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] |
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PUBLIC SERVICE COMPANY OF COLORADO h P. O. BOX 840 . DENVER, COLORADO 80201 OSCAR R. LEE August 21, 1984 wcc =c.mc . Fort St. Vrain
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hj Mr. E. H. Johnson, Chief Reactor Project Branch 1 L
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Region IV Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
Fort St. Vrain Control Rod Drive Refurbishment
REFERENCE:
P-84221 (Lee to Johnson, Dated July 18,1984)
Dear-Mr. Johnson:
This letter is to provide you with our findings and positions regarding the Fort St. Vrain control rod failure investigation which began as a result of the June 23, 1984 event where six control rods failed to automatically insert upon scram. To date, four of the six control rod drives (CRDs) have been examined. Attachment 1 summarizes the work performed and the observations made on each of these four CRDs.
A number of tests have been developed throughout the CRD work in order to better ascertain the mechanism for the apparent binding of the drive system. A brief description of these tests and their status is provided in Attachment 2. By far, the most conclusive of these tests is T-227, Back-EMF Testing. This test provides the most sensitive indication of control rod drive train performance available and has the additional benefit that it can be conducted even while the reactor is at power to confirm CRD operability. A "back-EMF" (voltage) is generated by the CRD shim motor as its control rod is scramming. The peak-to peak value of the back-EMF is a function of driving force on the motor and hence provides an indication of the amount of frictional resistance within the shim motor and the gear train (200 Assembly). Ideally, a back-EMF trace (which shows the voltage amplitude modulation throughout scram) should exhibit the following characteristics:
- 1) The average peak-to peak voltage shculd increase from a voltage of zero to a 'first maximum' at which the motor speed exceeds the constant speed for the remainder of the scram. This first maximum should occur at 2-5 seconds after scram i initiation. '
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- 2) The_ first maximum peak voltage should taper off to a relatively constant peak-to peak voltage until the scram is completed (i.e., ' flat' on the edges of the trace).
- 3) There should be minimal oscillating behavior in the trace after the first maximum.
Samples of back-EMF data taken from CRD No. 44 (installed in Region 28 on June 23,1984) are provided in Attachment 3. Figure 1 of- Attachment 3 shows the back-EMF signature at the beginning of scram prior to any refurbishment work having been performed. Note the amount. of time that- it took the control rod to reach maximum scram velocity. Scram was initiated at T = 0 seconds, and the point at which the maximum scram velocity was reached (i.e., the first
. voltage maximum or regenerative peak) was at T = 5.25 seconds. Also note the magnitude and the erratic variations in the voltage wave amplitude subsequent to the first peak voltage. Figure 2 shows the signature after refurbishing only the CRD shim motor and brake assembly. A marked improvement was observed. (The data was
' digitized for computer analysis and plotting. The slight variations on the edges of the trace are normal.) This signature is very similar to that of an ideal trace on a new CRD. The data shown in Figure 3 was taken following refurbishment of the 200 Assembly.
Based on this signature,.it was concluded that a gear train assembly problem had been created during rework, and the 200 Assembly was disassembled again. It was found that a shim had been placed incorrectly during the first reassembly. The shim placement was corrected, and the 200 Assembly was reassembled a second time.
Figure 4 shows the signature after all work was completed. By comparing Figure 2 and Figure 4, it can be concluded that refurbishment of the 200 Assembly did not significantly improve the CRD operation.
All of the CRDs that failed to scram on June 23, 1984, for which pre-refurbishment back-EMF signatures have been obtained (from Regions 6,10, 25, and 28), had pre-refurb,;hment back-EMF signatures exhibiting similarities to Figure 1 of Attachment 3. The magnitude of the average peak-to peak voltages was generally low, and erratic wave amplitude variations were characteristic. Back EMF signatures taken on a majority of the CRDs that scrammed properly on June 23, 1984, have exhibited larger average peak-to peak voltage values and more constant wave amplitudes similar to Figure 4 of
. Attachment 3.
