Letter Sequence Other |
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Results
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 Provided, ML20084C589, ML20084Q444, ML20092P626, ML20093K194, ML20094D774, ML20096C032, ML20098B305, ML20099K727, ML20100H112, ML20106B531, ML20106B533, ML20112G463, ML20117M059, ML20126B629, ML20127J822, ML20127K637, ML20127L885, ML20127N695, ML20132C948, ML20132E623, ML20132G502, ML20134E865, ML20138Q922, ML20206J841, ML20209E899
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MONTHYEARML20084C5891984-04-16016 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20132C9391985-07-12012 July 1985 Forwards Eg&G 850701 Evaluation of CRD Orifice Assembly Bearing Rept from Public Svc Co of Co, Per Util 850613 Submittal.Installed Bearings Acceptable Replacements for Original Design.Review of 850607 Submittal Also Encl Project stage: Approval ML20134E8651985-07-17017 July 1985 Issue 1 to Procedure SR-TE-9-X, Inserted Rod Position Verification Project stage: Other ML20134E8601985-07-31031 July 1985 Forwards Issue 1 to Procedure SR-TE-9-X, Inserted Rod Position Verification, in Response to Concerns Discussed at 850221 Meeting & in Project stage: Meeting ML20138Q9221985-12-19019 December 1985 Informs of Inability to Meet 851230 Completion Date of High temp,300 F,Crd Mechanism Test & Preliminary Evaluation,Due to Difficulties,Including Orifice Valve on Mechanism.Final Rept Will Be Submitted by 860331 Project stage: Other ML20199D3411986-06-11011 June 1986 Forwards Evaluation of Util Response to 851003 Review of Performance Enhancement Program.Method Should Be Provided to Confirm Functional Acceptability of Equipment Prior to Return to Svc Project stage: Approval ML20206B3301987-04-0606 April 1987 Requests Fr Publication of Notice of Issuance of Amend 52 to License DPR-34,increasing Circular Speed High Steam Trip Setting Listed in Table 4.4-3 of Tech Specs Project stage: Approval ML20206J9331987-04-0606 April 1987 Safety Evaluation Supporting Amend 52 to License DPR-34 Project stage: Approval ML20206J8411987-04-0606 April 1987 Amend 52 to License DPR-34,increasing Circulator speed-high Steam Trip Setting Listed in Table 4.4-3 of Tech Specs Project stage: Other ML20206J7481987-04-0606 April 1987 Forwards Amend 52 to License DPR-34 & Safety Evaluation. Amend Increases Circulator speed-high Steam Trip Setting in Table 4.4-3 of Tech Specs Project stage: Approval 1985-03-12
[Table View] |
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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
[Table view] |
Text
j k PUBLIC SERVICE COMPANY OF COLORADO P. O. BOX 840
- DENVER, COLORADO 80200 June 25, 1985 OSCAR R. LEE o d M . Wain y,c c ,,, c . , o ~ , Unit No. 1 P-85224 Regional Administrator Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Attention: Mr. Robert Martin Docket No. 50-267
SUBJECT:
Status of CRD0A Refurbishment Ef forts
REFERENCES:
- 1) NRC Letter, Wagner to PSC - FSV Dated December 17, 1984 (G-84470)
- 2) PSC Letter, Gahm to Region IV
-r- Administrator,
$ (C)[!! 0 $7 d. D Dated February 3, 1985 (P-85046)
- 3) NRC Letter, Martin to Lee, JUL - I 1985 Dated January 17,.1985(G-85024)
~
- 4) NRC Letter, Denise to Lee,
, Dated April 8, 1985 (G-85127)
- 5) PSC Letter, Warembourg to Johnson, Dated January 31, 1985 (P-85037)
- 6) PSC Letter, Warembourg to Johnson,.
Dated June 13, 1985 (P-85201)
- 7) PSC Letter, Lee to Region IV Administrator, Dated January 30,1985(P-85032)
- 8) PSC Letter, Lee to Johnson, Dated March 21, 1985 (P-85099)
Dear Mr. Martin:
1 1
The purpose of this letter is to inform the Nuclear Regulatory .
