in 1997 or at Any Time Subsequent to ML20137C0061997-03-18018 March 1997 Documents That There Have Been No Activities Involving Release of Radioactive Matls from Fsv Nuclear Station That Potentially Could Have Affected Environ,Subsequent to Previous Radiological Envion Operating Rept ML20136G1201997-03-11011 March 1997 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1996 & Jan-Mar 1997. All Effluent Releases Completed as of 960703.Repts on Activities After 960703 Reflect Disposal of Solid Waste ML20136B1331997-02-28028 February 1997 First Partial Response to FOIA Request for Documents. Documents Listed in App a Already Available in Pdr.Forwards App B Documents.App C Documents Being Withheld in Entirety (Ref FOIA Exemption 5) ML20135D7891997-02-27027 February 1997 Forwards Responses to Comments Re Fort St Vrain Final Survey Rept ML20135D9531997-02-27027 February 1997 Forwards Copy of Amend to Util Npdes,Wastewater Discharge Permit CO-0001121,which Clarifies That Monitoring of Farm Pond Outlet Required When Industrial Wastewater Being Discharged Through Upstream Goosequill Ditch ML20135A8711997-02-14014 February 1997 Requests That Encl Deficiencies Identified in Financial Assurance Mechanism for Fort St Vrain Decommissioning Cost Be Addressed within 45 Days ML20134D1551997-01-31031 January 1997 Forwards Util Responses to NRC Comments Provided in NRC Ltr Re Sampling & Survey Plan Used for Final Radiological Survey of Liquid Effluent Pathway at Ft St Vrain ML20134C8481997-01-30030 January 1997 Forwards Draft Confirmatory Survey Rept for Fsv Nuclear Station,Psc,Platteville,Co Providing Info on Essap Activities on 960930-1003 ML20133L4961997-01-0707 January 1997 Forwards Comments That Need to Be Resolved Before Final Approval of Util Submittal Entitled, Proposed Sampling & Survey Plan for Effluent Pathway,Ft St Vrain Final Survey Program ML20133E0481997-01-0202 January 1997 Forwards Comments to Fsv Nuclear Station, Decommissioning Project Final Survey Rept (Volumes 4-11), for Consideration ML20132G0421996-12-23023 December 1996 Forwards Insp Rept 50-267/96-05 on 961203-05.No Violations Noted ML20132F2841996-12-19019 December 1996 Forwards Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Plant,Covering Period of 960901-1130 ML20133A8591996-12-16016 December 1996 Forwards Original & Copy Transcripts of Public Hearing,Held on 961203 in Platteville,Co Re Decommissioning & License Termination of Util Ft Saint Vrain Nuclear Generating Station ML20133N0011996-12-0404 December 1996 Recommends That NRC Require License to Modify Submission of Unexecuted Draft Trust Agreement Remaining Decommissioning Costs for Ft St Vrain Nuclear Generating Station in Listed Ways ML20135B3861996-11-25025 November 1996 Informs That NRC Reviewed Util 961114 Submittal (P-96096) Entitled, Fort St Vrain Final Emergency Response Plan, & Meets Requirements of 10CFR50.54(q) ML20135A5861996-11-25025 November 1996 Submits Suppl Info Re Annual Environ Rept for 1995 Operation of Fsv ISFSI ML20135A6361996-11-20020 November 1996 Submits Copy of Describing Discharge Practices for Groundwater Seeping Into Fsv'S Reactor Building Sump ML20134L4721996-11-14014 November 1996 Notifies NRC That Util Adopted Fsv ISFSI Emergency Response Plan to Direct Emergency Response for Radiological Accidents Occuring at Site,Until 10CFR50 License Is Terminated ML20134F4351996-10-30030 October 1996 Forwards Sections 1,2,6 & 8 from Survey Packages F0015, F0039 & F0126 & Sections 1,2 & 6 from Survey Package F0115 to Support on-site NRC Insp ML20134G5991996-10-30030 October 1996 Forwards Volumes 1-12 to Final Survey Rept for Groups A,B,C Rev 1,D Rev 1,E,F Rev 1 & G-J for NRC Approval