6 . _._ . . _ . . _ - _ _ . _ . . . _ . . . _ , . _
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In summary, this is our evidence:
1)- Back-EMF data provides an effective means for identifying -degraded CRD performance. CRD operability, both prior to startup and during power operation, can be confirmed using this method.
- 2) Based 'on preliminary assessment of back-EMF data taken on all CRDs,_there are indications that some CRDs which scrammed properly on June 23, 1984, may
&lso exhibit degraded performance.
- 3) No. significant benefit is gained by refurbishing the 200 Assembly of the CRDs. To date, all performance improvements observed in the CRDs refurbished have been achieved following shim motor refurbishment alone.
-4)' We have performed 'an historical search of past operation with the intent of identifying' periods in which the reactor was operated under high moisture conditions for a relatively long period of time, and in which all rods inserted following an-automatic PPS action. From this. search, a reactor dew point of at' least 60 F has had no adverse effect on control rod scram capability.
We believe strongly that the cause of the event was the migration of moisture from the PCRV into the CRD motor area. Our ' evaluation of purge flow requirements, under the existing CRD design, has lead to
.the conclusion that this migration could not have been prevented even if full design purge flow requirements were met. Therefore, it is our position that the decrease in purge flow which occurred on
~
June 22, 1984, could not have significantly reduced the effects of the high primary coolant moisture levels con the motors.
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To ' elaborate, there are four passages through the CRD orifice motor plate which could result in a free-flow area being available for moisture migration. These four passages are: (1) one hole which provides access through the orifice motor plate for the RSD hopper pressurization line; (2) one _ hole for the RSD hopper vent line (3) and, two holes for access to eyebolts connected to the CRD lower assembly. In addition, there are four windows through the CRD housing which permit access to the CRD internals, and which could allow a flow path for primary coolant to reach the motor area (the windows are covered, but not sealed). The combination of areas
_ presented by the four orifice plate passages and by possible gaps around the four window cover plates results in a flow path being available for primary coolant to reach the CRD motor area. The purge flow capability, which is only intended to reduce plate-out in the motor area, is insufficient to overcome by pass flow via the aforementioned flow paths.
Thertir. e Public Service Company of Colorado commits to the fo110wE.g to be completed prior to restart:
- 1) Continue the refurbishment effort for the two remaining CRDs that failed to scram on June 23, 1984 (Regions 6 and 25). This refurbishment effort will include both the motor and gear train assemblies.
- 2) Repair the two control rods (Regions 19 and 30) which we have removed from the core for unrelated problems.
- 3) Continue to clean disassembled components of the CRD0As inspected, as appropriate, using uet or dry wiping, nitrogen blowdown, or alcohol solution methods.
- 4) Disassemble and inspect the motor-brake assemblies of two CRD0As which properly scrammed on June 23, 1984. In addition, one of the selected CRD0As will undergo disassembly and inspection of its 200 Assembly gear train.
- 5) Functionally test one 30 weight percent and one 40 weight percent reserve shutdown hopper, and perform a physical examination of the Reserve Shutdown material subsequent to testing.
- 6) Perform a test to determine the back EMF generated during scram for all 37 CRD0As. To date, all but the Region 30 CRD0A have been tested.
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- 7) Perform attest to determine the sensitivity of the motor bearing assembly to moisture relative to free rotational torque.
.8) Perform a test to determine the effects of exercising a CRDOA to ascertain the self clearing characteristics of the assembly.
- 9) Develop an acceptance criteria for establishing CRD operability based on reviews of back-EMF data, compare the back-EMF data taken from all CRDs against this acceptance criteria, and refurbish the CRDs that do. not meet the acceptance criteria as necessary'to return them to an acceptable status.
- 10) Complete i.vestigations into the effects of purge flow loss coincident with high primary coolant
, moisture. levels.