Commission (NRC) that Public Service Company of Colorado (PSC) has !
completed refurbishment of the first thirty-seven control rod drive 7 l
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PDR ADOCK 05000267 (6;
cru / P PDR:- g us-1\
-2
'and orificing assemblies (CRD0A's). Those refurbished CRD0A's are now installed in the reactor', and the seven remaining spares are in the process of- refurbishment for the 'next refueling outage. A summary of actions that have been taken to ensure the operability of the Fort St. Vrain CRDOA's follows.
Subsequent to the June 23, 1984 event where six of thirty-seven control rod pairs failed to insert into the core upon scram under the automatic velocity limited free-fall system, PSC initiated actions to identify the root cause of the event and restore the deficient CRD0A's to an operable status. The six CRD0A's that failed to scram were the first to be examined and rebuilt with an additional four being examined and rebuilt to various degrees afterwards. No definite cause for the failure to scram could be identified, but indications were that shim motor bearing wear and debris buildup was the primary contributor.
During this initial phase of_PSC's efforts, several other problems were also identified which were specifically unrelated to the failure to scram problem. First, CRD0A instrumentation anomolies began manifesting themselves, apparently induced by the high moisture content in the primary coolant. Second, a control rod absorber string suspension cable failed; the cable was evaluated, and stress corrosion cracking was identified as the failure mechanism (see-Reference 7). Third, during functional testing of one CRDOA's reserve shutdown (RSD) system, it was discovered that only thirty to forty of the eighty pounds (nominal) of RSD material was expelled.
Inspection and chemical analysis of the RSD material remaining in the RSD hopper revealed boric oxide crystallization which facilitated bridging of the boron balls inside the hopper (see Reference 8). A number of studies were initiated to fully evaluate each of the problems identified, and a summary of the activities performed in the initial phase was presented to the NRC~ in meetings held on November 28 and 29,1984 (see Reference 1).
The discovery of stress corrosion cracking in the CRD0A cables and boric acid crystallization on the RSD material, as well as the lack of a definite failure mechanism being identified.for the six CRD0A's failing to scram on June 23, 1984, led to a decision to refurbish all
! of the CRD0A's, restoring them to a "like new" condition. The major objectives of this program were established to include:
- 1) Refurbishment of all shim motors, replacing all motor bearings with new bearings,
- 2) Refurbishment of all 200 Assembly gear trains,
3)- Replacement of all CRD0A instrumentation with new components,
- 4) Replacement of all- stainless steel suspension cables with Inconel 625 cables,
- 5) Replacement of all RSD material with material manufactured under new specifications which significantly reduce the amount of B 20, impurities available for conversion to boric acid crystals,
- 6) Installation of CRDOA temperature monitoring devices,
- 7) Installation of CRD0A purge seals designed to inhibit primary coolant from entering the 200 Assembly gear train and motor area,
- 8) Refurbishment of all orifice drives, and
- 9) Replacement of miscellaneous CRDOA components with like components made from materials not as susceptible to chloride stress corrosion.
~
To ensure that a thorough knowledge of the.CRD0A's was attained prior to starting the refurbishment program, vendor (GA Technologies - GAT) support was solicited, but nearly all of the GAT personnel originally assigned to the design and manufacturing of the Fort St. Vrain CRDOA's had since left the company. PSC was able to locate one of the people responsible for developing the CRDOA 0&M manual and another individual who worked with him on the CRD0A's originally.
Both were brought to Fort St. Vrain in December, 1984, as expert consultants.
The CRDOA Refurbishment Program was developed and initially implemented during the period beginning in mid-November, 1984, and ending in early February, 1985. It was developed using the experience gained in the initial phase activities and the knowledge provided by the two CRD0A experts in addition to the in-house expertise already available. Implementation of the program involved the design and manufacture of special CRD0A handling equipment so that up to five CRD0A's could be worked simultaneously in an assembly line fashion.