in Support of Forthcoming Request for Termination of Fsv 10CFR50 License ML20133D7691996-10-22022 October 1996 Forwards Preliminary Rept Re Orise Support of NRC License Insp at Fsv on 960930-1003 ML20136B1411996-10-15015 October 1996 FOIA Request for Documents Re NOV Addressed to Scientific Ecology Group Re NRC Insp Rept 50-267/94-03 & OI Investigation Repts 4-94-010 & 4-95-015 ML20128M6181996-10-0404 October 1996 Forwards Ltr from PSC to Co Dept of Public Health & Environ Describing Monitoring Practices at Plant ML20128G8041996-10-0101 October 1996 Forwards Fsv Decommissioning Fire Protection Plan Update 1999-03-26
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20205G8771999-03-26026 March 1999 Forwards Copy of Cover Page from Fort St-Vrain Welding Manual,Which Had Been Listed as Encl on Page 4 of 990325 Reply to EA 98-081.Cover Page Had Been Inadvertently Left Out with Original Reply ML20197H8811998-12-0101 December 1998 Forwards Proposed Change to Fsv ISFSI Physical Protection Plan in Which Commitment Is Made to Provide Feature to Security Posture for Facility ML20198K1931997-10-10010 October 1997 Provides Supplemental Info in Support of Util Proposed Rev to Physical Security Plan for Plant Plant Isfsi.Plan Withheld,Per 10CFR2.790(d) & 10CFR73.21 ML20141F3521997-05-14014 May 1997 Forwards Proposed Issue 4 of Physical Security Plan for Fort St Vrain ISFSI for Review & Approval.Encl Withheld,Per 10CFR2.790(d) ML20138G2701997-04-28028 April 1997 Provides Response to NRC Comments Re Proposed Sampling & Survey Plan for Fsv Effluent Pathway.Response Documents Fsv Liquid Effluent Discharge Pathway Areas Are Acceptable for Release for Unrestricted Use IAW Draft NUREG/CR-5849 ML20148D4651997-04-24024 April 1997 Forwards Revised Interim Ltr Rept Which Describes Procedures & Results of Confirmatory Survey of Group E Effluent Discharge Pathway Areas at Fsv Station ML20138B0511997-04-22022 April 1997 Forwards Copy of Proposed Amend to Fsv NPDES Permit, Wastewater Discharge Permit CO-0001121 Requested to Support Repowering Activities,Iaw Section 3.2.d of Fsv Non-Radiological Ts,App B to License DPR-34 ML20140E1061997-04-10010 April 1997 Forwards Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20137S4481997-04-0808 April 1997 Informs That Decommissioning Activities at Fsv Are Complete & NRC Issued Exemption from Requirements of 10CFR50.54(w) in .Property Damage Insurance Policy Is Maintaned to Protect Fsv balance-of-plant Assets ML20137S5421997-04-0707 April 1997 Forwards Final Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Fort St Vrain Nuclear Station ML20148D5951997-04-0404 April 1997 Forwards Confirmatory Survey for Fsv Nuclear Station, Psc,Platteville,Co, Final Rept ML20148D5811997-03-26026 March 1997 Forwards Confirmatory Survey Plan for Group E Effluent Discharge Pathway Areas at Fsv Nuclear Station, Covered in Final Survey Rept,Vol 6 ML20137G7361997-03-25025 March 1997 Requests Addl Time for Util to Respond to NRC Comments in Re Financial Assurance Mechanism for Fort St Vrain Decommissioning Costs ML20137G9521997-03-24024 March 1997 Forwards Quarterly 10CFR50.59 Rept for Period 961201-970228 Re Changes,Tests & Experiments for Fort St Vrain Decommissioning ML20137C0061997-03-18018 March 1997 Documents That There Have Been No Activities Involving Release of Radioactive Matls from Fsv Nuclear Station That Potentially Could Have Affected Environ,Subsequent to Previous Radiological Envion Operating Rept ML20137C0181997-03-18018 March 1997 Documents That No Personnel Has Received Radiation Exposure at Fsv in 1997 or at Any Time Subsequent to ML20136G1201997-03-11011 March 1997 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1996 & Jan-Mar 1997. All Effluent Releases Completed as of 960703.Repts on Activities After 960703 Reflect Disposal of Solid Waste ML20135D7891997-02-27027 February 1997 Forwards Responses to Comments Re Fort St Vrain Final Survey Rept ML20135D9531997-02-27027 February 1997 Forwards Copy of Amend to Util Npdes,Wastewater Discharge Permit CO-0001121,which Clarifies That Monitoring of Farm Pond Outlet Required When Industrial Wastewater Being Discharged Through Upstream Goosequill Ditch ML20134D1551997-01-31031 January 1997 Forwards Util Responses to NRC Comments Provided in NRC Ltr Re Sampling & Survey Plan Used for Final Radiological Survey of Liquid Effluent Pathway at Ft St Vrain ML20134C8481997-01-30030 January 1997 Forwards Draft Confirmatory Survey Rept for Fsv Nuclear Station,Psc,Platteville,Co Providing Info on Essap Activities on 960930-1003 ML20133E0481997-01-0202 January 1997 Forwards Comments to Fsv Nuclear Station, Decommissioning Project Final Survey Rept (Volumes 4-11), for Consideration ML20132F2841996-12-19019 December 1996 Forwards Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Plant,Covering Period of 960901-1130 ML20133A8591996-12-16016 December 1996 Forwards Original & Copy Transcripts of Public Hearing,Held on 961203 in Platteville,Co Re Decommissioning & License Termination of Util Ft Saint Vrain Nuclear Generating Station ML20133N0011996-12-0404 December 1996 Recommends That NRC Require License to Modify Submission of Unexecuted Draft Trust Agreement Remaining Decommissioning Costs for Ft St Vrain Nuclear Generating Station in Listed Ways ML20135A5861996-11-25025 November 1996 Submits Suppl Info Re Annual Environ Rept for 1995 Operation of Fsv ISFSI ML20135A6361996-11-20020 November 1996 Submits Copy of Describing Discharge Practices for Groundwater Seeping Into Fsv'S Reactor Building Sump ML20134L4721996-11-14014 November 1996 Notifies NRC That Util Adopted Fsv ISFSI Emergency Response Plan to Direct Emergency Response for Radiological Accidents Occuring at Site,Until 10CFR50 License Is Terminated ML20134F4351996-10-30030 October 1996 Forwards Sections 1,2,6 & 8 from Survey Packages F0015, F0039 & F0126 & Sections 1,2 & 6 from Survey Package F0115 to Support on-site NRC Insp ML20134G5991996-10-30030 October 1996 Forwards Volumes 1-12 to Final Survey Rept for Groups A,B,C Rev 1,D Rev 1,E,F Rev 1 & G-J for NRC Approval in Support of Forthcoming Request for Termination of Fsv 10CFR50 License ML20133D7691996-10-22022 October 1996 Forwards Preliminary Rept Re Orise Support of NRC License Insp at Fsv on 960930-1003 ML20136B1411996-10-15015 October 1996 FOIA Request for Documents Re NOV Addressed to Scientific Ecology Group Re NRC Insp Rept 50-267/94-03 & OI Investigation Repts 4-94-010 & 4-95-015 ML20128M6181996-10-0404 October 1996 Forwards Ltr from PSC to Co Dept of Public Health & Environ Describing Monitoring Practices at Plant ML20128G8041996-10-0101 October 1996 Forwards Fsv Decommissioning Fire Protection Plan Update ML20128G0481996-09-30030 September 1996 Submits Rev to Psco Definitions of Contents of Documentation Packages Re Fsv Final Survey Project ML20129C0421996-09-20020 September 1996 Forwards Quarterly Submittal of 10CFR50.59 Rept of Changes, Tests & Experiments for Facility Decommissioning,Covering Period of 960601-0831 ML20133D7601996-09-16016 September 1996 Forwards Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project,First Final Survey Rept Submittal- Vols 1-5.NRC Comments Incorporated.Spending Plan Attached ML20117P0711996-09-13013 September 1996 Describes Util Plans to Remove Bldg 28 from Plant Facility ML20129A4431996-09-11011 September 1996 