|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6741999-10-0202 October 1999 Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data ML18066A6791999-10-0101 October 1999 Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants. ML18066A6621999-09-30030 September 1999 Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS ML18066A6601999-09-29029 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18066A6471999-09-17017 September 1999 Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs ML18066A6331999-09-0202 September 1999 Forwards Monthly Operating Rept for Aug 1999 & Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18066A6261999-08-26026 August 1999 Forwards Addl New Valve Relief Request as Alternative to Code Requirements That Will Provide Acceptable Level of Quality & Safety.Request Would Allow Use of App II, Check Valve Condition Monitoring Program, of ASME OM Code-1995 ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML18066A6111999-08-13013 August 1999 Requests Exemption from Certain Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101. Request Concerns Oil Collection Sys Requirements for PCP Motors ML18066A5881999-07-30030 July 1999 Provides Rev to Instrument Channel Drift Measurement Submitted on 990611,in Response to NRC Comments on Util RAI Response for Sections 3.3,3.5 & 3.6 & Editorial Changes Revs Necessary for Consistency within ITS ML18066A5921999-07-30030 July 1999 Forwards Results of Review by Consumers Energy of Two NRC Draft Repts Entitled, Evaluation of Air-Operated Valves at Light-Water Reactors & Study of Air-Operated Valves in Us Nuclear Power Plants. ML18066A5971999-07-30030 July 1999 Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments ML20210G8351999-07-29029 July 1999 Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in PDR ML18066A5651999-07-19019 July 1999 Forwards Corrections to Previously Submitted TS Section 3.7, Plant Systems, Converting to Its,Per NUREG-1432.Licensee Realized That Certain Provisions of CTS Had Been Inappropriately Replaced with Provisions from STS ML18066A5111999-06-29029 June 1999 Provides Voluntary Confirmation of Facility Readiness as Outlined in GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure & Response Encl ML20209B2081999-06-29029 June 1999 Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901 ML20210G8791999-06-23023 June 1999 FOIA Request for All Document Communications Between NRC & Region III Involving R Landsman,B Jorgensen & R Caniano & NRC Staff Under Their Supervision & All Communications in Their Possession to & from Consumers Power Re Plant ML18066A5061999-06-17017 June 1999 Forwards Responses to NRC Questions for ITS LCOs 3.6.3 & 3.6.6 of 990126 Submittal.One Editorial Change in Addition to Those Made in Response to NRC Comments & Conforming Changes Made to Associated Bases,Encl ML18066A4991999-06-11011 June 1999 Forwards Responses to NRC Comments Re ITS Section 3.3 & Associated Revs to ITS Sections 1.0,3.3,3.4 & 3.9 of 990126 ITS Conversion Submittal.One Technical Change & Several Editorial Changes Unrelated to NRC Comments,Also Provided IR 05000255/19970181999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18066A4921999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18068A6011999-06-0808 June 1999 Forwards Description of Recent Changes Made to Palisades Site Emergency Plan,Excluding Minor & Editorial Changes Not Requiring Further Explanation ML18066A4881999-06-0404 June 1999 Provides Responses to NRC Questions & Associated Editorial Revs for ITS LCOs 3.6.1,3.6.2,3.6.4,3.6.5 & 3.6.7 of 980126 Submittal.Responses to Comments on Remaining Section 3.6 LCOs Will Be Submitted Separately ML18066A4801999-05-24024 May 1999 Forwards Copy of Rev to NPDES Permit Number MI0001457 Renewal Application as Submitted to Mi Dept of Environ Quality on 990513 ML18066A4721999-05-18018 May 1999 Informs That During Period from 981101-990430,there Were No NPDES Permit Violations & No Repts of Oil,Salt or Polluting Matl Losses Were Made to Govt