Existing procedures for the maintenance of CRD0A's were extensively rewritten based on ieviews of vendor supplied 0 & M manuals, design and. fabrication drawings, and additional clarifications on specific design and operation details obtained from original manufacturers.
Personnel from all associated areas of expertise within PSC were
involved in'the procedure preparation. Those areas of expertise incl _uded, but were not limited to: Maintenance, Health Physics, Quality Assurance, Nuclear Engineering, Technical Services Engineering, and Nuclear Betterment Engineering. Again, the expert consultants provided significant insight as well. Quality Control inspection criteria were included to ensure original design component standards as a minimum. Additional inputs were incorporated based on a review of the procedure by the Senior Resident Inspector.
Contract personnel arrived on site approximately three weeks before the scheduled start of work for. training purposes. A letter of agreement with the union representing PSC. Maintenance allowed the hiring of special non-union " precision" mechanics for work on the delicate 200 Assembly motor and gear train aspects. A spare CRD0A
~200 Assembly motor and gear train was repeatedly disassembled and reassembled under the guidelines of the rewritten procedures.
Further refinements to the procedure were accomplished at this point.
Union contract personnel were trained on.the operation of new CRDOA handling equipment, and all personnel received extensive Health Physics training.
-Work on the first CRD0A began on February 6, 1985. This CRDOA was refurbished in its entirety prior to beginning the assembly line type process so that all aspects could be evaluated and verified acceptable. Numerous procedure revisions were made to improve workability. Several improvements to the original design were implemented. A summary of all design changes made to the CRD0A's is provided in Attachment 1. The overall refurbishment process was presented to the NRC in Reference 2, and all aspects of the CRDOA refurbishment program were discussed at length in meetings held on January 15, 1985, and February 20-22, 1985 (see References 3 and 4).
As the CRD0A Refurbishment Program progressed, several changes in scope were made to accommodate improvements to the original design and additional maintenance activities which'were deemed prudent for improving overall CRD0A' performance. Specific improvements to the original design beyond those previously identified included the increasing of the cable drum inside diameter to third stage pinion gear clearance to eliminate potential interference, and the installation of a slack cable switch bushing cap to ensure positive bushing retention. Additional maintenance ~ activities performed on all CRDOA's beyond those previously identified included relubrication of the 200 Assembly and orifice drive gear trains and examination and recoating of shim motor stators as necessary to restore them to original design specifications.
Near the end of the CRD0A Refurbishment Program, it was discovered that certain replacement 200 Assembly motor and gear train bearings
did not meet design specifications (e.g. shim motor bearings were provided by the manufacturer with eight balls instead of the specified nine). The problems associated with the bearings have been resolved through engineering evaluations and qualification testing of the "eight ball" bearings. A report on this. testing and evaluation was submitted via Reference 6.
To confirm that the 18 CRDOA's which had been refurbished prior to the Enforcement Conference on April 24, 1985, and that selected CRD0A's refurbished subsequent to that Conference were completed in accordance with high quality standards, audits of completed work packages were conducted by Quality Assurance.
As part of the control rod drive refurbishment, NFSC G-85-02 Audit, the Fuel Handling Procedure Work Packages (FHPWP's) governing the refurbishment of the CRD0A's were reviewed for proper documentation with emphasis on the QC hold and witness points and for records of task sign-out/ sign-in and completion. A limited review of two FHPWP's was completed, and 26 FHPWP's were examined in depth. The QC hold and witness points were examined to ensure that the points were signed by QC personnel. If these points were not signed, further investigation was done to determine the reason (s) and resolve the situation.
In addition to reviewing completed FHPWP's, the NFSC G-85-02 Audit reviewed Procedure Deviation k norts (PDR's) related to the CRD0A work, concerns and corrective actions identified in the NFSC G-85-01 Audit, and conducted a review of the D1201-200 series drawings on the CRD0A's. This D1201-200 review addressed the notes on the drawings relative to conflicts with the CRDOA refurbishment program, correctness of revision, and resolution of deficient areas noted during the review process.