11). Complete. and report the results of our analyses of the identification / composition of debris found in the assemblies.
- 12) Evaluate and develop as necessary a CRDOA preventive- maintenance program for future
-refuelings; 13). Develop appropriate Technical Specification changes to include at least the following:
a) The requirements to perform an.immediate orderly shutdown when a moisture ingress event occurs resulting in primary coolant moisture levels exceeding a not yet specified dewpoint.
b)- The requirement' to perform periodic back-EHF tests to verify control rod operability, probably in conjunction with SR 5.1.1 c) Revise SR 5.1.1 frequency from monthly to weekly. Note that our reevaluation of the ~ 6" rod drop distance is more than adequate to verify scram times and to obtain back-EMF data.
7 d) The. requirement to obtain CRD motor
. temperature data in conjunction with SR 5.1.1 whenever power levels are above 30%.
e) The development of a definition of
' operable control rod' (to include minimum. requirements for position.
indication).
In the event. that a Technical Specification revision can not be' issued prior to the desired restart date, but a proposed revision which is satisfactory to both Public Service Company of Colorado and the Nuclear Regulatory Commission has been developed, then we . will implement the necessary. controls to incorporate the propcsed revision into our operation.
We are also evaluating design modifications to the control rods to decrease the free-flow area available for the moisture to enter the motor area, with the goal of not requiring an immediate orderly shutdown following a moisture ingress event. Preliminary analyses / tests' indicate that such a design modification is possible.
Therefore, we commit to design and manufacture devices which reduce
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the flow ' area available for primary coolant to reach the motor area via the orifice motor plate passages and CRD windows. This flow area will be reduced to the point where the existing purge system can overcome these by pass flow paths. We will schedule installation of this modification as a part of the future CRD preventive maintenance program.
We have a difficult task before us, both in the completion of the CRD refurbishment effort and in the development of appropriate Technical Specifications. I am confident of the correctness and completeness of the analyses that have been performed to date on the control rods, and I am basing the aforementioned commitments on these analyses.
Your prompt concurrence with this position will be appreciated.
he. _._
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-I Lwould like to propose a meeting of - my staff and the Nuclear
- Regulatory Commission in Arlington, Texas on September 11, 1984 to
~ discuss the' technical aspects of our findings and positions. Due to previous commitments, however, I will be unable to attend this meeting, but' I plan to come to- Arlington later in September to introduce myself to Mr. Robert Martin.
Very truly yours,
. R. ee Vice-President, Electric Production Attachments ORL/djm J.
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Attachment 1 Page 1 OBSERVATIONS ON REWORKED CONTROL R00 MECHANISMS Serial Number 25 This was the first mechanism to be reworked. At this time of the incident, it was installed in Region 14 and was a shim group rod mechanism. This mechanism was removed to the hot cell, had its shim motor only disassembled and reworked, and was subsequently returned to the Reactor in Region 7. After return to the Reactor, during the performance of T-227, which observed generated voltage during scram (back-EMF), slack cable indication was observed during run-out and the rod pair was inserted observing motor wattage. Although a slight increase in wattage was observed, it is not believed that this indicated a stuck or separated rod. It is : thought that spurious activation of the slack cable indication occurred as a result of inccrrect preload on the slack cable spring. This mechanism awaits a second removal from the reactor to correct the slack cable assembly problem.
Serial Number 18 This mechanism, the second to be examined, was installed in Region 7 at the time of the incident and was withdrawn to 190". It was removed to the hot cell where both the shim motor and the gear train were disassembled and reworked, and was subsequently returned to Region 10. This mechanism also failed to scram in .the February 22, 1982 incident (Reference LER 82-007).
Serial Number 14 This mechanism, the third to be reworked, was installed in Region 10 at the time of the incident, and was a shim group mechanism. The mechanism was removed to the hot cell, and both the shim motor and gear train were reworked. This is the first mechanism for which pre-disassembly back-EMF's were taken (although this me.hanisms trace was first taken in'the hot cell, not the reactor). After rework, the mechanism was returned to Region 6.