Agencies ML18066A4651999-05-17017 May 1999 Forwards ISI Program Relief Request 14 for NRC Approval in Accordance with 10CFR50.55(a)(3) as Requirement for Which Proposed Alternative Provide Acceptable Level of Quality & Safety.Rev 0 to SIR-99-032 Rept Also Encl ML18066A4611999-05-14014 May 1999 Requests Approval to Use Alternative Requirements IAW 10CFR50.55a(a)(3)(i),proposing to Follow Requirements of ASME Boiler & Pressure Vessel Code Case N-566-1.IST Program Relief Request 6 for NRC Approval Encl ML18068A5831999-05-0303 May 1999 Forwards Proposed TS Section 3.5,in Response to NRC 990317 RAI Re Util 980126 TS Change Request Re Conversion to Improved Ts,Per NUREG-1432 ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20217A8191999-04-29029 April 1999 Forwards Listed Matls Related to Palisades Plant June 1999 Initial License Exam ML20206E8271999-04-28028 April 1999 Forwards Palisades Plant Annual Radiological Environ Operating Rept for 1998. There Were No Reportable Events During This Period ML20207B4661999-04-23023 April 1999 Forwards Copy of Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981201 for Palisades Npp.No Deficiencies Noted.Seven New Arcas Identified ML18066A4531999-04-0707 April 1999 Forwards ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1,as Requested by NRC 990406 Telcon,Per TS Change Request Submitted 980126.Change Submitted Does Not Alter Conclusions of No Signficant Hazards Considerations ML18066A4481999-04-0202 April 1999 Responds to Violations Noted in Insp Rept 50-255/98-06. Corrective Actions:Nuclear Performance Assessment Dept Has Reviewed Observations & Agrees That Field Observations by Qualified Personnel Are Important Aspect of Program ML18066A4471999-03-30030 March 1999 Confirms Completion of Util Review of Design Engineering Contractor Cable Ampacity Evaluation.Evaluation Available at Plant for NRC Review ML18066A4411999-03-30030 March 1999 Forwards Response to NRC 990126 RAI Re TS Section 3.7 of Util 980126 LAR Request for Conversion to Its.Licensee Received Permission to Delay TS Section 3.6 Response to Allow for Addl Time for Preparation & Internal Review ML18066A4441999-03-26026 March 1999 Submits Certification of Financial Assurance for Decommissioning of Palisades Nuclear Plant.Certified Rept of Status of Consumers Energy Co Decommissioning Funding & Trust Agreement Encl as Attachments 1 & 2 ML18066A4401999-03-25025 March 1999 Forwards Revised Best Estimate Fluence Evaluation Using Industry Data, Providing Justification for Using Industry Data to Determine Best Estimate Fluence.Review of Info & SE Requested ML18066A4191999-03-23023 March 1999 Forwards 1998 Annual Radioactive Effluent Release & Disposal Rept, for Palisades Plant,Providing Summary of Quantities of Radioactive Liquid & Gaseous Effluent Releases & Solid Radioactive Waste Processed During 1998 ML18066A4231999-03-22022 March 1999 Forwards Answers to 990311 Telcon Request for Addl Clarification & Revs Re ITS Section 3.4.Markups of Previously Submitted TS Pages & Revised Pages for Section 3.4 Also Encl ML20204F2091999-03-18018 March 1999 Requests That Listed TS Change Requests (Tscrs) Be Issued with Allowance That Tscrs Be Fully Implemented within Sixty Days of Issuance.Request Will Allow Time for Completion of Final Training & Procedure Changes Associated with Amend ML18066A4121999-03-18018 March 1999 Concludes That Mod to Provide Automatic Switchover of Control Room Heating,Ventilation & Air Conditioning (CRHVAC) Sys to Emergency Mode Is Not Needed to Meet Regulatory Requirements.Mod Commitment Cancelled ML18066A4141999-03-18018 March 1999 Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML18066A4131999-03-11011 March 1999 Responds to NRC 990210 Ltr Re Violations Noted in Insp Rept 50-255/98-22.Corrective Actions:Analytical Evaluation, EA-C-PAL-98-1067-01, P-50A Case to Cover Stud Evaluation, Was Submitted to NRC on 981220 ML18068A5241999-02-12012 February 1999 Resubmits Relief Request 12,with Addl Info That Includes Specific