If a situation could not be resolved, a Corrective Action Request (CAR) was issued. The recommended corrective action in each case addressed a determination of material impact on the CRDOA work as a result of the discrepant condition noted in the CAR. Resolution of all CAR's with respect to material impact on the CRD0A work will be completed prior to startup.
The Nuclear Engineering Division obtained the services of a consultant to conduct a review of the CRD0A drawings and 0&M manuals to verify that all design requirements specified on the GA drawings or in the CRD0A 0 & M manual, which relate to the CRD0A refurbishment program, have been appropriately considered in the procedures being used to control the CR00A refurbishment work or have been appropriately considered in the purchase orders for spare parts.
Upon completion of the review, any requirements related to the CRDOA m
refurbishment work, which are specified on the CRD drawings or identified in the 0&M Manual which were not specifically incorporated in the procedures or specified in purchase orders for spare parts, will be resolved prior to startup.
The Nuclear Production Division selected a representative sample of nine CRDOA's to be reworked for installation of slack cable switch bushing retainers and/or back-EMF considerations, and inspected them for quality indicators such as loose bolts, improper lockwiring, frayed cables, Resistance Temperature Device (RTD) positioning, general surface condition, etc. Additional back-EMF and RP-5 testing was also completed on all nine CRD0A's. No indication of overall quality workmanship problems were detected.
CRD0A post refurbishment testing was conducted on all CRDOA's including both functional and performance testing. The functional tests , included verification of proper position indication, limit.
switch protective functions, performance of RSD system integrity and primary and secondary reactor vessel seal integrity per already
. established functional criteria. Additional testing was conducted to verify proper installation of RTD's.
The performance testing criteria was established and submitted via Reference 5 prior to the initiation of the refurbishment program. At that . time, only four of the thirty-seven CRD0A's in core met the criteria. This performance criteria were based upon original performance testing conducted by the designer. They included minimum pre-electromotive force acceleration and steady state velocity stability requirements. The results of back-EMF testing are provided in Attachment 2. "Before" and "after" refurbishment torque testing was also ' performed- to establish shim motor and gear train rolling resistance, which provides a basis for determining operational acceptability of the shim motor and gear train assembly (see Attachments 3 and 4). As verified by post refurbishment performance
. testing, all CRDOA's refurbished surpassed the performance acceptance criteria.
The actions taken during the refurbishment program restored the CRDOA's to a "like new" condition thereby ensuring reliable operation. The modifications to the CRD0A's did not alter their design intent or function, involve a change to the Technical Specifications or an unreviewed safety question. A description of u
the modifications, including a summary of the safety evaluation of each, will be submitted to the NRC in the annual report in accordance with the provisions of 10 CFR 50.59.
If you have any questions, please contact Mr. M. H. Holmes at (303) 571-8409.
Sincerely, b]~ ts
- 0. R. Lee, Vice President Electric Production ORL: FJN/skd Attachments L
ATTACHMENT 1 Design-and material changes listed in the table below were made to increase the reliability and improve the performance of the CRD0As.
Among these;were design modifications such as the' installation of a slack cable bushing retainer cap, the enlargement of the inner cable drum inner diameter and the installation of eyebolt and tube hole cover assemblies. Material changes were also implemented to reduce susceptibility to chloride stress corrosion. Other material changes were made to accommodate expedient material delivery or increase material. temperature ranges; which had no significant affect on component quality, performance or reliability. Bearing discrepancies not listed are noted in Reference 6 of this letter.
Control Rod Drive And Orificing' Assembly Changes Dwg. No.
D1201-100 Control & Orificing Assy.
The helium line connector o-rings were replaced using o-rings made of ethylene propylene to increase the o-ring temperature rating.to 300 F.
The following note changes were made:
Alternate material specs, are called out for the new ethylene' propylene o-rings for delivery time purposes.
Use of "Cerac" SP111 lubricant was specified in place of Jetlube SS-30 on all bolt threads to increase the temperature rating.