Describes Util Plans for Demonstrating That Liquid Effluent Pathway & Surrounding Open Land Areas Satisfy 10 Mrem/Yr Criteria Provided in Plant Final Survey Plan ML20117K5291996-09-0404 September 1996 Provides Notification That Util Will Be Revising Financial Assurance Mechanism That Will Be Used to Cover Remaining Costs of Decommissioning Plant ML20117C7281996-08-22022 August 1996 Discusses Impact of Final Decommissioning Rule & Requests NRC Concurrence That Requirements to Submit & Obtain Approval of License Termination Plan Have Been Satisfied ML20116P3431996-08-16016 August 1996 Describes Actions to Remove Structures & Equipment Items from Fort St Vrain Facility for NRC Info.Requests That NRC Advise Util of Wishes to Perform Confirmatory Survey of Any Parts of New Fuel Storage Building Before 960903 ML20133D7551996-08-14014 August 1996 Provides Environ Survey & Site Assessment Program'S (Essap) Comments Re Review of Fsv Nuclear Station Decommissioning Project Final Survey Rept ML20116M0771996-08-14014 August 1996 Provides Suppl Response to Re Insp Rept 50-267/96-01 in Jan 1996 Re NRC Concerns About Fsv Final Survey Program.Specifically,Bias in Instrumentation Response Overestimating Amount of Contamination Present ML20116M1841996-08-13013 August 1996 Forwards Util Responses to NRC Comments in Re Use of in-situ Gamma Spectroscopy to Measure Exposure Rates During Plant Final Survey.Approval to Use in-situ Gamma Spectroscopic instrument,Microspec-2,requested ML20116K0061996-08-0909 August 1996 Submits Fort St Vrain Nuclear Station Decommissioning Project Final Survey Rept ML20116M1241996-08-0808 August 1996 Responds to NRC Bulletin 96-004, Chemical,Galvanic,Or Other Reactions in Spent Fuel Storage & Transportation. Informs That Modular Vault Dry Storage Sys Is Not Susceptible to Problems Addressed in Bulletin ML20116F3611996-08-0202 August 1996 Submits Revised Documentation for Fort St Vrain Final Survey Program ML20116F8141996-08-0202 August 1996 Informs of Util Intent to Modify Fort St Vrain Control Room,Which Will Make Certain Final Survey Locations Unavailable for Further Review.Final Survey Efforts Are Complete ML20116A4511996-07-19019 July 1996 Requests NRC Approval of Proposed Method to Fsv Final Survey Plan to Determine Exposure Rates in Prestressed Concrete Reactor Vessel 1999-03-26
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059H9471990-09-14014 September 1990 Forwards Rev to Proposed Physical Security Plan,Per .Encl Withheld (Ref 10CFR73.21) ML20064A6841990-09-14014 September 1990 Notifies That Ms Frazier License OP-5608-1 Terminated Effective 900906,per 10CFR50.74 ML20059K2091990-09-14014 September 1990 Requests That Dj Trumblee Reactor Operator License Be Terminated,Effective 900912 ML20059L5831990-09-14014 September 1990 Forwards Application for Amend to License DPR-34,changing Tech Spec Design Features Section to Remove CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20059D3231990-08-15015 August 1990 Forwards fitness-for-duty Performance Data Rept for Plant ML20058N5661990-08-0808 August 1990 Requests Exemption from 10CFR50.54(w)(1) Requirements for Min Property Insurance Coverage ML20058L8031990-08-0303 August 1990 Forwards GA-C18103, Fort St Vrain Cycle 3 Core Performance, Per Request for Addl Info Re Proposed Amend to Tech Spec Which Would Allow Util to Complete Defueling of Facility ML20058M1931990-07-31031 July 1990 Advises of Termination of Kj Einig Reactor Operator License, Effective 900727 ML20056A1791990-07-30030 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-267/90-07.Corrective Actions:Electrical & Mechanical Craft Personnel Assigned to Planning & Scheduling Organization