Locations Where Relief Request Would Be Applied,Per 10CFR50.55a(g)(5)(iii) ML18068A5211999-02-11011 February 1999 Informs NRC That Implementation of Formal Industry Position on Severe Accident Mgt at Palisades Plant Was Completed on 981217 ML18066A4051999-02-10010 February 1999 Requests Copy of Consumers Energy (Palisades) Formal Response to RAI Dtd 990512 (USI A-46) 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6741999-10-0202 October 1999 Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data ML18066A6791999-10-0101 October 1999 Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants. ML18066A6621999-09-30030 September 1999 Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS ML18066A6601999-09-29029 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18066A6471999-09-17017 September 1999 Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs ML18066A6331999-09-0202 September 1999 Forwards Monthly Operating Rept for Aug 1999 & Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18066A6261999-08-26026 August 1999 Forwards Addl New Valve Relief Request as Alternative to Code Requirements That Will Provide Acceptable Level of Quality & Safety.Request Would Allow Use of App II, Check Valve Condition Monitoring Program, of ASME OM Code-1995 ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML18066A6111999-08-13013 August 1999 Requests Exemption from Certain Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101. Request Concerns Oil Collection Sys Requirements for PCP Motors ML18066A5971999-07-30030 July 1999 Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A5921999-07-30030 July 1999 Forwards Results of Review by Consumers Energy of Two NRC Draft Repts Entitled, Evaluation of Air-Operated Valves at Light-Water Reactors & Study of Air-Operated Valves in Us Nuclear Power Plants. ML18066A5881999-07-30030 July 1999 Provides Rev to Instrument Channel Drift Measurement Submitted on 990611,in Response to NRC Comments on Util RAI Response for Sections 3.3,3.5 & 3.6 & Editorial Changes Revs Necessary for Consistency within ITS ML18066A5651999-07-19019 July 1999 Forwards Corrections to Previously Submitted TS Section 3.7, Plant Systems, Converting to Its,Per NUREG-1432.Licensee Realized That Certain Provisions of CTS Had Been Inappropriately Replaced with Provisions from STS ML18066A5111999-06-29029 June 1999 Provides Voluntary Confirmation of Facility Readiness as Outlined in GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure & Response Encl ML20210G8791999-06-23023 June 1999 FOIA Request for All Document Communications Between NRC & Region III Involving R Landsman,B Jorgensen & R Caniano & NRC Staff Under Their Supervision & All Communications in Their Possession to & from Consumers Power Re Plant ML18066A5061999-06-17017 June 1999 Forwards Responses to NRC Questions for ITS LCOs 3.6.3 & 3.6.6 of 990126 Submittal.One Editorial Change in Addition to Those Made in Response to NRC Comments & Conforming Changes Made to Associated Bases,Encl ML18066A4991999-06-11011 June 1999 Forwards Responses to NRC Comments Re ITS Section 3.3 & Associated Revs to ITS Sections 1.0,3.3,3.4 & 3.9 of 990126 ITS Conversion Submittal.One Technical Change & Several Editorial Changes Unrelated to NRC Comments,Also Provided IR 05000255/19970181999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18066A4921999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18068A6011999-06-0808 June 1999 Forwards Description of Recent Changes Made to Palisades Site Emergency Plan,Excluding Minor & Editorial Changes Not Requiring Further Explanation ML18066A4881999-06-0404 June 1999 Provides Responses to NRC Questions & Associated Editorial Revs for ITS LCOs 3.6.1,3.6.2,3.6.4,3.6.5 & 3.6.7 of 980126 Submittal.Responses to Comments on Remaining Section 3.6 LCOs Will Be Submitted Separately ML18066A4801999-05-24024 May 1999 Forwards Copy of Rev to NPDES Permit Number MI0001457 Renewal Application as Submitted to Mi Dept of Environ Quality on 990513 ML18066A4721999-05-18018 