. D1201-102 Bearing Lubrication Procedure A step was added in the procedure to wash the bearing in ethyl alcohol to insure removal of all residual acid from a previous step.
D1201-105 Tab Washer-T Alternate material spec. ASTM A366 was specified for j fabrication purposes.
D1201-111 Housing Aluminum Alloy 6061-T6'per ASTM B221 was specified as an alternate material for the aluminum casting for fabrication purposes.
All small radii for casting purposes were deleted on machined parts.
Casting classes for inspection were revised to show inspection requirements in certain areas.
- j. .
L ~
D1201-115. Reserve Shutdown and Helium Purge Lines i: -
'The tube material was changed from stainless steel to Inconel 600 per SB163 or SB167 to avoid possible i stress corrosion problems, t
The connector & elbow material was changed from SST to
, carbon steel to avoid stress corrosion problems.
i 01201-150 Process Procedure for Electromagnetic Assys.
General Electric RTV #162 sealant was specified as an y alternate sealant because of availability.
The glass fiber filler content was revised to show the
, amount actually used.
- D1201-200 Control Rod Drive Assy.
Replace the rewind gear cap screws with screws made of alloy steel to avoid possible stress corrosion
_. problems.
A note was added to specify a bolting torque of 20 l in.-lb. to the rewind gear cap screws to avoid
- overstressing of the screw.
D1201-206 Flange, Inner, Cable Drum Aluminum plate 6061-T6 per ASTM B221 is specified as
, an alternate material to the aluminum casting for j fabrication purposes.
The inside diameter is increased by 0.040 in. to avoid rubbing. '
j D1201-207 Hub, Cable Drum h
Aluminum Alloy 6061-T-6 per ASTM B221 is specified as an alternate material to the aluminum casting for fabrication purposes.
D1201-217_ Motor & Brake Assy.
The insert material in the socket head cap screw was
. changed to KEL-F to increase the temperature rating to
, 300 F.
i A note change was made to delete the reference to the old environmental test for the motor. The motors will be tested per the new environmental test spec. 12-U-5.
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_3 D1201-217 Motor & Brake Assy. (cont.)
An alternate protective treatment for electroless nickel plating was called out per MIL-C-26074B(1) since the original Kanigan process is no longer available.
01201-218 Shim Motor The note specifying the test speed for the motor changed from 2200 to 2400 rpm to be consistent with test requirements.
A Long Lok set screw LL62XA62J2E was listed as an alternate to increase the temperature rating of the set screw. The insert material is KEL-F.
Locking specification RM-3-1, Class B, type II was specified to increase the temperature rating to 300 F.
The rotor imbalance was revised to be consistent with drawing D1201-217.
The encapsulation mixture used on the shim motors was revised to represent the mixture used on all motors manufactured.
A note was added to specify the protective coating used on the shim motor stator & rotor previously manufactured by the supplier.
The rotor and stator dimensional tolerances were changed to insure a minimal diametral air gap of 0.014 inches after painting.
The permanent magnet is bonded to the shaft. This alternate assembly method is permitted to avoid the requirement for the light interference fit between the permanent magnet and the shaft.
D1201-219 Brake Assy.
A socket head cap screw was replaced by an alloy steel screw to avoid stress corrosion. A cadmium plating was used.
The set screw was torqued to 16 in.-lb. to avoid overstressing of the screw.
A Long Lok screw was specified as an alternate screw due to availability.
L______._______
r 3
_4_
s D1201-221 Retainer, Bearing, Shim Motor Stainless steel type 17-4 PH was specified as an alternate material. This material is to be used when increased brake holding torque is required to satisfy the design requirements.
D1201-223 End Bells Aluminum alloy 6061-T6 per ASTM B221 was specified as an alternate material to the aluminum casting for fabrication purposes.
The corner radii are not required on the machined parts.
01201-227 Tie Bolt AISI C-1215 is an alternate material spec. for availability reasons.