ML20055H8091990-07-23023 July 1990 Forwards Addl Info in Support of 900622 SAR for Isfsi. Proprietary SAR Withheld (Ref 10CFR2.790) ML20056A1711990-07-20020 July 1990 Discusses Decommissioning Funding for Plant.Util Revised Decommissioning Financial Plan,Based on Safstor,Currently in Effect & Funds Will Be Accumulated Per Plan Provisions ML20055H6571990-07-20020 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Model 1153 or 1154 Transmitters Presently in Use at Plant ML20058P6891990-07-20020 July 1990 Forwards Security Plan for Proposed ISFSI for NRC Review,Per 900622 & 0412 Ltrs.Plan Withheld (Ref 10CFR73.21) ML20055G8601990-07-20020 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-267/90-07.Corrective Actions:Site Mgt Recognized Applicability of 10CFR50.72(b)(2)(vi) Re Previous Day Notification & Immediately Notified NRC ML20055H2811990-07-20020 July 1990 Forwards Rev 4 to Updated Fire Protection Plan ML20055G7061990-07-20020 July 1990 Forwards Application for Amend to License DPR-34,revising Tech Spec 6.1 to Remove Equipment to Support Plant Closure ML20059D1361990-07-13013 July 1990 Applies for Exemption from Payment of Annual Fees for FY90, Per 10CFR171 ML20055E0401990-07-0303 July 1990 Forwards Issue 3 to FPOR-18, Fire Protection Operability Requirements, as Result of Rev 3 to Facility Fire Protection Plan ML20055E0331990-07-0202 July 1990 Informs of Plans to Remove B Helium Circulator from Plant Prestressed Concrete Reactor Vessel in Mannner Similar to Previous Circulator Maint Outages.Requests Timely Ack of NRC Concurrence W/Undertaking ML20055E9171990-06-29029 June 1990 Resubmits Semiannual Radioactive Effluent Release Rept Jul-Dec 1989, as Result of Omitted Tables ML20044A8281990-06-29029 June 1990 Notifies of Termination of Wj Ashmore,License SOP-43244 & Requests That Reactor Operator License Be Terminated Effective 900620,per 10CFR50.74 ML20055D3931990-06-29029 June 1990 Forwards Response to Generic Ltr 90-04,requesting Info on Status of Generic Safety Issues.W/O Encl ML20055D1591990-06-22022 June 1990 Forwards Proposed Change to Updated Fsar,App B Re Use of Controls Other than Change Notice Sys to Implement Mods Such as Cutting & Capping of Piping,In Order to Obtain Positive Equipment Isolation ML20043J0581990-06-15015 June 1990 Forwards Proposed Issue 5 to Fort St Vrain Nuclear Generating Station Defueling Emergency Response Plan, Deleting Offsite Emergency Response Capabilities,Per Util 890816 Defueling SAR & NUREG-0654 ML20043D3291990-05-25025 May 1990 Forwards Response to NRC 900330 Ltr Re Violations Noted in Insp Rept 50-267/90-04.Encl Withheld (Ref 10CFR73.21) ML20055D2051990-05-25025 May 1990 Responds to Violations Noted in Insp Rept 50-267/90-06. Corrective Actions:Extensive Training on Radiological Emergency Response Plan Implementing Procedures Will Be Provided to Operating Crews Beginning in May 1990 ML20043C8981990-05-25025 May 1990 Responds to NRC 900427 Ltr Re Violations Noted in Insp Rept 50-267/90-05.Corrective Actions:Mgt Will Continue to Stress Requirement for Procedural Compliance on Ongoing Basis ML20043B3691990-05-22022 May 1990 Describes Util Current Plans for Removal of Certain Plant Equipment Items.Components to Be Removed Have No Required Nor Useful Function During Planned or Postulated Remaining Defueling or Shutdown Conditions ML20043A9491990-05-11011 May 1990 Forwards Issue 59 to AOP-K-1, Environ Disturbances - Earthquake. ML20042F9771990-05-0404 May 1990 Forwards Assessment of Possible Sources of Water in Plant Core,Means of Detecting Water in Pcrv & Effects of Water Ingress on Reactivity,For Info ML20042F9011990-05-0101 May 1990 Forwards Conceptual Plan & Cost