May 1999 Informs That During Period from 981101-990430,there Were No NPDES Permit Violations & No Repts of Oil,Salt or Polluting Matl Losses Were Made to Govt Agencies ML18066A4651999-05-17017 May 1999 Forwards ISI Program Relief Request 14 for NRC Approval in Accordance with 10CFR50.55(a)(3) as Requirement for Which Proposed Alternative Provide Acceptable Level of Quality & Safety.Rev 0 to SIR-99-032 Rept Also Encl ML18066A4611999-05-14014 May 1999 Requests Approval to Use Alternative Requirements IAW 10CFR50.55a(a)(3)(i),proposing to Follow Requirements of ASME Boiler & Pressure Vessel Code Case N-566-1.IST Program Relief Request 6 for NRC Approval Encl ML18068A5831999-05-0303 May 1999 Forwards Proposed TS Section 3.5,in Response to NRC 990317 RAI Re Util 980126 TS Change Request Re Conversion to Improved Ts,Per NUREG-1432 ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20217A8191999-04-29029 April 1999 Forwards Listed Matls Related to Palisades Plant June 1999 Initial License Exam ML20206E8271999-04-28028 April 1999 Forwards Palisades Plant Annual Radiological Environ Operating Rept for 1998. There Were No Reportable Events During This Period ML20207B4661999-04-23023 April 1999 Forwards Copy of Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981201 for Palisades Npp.No Deficiencies Noted.Seven New Arcas Identified ML18066A4531999-04-0707 April 1999 Forwards ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1,as Requested by NRC 990406 Telcon,Per TS Change Request Submitted 980126.Change Submitted Does Not Alter Conclusions of No Signficant Hazards Considerations ML18066A4481999-04-0202 April 1999 Responds to Violations Noted in Insp Rept 50-255/98-06. Corrective Actions:Nuclear Performance Assessment Dept Has Reviewed Observations & Agrees That Field Observations by Qualified Personnel Are Important Aspect of Program ML18066A4411999-03-30030 March 1999 Forwards Response to NRC 990126 RAI Re TS Section 3.7 of Util 980126 LAR Request for Conversion to Its.Licensee Received Permission to Delay TS Section 3.6 Response to Allow for Addl Time for Preparation & Internal Review ML18066A4471999-03-30030 March 1999 Confirms Completion of Util Review of Design Engineering Contractor Cable Ampacity Evaluation.Evaluation Available at Plant for NRC Review ML18066A4441999-03-26026 March 1999 Submits Certification of Financial Assurance for Decommissioning of Palisades Nuclear Plant.Certified Rept of Status of Consumers Energy Co Decommissioning Funding & Trust Agreement Encl as Attachments 1 & 2 ML18066A4401999-03-25025 March 1999 Forwards Revised Best Estimate Fluence Evaluation Using Industry Data, Providing Justification for Using Industry Data to Determine Best Estimate Fluence.Review of Info & SE Requested ML18066A4191999-03-23023 March 1999 Forwards 1998 Annual Radioactive Effluent Release & Disposal Rept, for Palisades Plant,Providing Summary of Quantities of Radioactive Liquid & Gaseous Effluent Releases & Solid Radioactive Waste Processed During 1998 ML18066A4231999-03-22022 March 1999 Forwards Answers to 990311 Telcon Request for Addl Clarification & Revs Re ITS Section 3.4.Markups of Previously Submitted TS Pages & Revised Pages for Section 3.4 Also Encl ML18066A4121999-03-18018 March 1999 Concludes That Mod to Provide Automatic Switchover of Control Room Heating,Ventilation & Air Conditioning (CRHVAC) Sys to Emergency Mode Is Not Needed to Meet Regulatory Requirements.Mod Commitment Cancelled ML18066A4141999-03-18018 March 1999 Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles ML20204F2091999-03-18018 March 1999 Requests That Listed TS Change Requests (Tscrs) Be Issued with Allowance That Tscrs Be Fully Implemented within Sixty Days of Issuance.Request Will Allow Time for Completion of Final Training & Procedure Changes Associated with Amend ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML18066A4131999-03-11011 March 1999 Responds to NRC 990210 Ltr Re Violations Noted in Insp Rept 50-255/98-22.Corrective