MIL-C-26074B(1) was specified as an alternate protective treatment since the original Kanigan process is no longer available.
01201-231 Gear Box Housing Carbon steel plate per ASTM A516, GR70 was specified as an alternate material to the steel casting for fabrication purposes.
The corner radii are not required in the machined parts.
D1201-232 Pinion Housing Steel plate or bar per AISI 1015 thru 1020 was specified as an alternate material to the steel casting for fabrication purposes.
D1201-244 SH. 2 of 2 Cam An alternate cam with a different geometry was permitted to provide better limit switch operation.
Stainless steel 410 was used on the new cams for fabrication purposes.
01201-246 Bracket, Limit Switch Aluminum alloy 6061-T6 per ASTM B221 was specified as an alternate material to the aluminum casting for fabrication purposes.
L.
01201-250 Cable Assy.
A note was added describing the new cable pull test to 3500 lb.
A torque of 8 in.-lb. was specified for the set screw to avoid overstressing of the screw.
A torque of 150 in.-lb. was specified for the nut bushing to avoid overstressing during assembly.
A stainless steel retaining ring was used to replace a carbon steel retaining ring for availability reasons.
A 304 stainless steel screen & spring was changed to 416 stainless & I-X750 Inconel respectively.
D1201-251 Cable The cable material was changed from AISI 347 stainless steel to Inconel 625 per ASTM B-446 to avoid stress corrosion problems.
01201-252 Anchor, Cable The anchor material was changed from AISI 304 stainless steel to AISI 416 stainless steel to avoid stress corrosion problems.
The anchor was gas nitrided to avoid welding or galling. Dry lubricant "Cerac" SP111 is used to avoid added friction.
01201-255 SH. 2 of 2 Nut Bushing The nut bushing for the cable assembly involved a geometry change to allow for better limit switch operation.
D1201 259 Bearing Bearing model SS3207 or equal was specified for availability reasons.
01201-260 Bearing Bearing model MRC-210S-ST or equal was specified for availability reasons.
01201-262 Segment Restrictor Stainless steel 416 per ASTM A582 was specified as an alternate material to the stainless steel casting for fabrication purposes.
u
1 D1201-262 Segment Restrictor (cont.)
The 416 SST is heat treated per MIL-H-6875 to Rockwell hardness of C25-32 for fabrication purposes.
01201-263 Rod End The rod end material was changed from 304 stainless steel to Inconel I-625.
01201-275 Closure Assy.
The o-rings are replaced with o-rings made of ethylene propylene to increase the temperature rating of the o-rings to 300 F.
Alternate material specs. are given for the o-rings for availability reasons.
01201-279 Plug The o-ring was replaced with an o-ring made of ethylene propylene to increase the temperature rating of the o-ring for availability reasons.
01201-281 Support Aluminum alloy 6061-T6 per ASTM B221 was specified as an alternate material to the aluminum casting for fabrication purposes.
Corner radii are not required on machined parts.
Casting grade was specified for fabrication purposes.
The anodizing spec. on the drawing'was corrected to reference the proper specification.
D1201-282 Eyebolt An alternate material A36 carbon steel was specified for fabrication purposes.
D1201-284 Receptacle-Aluminum alloy 6061-T6 per ASTM B221 was specified as an alternate material to the aluminum casting for fabrication purposes.
Casting grade was specified for fabrication and inspection purposes.
D1201-286 Bushing Cap A slack cable bushing cap was added to insure positive retention of the bushing.
t
i D1201-287 Shim Shims with a 0.003" thickness were added to improve.
assembly operations.
01201-700 Shield Assy.
A button head socket cap screw was specified with an alternate alloy steel material to avoid possible stress corrosion problems.
D1201-811 Seal Ring The gask-o-seal was replaced with a seal made of ethylene propylene to increase the temperature rating of seal of 300 F.