Estimates for Early Dismantlement of Fort St Vrain Pcrv, Per NRC 900315 Request ML20042E8911990-04-27027 April 1990 Requests 30-day Extension to 900529 to Submit Response to Violations Noted in Insp Rept 50-267/90-04 ML20042F3111990-04-26026 April 1990 Forwards Application to Amend License DPR-34,providing Tech Spec Changes Needed to Complete Defueling ML20012D4711990-03-19019 March 1990 Requests Approval of Encl Exemption Request Allowing Util to Accumulate Decommissioning Funds Beyond Termination of Operations ML20012B7541990-03-0707 March 1990 Informs of Electronic Transfer of Fees on 900307 for Invoice IO547 ML20011F4691990-02-22022 February 1990 Responds to NRC 900116 Ltr Re Violations Noted in Insp Rept 50-267/89-23.Violation Re Fire Doors 13 & 9 Between 480-volt Ac Switchgear Room & Bldg 10 Propped Open on 891129 Disputed.Improved Communications Underway ML20006E7821990-02-15015 February 1990 Forwards Responses to 891004 Questions Re Decommissioning Financial Plan ML20011E8941990-02-0707 February 1990 Responds to 890719 NRC Bulletin 89-002 Re safety-related Anchor/Darling Model S350W Swing Check Valves.Licensee Reviewed Plant Data Base & Design Documents & Concludes That No Anchor/Darling Model S350W Valves Installed at Plant ML20011E7861990-02-0707 February 1990 Forwards Overview of Evaluation on Compliance W/Environ Qualification Regulation (10CFR50.49) During Defueling of Facility.During Defueling,Pcrv Will Be Maintained at Nearly Atmospheric Pressures & Rapid Depressurization Not Possible ML20011E5031990-02-0606 February 1990 Notifies of Termination of Ma Rhoton Employment W/Util, Effective 900206 ML20006D6621990-02-0606 February 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Currently Established Preventive Maint & Tech Spec Surveillance Activities on HXs Remaining in Svc Will Continue ML20006B2091990-01-26026 January 1990 Forwards Fire Operability Requirements 3 & 14,Issues 3 & 4, Respectively,To Fire Protection Program Plan,Section FP.6.1. Changes Cover Halon Sys & Basis & Records Ctr Halon Sys ML20006B7791990-01-25025 January 1990 Forwards Application for Amend to License DPR-34,changing Section 7.1 of Tech Specs.Specifically,Senior Vice President,Nuclear Operations Revised to Vice President, Nuclear Operations & Nuclear Training Manager Revised ML20006A5001990-01-19019 January 1990 Notifies of Util Intent to Bore 10 Concrete Core Drills Into Prestressed Concrete Reactor Vessel Barrel Section at Various Elevations Found Necessary for Decommissioning Planning.Drillings Wil Begin on 900205.Assessment Encl ML20006A5041990-01-19019 January 1990 Responds to NRC 891218 Ltr Re Weaknesses Noted in Insp Rept 50-267/89-22.Corrective Actions:During Power Operations Three Licensed Reactor Operators Will Be Present in Control & Short in Emergency Public Address Sys Repaired ML20005G5001990-01-12012 January 1990 Forwards Approved Proposed Change to NPDES Permit to Use Halocide Product for Microbiological Control in Smaller Cooling Tower ML19354D8581990-01-0505 January 1990 Forwards Safety Assessment of Proposed Changes to Fire Protection Program Plan,Per P Erickson Request.Changes Cover Acceptance Criteria for Shutdown Cooling Following Fire & New Fire Protection Cooldown Trains 1 & 2 ML20005F5531990-01-0303 January 1990 Certifies That Util Has Implemented fitness-for-duty Program Meeting 10CFR26 Requirements ML20005D8921989-12-21021 December 1989 Forwards Proposed Change to Plant NPDES Permit ML19354D7441989-12-0808 December 1989 Requests Relief from Requirements of Generic Ltr 89-10 Re motor-operated Valves Since Plant Permanently Shut Down Since 890818 & Defueling Initiated on 891127 1990-09-14