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Attachment 1 Page 2 Serial Number 44 This mechanism was the fourth to be-reworked. It was installed-in Region 28 and was withdrawn to 190" at the time of the incident. After removal from the reactor, it was placed in an Equipment Storage Well (prior to installation in the hot cell for refurbishment).
In-Reactor and hot cell back-EMF traces indicated that
.this rod exhibited poor back-EMF behavior. Pcrformance of T-236, to establisn that the rod would scram from any withdrawn position, showed that initially the rod pair would not insert freely from a variety of positions below the approximately half-withdrawn position. A
-second performance of this test approximately twelve hours later showed dramatic improvment. This improvement is attributed to natural ' drying' of the CRD motor while it was in the hot cell. The shim motor only was disassembled and reworked, and re-installed on the mechanism. .A back-EMF trace showed a very smooth voltage signature indicative of very little restri'ction of motion. After the refurbishment of the motor, the rod pair would scram freely from any position. After refarbishment of the gear train mechanism, another back-EMF trace indicated a substantial increase in mechanism' resistence during scram. The gear train was again reworked, this . time yielding a good back-EMF trace. (The gear train problem was traced to an improperly installed shim.) This mechanism was also involved .in the February 22, 1982 failure-to-scram incident (Reference LER 82-005). This mechanism is currently in an Equipment Storage Well awaiting return to the reactor.
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c-Attachment 2
'T-TEST
SUMMARY
AND STATUS ET-214 lCRDOA Motor Wattage Test PURPOSE: This- test is to establish a data base of Control Rod Drive Motor characteristics and to monitor the performance of the rod drive mechanism.
STATUS: -This' test-was performed in March and April of 1984
.on all.CRD0A's in the core. It was conducted again.
on' all -CRD0A's in. the core within three days following the. failure to scram incident.
T-226 Visual Examination of the Six CRD0A's That Failed
.to Scram PURPOSE: This test is to make observations that possibly will enable the' determination of the cause for the failure of CRD0A's in Regions 6, 7,:10, 14, 25, 28 to " SCRAM" on June 23, 1984.
. STATUS: -CRD0A's from Regions 14, 7, 10, 28 have been examined prior'to, during and after refurbishment.
- T-227 Shim Motor Back EMF Generated During Scram PURPOSE: This test' is to establish a data base of CRD0A back-EMF. It consists of obtaining coarse and detailed signatures of the EMF generated byL the
-shim motor / generator when the rods are scrammed.
STATUS: LThis test has been-performed on all CRD0A's in the core except Region #30 aCRDOA. This CRD0A shim motor. is believed to be bad. The signatures for the- six CRD0A's' that failed to scram on -
' June 23, 1984~-'are all of an irregular pattern indicating frictional resistance during scram.
- T-228' Susceptability of- Brake Assembly to Seize When.
-Exposed to Moisture
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PURPOSE:1To investigate the- possibility of. the brake assembly to seize when exposed to moisture.
STATUS: This test has been completed. -This test indicated no tendency for the brake assembly to be affected by moisture.
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Back-EMF Trace for i CRD No. 44 (Installed in Region 28 on 6/23/84)
Taken Prior to Refurbishment
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l FIGURE 2 Back-EMF Trace for CRD No. 44 (Installed in Region 28 on 6/23/84)
Taken After Refurbishment of Shim Motor / Brake Assembly Only BACK EMF CRD SN 44 840808 HSF G L 2 3 4 5 6 7 8 9 13 G Al i I I I I G
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! Back-EMF Trace for
[ CRD No. 44 (Installed in Region 28 on 6/23/84)
- . Taken After Refurbishment (Correct 200 Assembly Shim Placement)
- BACK EMF CRD SN 44 840815 HSF G l 2 3 4 ,
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