01201-1079 Clevis Bolt The clevis bolts are replaced as the new bolts become available. The new bolts are made of Inconel X-750 to avoid possible stress corrosion problems. The corrosion resistant steel was used as the "old" material successfully passed qualification testing in a high chloride concentration solution. Actual examination of clevis bolts previously installed on CRDOAs which were resident in the reactor during power operation, were also made in the hot service facility using video monitors. No evidence of damage or cracking was observed.
An alternate material of 17-7 PH per AMS 5678 was specified for the retaining element for availability reasons.
.01201-1080 Tube Hole Cover Assy.
Two bellows seal assemblies have been' installed in the CRD cavity. The seals prevent natural circulation of primary coolant into the cavity through the holes around the reserve shutdown helium tube lines. This was done to prevent possible moisture carryover into the CRD cavity.
01201-1085 Eye Bolt Hole Cover Assy.
Two bellows seal assemblies have been installed in the CRD cavity. The seals prevent natural circulation of primary coolant into the cavity through the penetrations for the two shielding containter eye bolts. This was done to prevent possible moisture carryover into the CRD cavity, u
A D1201-1090 Access Cover Assy.
Four newly designed access cover plates are installed to prevent moisture ingress into the CRD cavity. The cover plates are fitted with integral gaskets to insure a tight fit. The cover plates also include the bolts and tabwashers to install them.
01201-1095 Spherical Bearing Assy.
No changes were involved and the new drawing was created for fabrication purposes only.
D1201-1096 Rod End The part, previously part 2 on D1201-263, was changed to Inconel 625 to avoid possible stress corrosion problems.
D1201-1097 Spring The aging treatment was changed to AMS 5699 since it is a more applicable spec. for tempering of springs.
The material was changed to Inconel X-750 to avoid possible stress corrosion problems.
D1201-1098 Insulator, Magnet No changes to the part are involved. The drawing was added to the documentation system.
D1201-1099 Washer The original part number was not available so this drawing was created for fabrication purposes only. No changes to the washer are involved.
. 'ATTACllMENT 2 CRDOAs PRE AND POST-REFURBISHMENT ACCELERATION PROFILES CRDOA PRE-REF F.E. POST-REF F.E. DELTA COMMENTS S. N. TEST DATE ACCEL. TEST DATE ACCEL. ACCEL.
1 850323 99.4 850411 125.1 25.7 1 2 850308 128.0 860316 127.9- .1 2 3 850428 95.5 860602 121.0 25.5 1
-4 850316 124.5 850415 123.2 -1.3 2 5 850312 82.5 850326 124.3 41.8 1 6 850220 103.0 850323 124.2 21.2 1 7 850329 82.7 850415 131.2 48.5 1 8 850505 85.9- 850603 126.7 40.8 1 10 850517 120.0 850621 121.4 1.4 1 11 850419 123.6 850423 124.5 .9 3 12 850415 105.0 850504 122.9 17.9 1 13 850410 104.2 850524 111 1 6.9 5 14 850531 103.2 850611 101.1 -2.1 1 15 850202 88.8 850322 129.0 40.2 1 16 850417 114.9 850427 123.9 9.0 1 17 850408 63.5 850524 117.5 54.0 1 18 850221 83.4 850414 111.9 28.5 1 21 850220 105.0 850415 114.3 9.3 2 22 850516 91.2 850521 124.5 33.3 2 23 850320 88.8 850408 112.6 23.8 1 24 850504 96.1 850614 121.3 25.2 1 26 850308 129.2 850314 130.4 1.2 2 28 850421 81.6 850429 126.0 44.4 1 29 850519 88.0 850526 125.7 37.7 1 30 850423 110.9 850614 120.5 9.6 1 31 850501 115.5 850528 119.2 3.7 1 32 850429 108.2 850614 124.8 16.6 1 33' 850525 97.6 850602 128.4 30.8 1 34 850503 93.2 850620 123.6 30.4 1 35 850425 84.7 850504 127.3 42.6 1 36 850316 79.8 850410 124.1 44.3 1 37 850506 84.9 850614 129.8 44.9 1 38 850322 117.9 850407 119.9 2.0 1 39 850415 80.0 850428 120.8 40.8 1 40 850523 89.3 850530 126.3 37.0 1 41 850529 91.3 850620 121.4 30.1 1 42 850407 81.4 850614 125.5 44.1 1 44 850518 92.4 850615 121.2 28.8 1 Comments:
1,5-Based on shots in the core before and after refurbishement.