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16805 WCR 19 1/2, Platteville, Colorado 80651 January 20, 1986 Fort St. Vrain Unit No. 1 P-86047 Director of Nuclear Reactor _ Regulation U.S. Nuclear Regulating Commission Washington, D.C. 20555 ATTN: Mr. H.N. Berkow, Project Director Standardization and Special Projects Directorate Docket No. 50-267
SUBJECT:
COMMISSION POLICY STATEMENT ON ENGINEERING EXPERTISE ON SHIFT
REFERENCES:
(1 ) P-79305, Warembourg to Varga, December 18, 1979 (2 ) G-80049, Speis to Fuller, Received March 31, 1980 (3 ) P-80444, Warembourg to Eisenhut, December 30, 1980 (4 ) G-81142, Miller to Lee, August 6, 1981 (5 ) G-81175, Miller to Lee, October 2, 1981 (6 ) P-81271, Lee to Miller, October 30, 1981 (7 ) G-81223, Kuzmycz to Lee, November 9, 1981 (8 ) G-82080, Clark to Lee, March 19, 1982 (9 ) P-82112, Lee to Clark, April 20, 1982 (10) G-83369, Wagner to Lee, October 13, 1983
Dear Mr. Berkow:
On October 28, 1985, the Nuclear Regulatory Commision published in the Federal Register (43621), the " Commission Policy Statement on Engineering Expertise on Shift." The purpose of this policy statement was to present the Commission's policy "with respect to ensuring that adequate engineering and accident assessment expertise is possessed by the operating staff at a nuclear power plant." This policy presents licensees with two options for providing the requisite engineering expertise on shift.
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~2-Option 1 of this policy statement provided for a " combined SR0/STA-Position" in order to meet this need, and option 2 allowed the
" continued use of the STA position." The purpose of this letter is to discuss the position of Public Service Company of Colorado with regard to the aforementioned policy statement.
Public Service Company of Colorado intends to continue its use of a Technical Advisor (TA) position to meet this ongoing need. The Technical Advisor position has been in use at Fort St. Vrain since early 1980, when, in response to NUREG-0578 Item 2.2.1.b and NUREG-0660 Item I.A.1.1, three engineers were placed on call to the Operations Department with a one hour maximum response time as-discussed in Reference 1.
On March 20, 1980, the Commission staff transmitted to PSC the results of their evaluaticn of the implementation of " Category A" Lessons Learned requirements (Reference 2). In the discussion of Item 2.2.1.b, the Fort St. Vrain Technical Advisor position was found acceptable as follows:
"The program that the licensee has implemented to satisfy the STA accident assessment function utilizes three engineers who are placed on-call to respond to potential accident conditions at the
~
plant. The licensee has committed to a one-hour response time for the on-call STA, in contrast to the staff's position for a 10 minute response time. We have considered the licensee's argument.
for the relatively long times (i.e., hours) for accident conditions to develop' in a gas cooled reactor versus a significantly shorter time for light water reactors. Considering this unique feature of a gas cooled reactor the staff finds the one-hour response time acceptable.for Fort St. Vrain. The three STA engineers will also fulfill the required operating experience assessment function required by NUREG-0578.
"We have reviewed the licensee's October 29 and December 12, 1979, submittals describing their STA program. In addition, during the site visit we discussed the program with the licensee and determined that a satisfactory STA program is in operation.
We find that their STA program satisfies the staff's requirements described in Section 2.2.1.b of NUREG-0578 and is therefore acceptable."