2-Orig, in Equip. Stor. Well. No pre-refurb, in-core shot available.
3-CRD did not have a motor. No pre-refurb, in-core shot available.
4-No valid post-refurbishment, in-core shot available.
5-Post shot with old DAS system due to noise problems.
ATTACIDfENT 2 (cont.)
The effect of the refurbishment process on Front End (F.E.) Acceleration varied considerably from CRDOA (Control Rod Drive and Orifice Assembly) to CRDOA. The following tables sumarize the results:
CRDOA Lowest Pre-Returb F.E. Accel. 17 63.5 rads /seca2 Highest Pre-Refurb F.E. Accel. 26 129.2 rads /seca2 Lowest Post-Refurb F.E. Accel 14 101 1 rads /seca2 Highest Post-Refurb F.E. Accel. 7 131.2 rads /sec^2 Highest Gain in F.E. Accel. 17 54.0 rads /sec^2 Highest Loss in F.E. Accel 14 -2.1 rads /seca2 CRDOAs SHOWING A NET F.E. ACCEL. LOSS AFTER REFURBISHMENT CRDOA PRE-REFURB POST-REFURB NET EFFECT 2 128.0 127.9 .1 4 124.5 123.2 -1.3 14 103.2 101.1 -2.1 CRDOAs WITH COMPARATIVELY LOW F.E. ACCEL.
CRDOA PRE-REFURB POST-REFURB NET EFFECT 13 104.2 111.1 6.9 14 103.2 101 1 -2.1 17 63.5 117.5 54.0 18 83.4 111.9 28.5 21 105.0 114.3 9.3 23 88.8 112.6 23.8 AVERAGE PRE-REFURB F.E. ACCEL.
97.77 AVERAGE POST-REFURB F.E. ACCEL. '
122.49 AVERAGE F.E. ACCEL. GAIN 20.18 %
REFURBISHMENT CRITERIA F.E. ACCEL. FAILURE LEVEL 98.83 NOTE: All acceleration values are expressed in cad,/sec^2.
L ,
ATTACHMENT 3 T-260 Shim Motor Torque Maximum Breakaway Torque Shim Motor No. TORQUE (in.oz.)
Pre-Refurb. Post-Refurb 1 6 4 2 42 6 3 20 3 4 13 4 5 20 4 6 22 2 7 Bearing Test Motor 9 6 9 18 2 10 26 2 11 36 2 12 24 2 13 7 2 14 16 3 15 18 2 16 3 18 26 3 20 7 2 21 4 22 5 1 23 15 4 24 19 2 26 5 2 28 8 6 29 32 2 30 6 3 31 15 4 32 18 8 33 10 2 34 3 35 8 2 36 10 4 37 22 2 38 43 3 39 42 2 40 11 2 41 8 5 42 9 4 43 2 1A 13 3 100 4 101 5 3
ATTACHMENT 4 T-261 Shim Motor / Gear Train Torque Maximum System Breakaway Torque.
(Post Refurbishment)
TORQUE (in. oz.)
CRD N0. Holding Breakaway 1 22 28 2 24 32 3 22 24 4 22 32 5 22 24 6 18 26 7 24 32 8 22 28 9 22 34 10 22 30 11 20 30 12 23 25 13 18 26 14 19 33 15 18 25 16 20 28 17 19 31 18 24 36 19 22 27 21 22 27 22 22 28 23 22 30 24 21 31 26 22 28 28 20 30 29 22 28 30 20 30 31 22 34 32 20 30 33 21 28 34 22 26 35 20 32 36 19 33 37 21 29 38 22 28 39 21 30 40 22 27 41 24 28 42 18 26 44 20 32 u