_ a ._. _ .__ _ __ _. _ _ . , _
4 In November 1980, the Nuclear Regulatory Commision issued NUREG-0737 which, in Item I.A.1.1, endorsed the Shift Technical Advisor position as a requirement for the operating staff as described in Item 2.2.1.b of NUREG-0578 and Item I.A.I.1 of NUREG-0660. Public Service Company of Colorado responded to the NUREG-0737 Item I.A.I.1 in detail via correspondence to the Commission (Reference 3). In that letter, the Fort St. Vrain training program for Technical Advisors was discussed, as well as the duties, responsibilities, accountability, and qualification requirements for the Fort St. Vrain Technical Advisor position. In addition, the long range plans for the Technical Advisor position at Fort St. Vrain were clarified, as required by NUREG-0737. Public Service Company of Colorado stated its intent to:
"1. Retain the TA's as permanent Fort St. Vrain staff for the duration of operating license in lieu of upgrading SR0's to a college level engineering degree.
"2. Upgrade the operator and SRO training and requalification requirements to include courses in heat transfer, fluid flow, and thermodynamics as well as other upgrading as outlined in Attachment 5 [to P-80444], but retain the Technical Advisors as the college level expertise rather than providing this expertise to the operator."
On August 6, 1981, the Commission issued an Order confirming PSC's commitments to Three Mile Island Action Plan related items (Reference 4). In that letter, the Commission granted acceptance of the Fort St. Vrain Technical Advisor position _as follows:
"The licensee has agreed to the requirements of Item 1.A.1.1 (sic), ' Shift Technical Advisor' with the exception that instead of the staff's position for a 10 minute response time, the-licensee has committed to a one hour response time for the on-call STA. Considering the unique features of gas cooled reactor, i.e., long times for accident conditions to develop, the staff finds the one hour response time acceptable for the Fort St. Vrain Nuclear Generating Station."
The Commission staff, on October 2, 1981, via Reference 5 transmitted the determination that the " Shift Technical Advisor section should be included in the Technical Specifications...The bases for this determination is contained in our" (the NRC's) " March 20, 1980, letter to Public Service." In response to that request, PSC submitted a request for an amendment to the Fort St. Vrain Technical Specifications (Reference 6) to include the Technical Adviso'r position in section AC 7.1.1 as part of the operating staff, and to place a requirement for a one hour response time capability. This amendment was issued by the Commision as Amendment No.24 to the Facility Operating License on November 9,1981 (Reference 7).
e On March 19, 1982, PSC was advised of the results of a post-implementation review of Shift Technical Advisor training programs (Reference 8). In that letter, PSC was advised:
"Our review indicated that your STA training. program is acceptable in meeting the intent of the guidelines set forth in the above referenced letters. You are requested to propose a-Technical Specification change incorporating the following qualification requirements for the STA as paragraph 6.3.2: 'The Shift Technical Advisor.shall have a bachelor degree- or equivalent in a scientific or engineering disc'.pline with specific training in plant design and response and analysis of the plant for transients and accidents.'"
PSC responded on April 20, 1982, via Reference 9 with a request for an amendment to section AC 7.1, as requested in G-82080. This change was implemented as Amendment No. 36 to the Facility Operating License upon receipt of G-83369 (Reference 10).
PSC has been pleased with the results of the incorporation of the Technical Advisor position into the operating staff at Fort St.
Vrain, and is continuing to explore areas ;nto which Technical Advisor manpower and experience can be utilized to e, hance operations of Fort St. Vrain. 'A large scale review of the Technical Advisor training program was recently completed at the suggestion of the Institute of Nuclear Power Operations (INPO) relative to the INP0 accreditation program, and new candidates for the Technical Advisor program are presently being trained in accordance with that enhan~ced program. Early feedback from that effort has been good, and we anticipate that the level of preparation of these candidates will be superior.
If you have questions regarding this matter,' please contact Frank Novachek of my staff at (303) 785-2224.
l Sincerely,.
l ahm Manager, Nuclear Production Fort St..Vrain Nuclear Generating Station JWG:JMS/jlr
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