Actions:Analytical Evaluation, EA-C-PAL-98-1067-01, P-50A Case to Cover Stud Evaluation, Was Submitted to NRC on 981220 ML18068A5241999-02-12012 February 1999 Resubmits Relief Request 12,with Addl Info That Includes Specific Locations Where Relief Request Would Be Applied,Per 10CFR50.55a(g)(5)(iii) ML18068A5211999-02-11011 February 1999 Informs NRC That Implementation of Formal Industry Position on Severe Accident Mgt at Palisades Plant Was Completed on 981217 ML18066A4051999-02-10010 February 1999 Requests Copy of Consumers Energy (Palisades) Formal Response to RAI Dtd 990512 (USI A-46) ML18066A3921999-01-29029 January 1999 Forwards Licensee Interpretation of TS Requirements for Performance of SRs as Applied to Instrumentation Channel Calibr.Ltr Established No New Commitments ML18066A3891999-01-28028 January 1999 Submits Response to Concern Expressed in Insp Rept 50-255/98-06 Re Whether Palisades ISI Program Was Being Conducted IAW Applicable Requirements 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML18057A4811990-09-17017 September 1990 Confirms 900718 Telcon Notification Re Westinghouse Agreement to Join Utils as Equity Investor in Plant ML18057A4551990-09-0606 September 1990 Forwards Proprietary Info Re Dept of Labor Decision on Discharge of Former Employee of Util,Per NRC 900809 Request. No 10CFR50.7 Violation Occurred Since Job Performance Was Reason for Discharge.Encl Withheld (Ref 10CFR2.790(a)(6)) IR 05000255/19900101990-09-0404 September 1990 Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated ML18057A4521990-09-0404 September 1990 Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated ML18057A4381990-08-31031 August 1990 Forwards Info Re Contamination of South Radwaste Area,Per 10CFR20.302,in Response to NRC 900112 Request.Approval Requested to Dispose of Low Level Radwaste in Place ML18057A4371990-08-31031 August 1990 Forwards Analysis Concluding That Plant Reactor Beltline Matl Upper Shelf Energy Will Remain Greater than 50ft-lbs Until Yr 2032,per 900716 Commitment ML20059E0001990-08-29029 August 1990 Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990 ML18057A4201990-08-24024 August 1990 Forwards Revised Application for Amend to License DPR-20, Changing Tech Specs Re Incore Analysis Program.Request Revised Per NRC Comments During 900709 Meeting ML18057A4021990-08-22022 August 1990 Forwards Missing Pages from Decommissioning Funding Rept, Consisting of Pages 25 & 26 of Attachment a to Exhibit E ML18057A4071990-08-21021 August 1990 Forwards Tech Specs Change Request to License DPR-20,to Remove Redundant Requirements & Change Basis Statements No Longer Applicable ML18057A4121990-08-21021 August 1990 Forwards Application for Amend to License DPR-20,changing Tech Specs to Revise Wording for Reactor Protective Sys Trip Setting Limits for Steam Generator Low Water Level ML18057A4181990-08-21021 August 1990 Forwards Description of Changes Being Made to Plant Site Emergency Plan & Emergency Plan Changes.Change Allows Reduction in Shift Staffing During Cold Shutdown for Stated Staff ML18057A4241990-08-21021 August 1990 Forwards Application for Amend to License DPR-20,changing Tech Spec 4.5.1 Re Statement on Integrated Leak Rate Test ML18057A3841990-08-17017 August 1990 Provides Addl Info Re Transfer of Plant Ownership to Palisades Generating Co,Per NRC 900725 Ltr ML18057A3851990-08-17017 August 1990 Forwards Addl Info in Support of NRC Development of SER for full-term OL for Plant,Including Date of SER Providing Provisional OL to Plant & Summary of Valid Exemptions from 10CFR Regulations,Per Telcon ML18057A3911990-08-17017 August 1990 Forwards Replacement Pages,To Palisades Second 10-Yr Interval Inservice Insp Program. ML18057A3821990-08-14014 August 1990 Requests That Bechtel-KWU Rept 128901/MJS, Full Flow Testing of Motor-Operated Valve MO-1042A, Be Withheld (Ref 10CFR2.790(b)(1)) ML18057A3721990-08-0808 August 1990 Forwards Addl Info Re Util Request for Exemption from Separation Criteria of 10CFR50,App R,Section III.G.2 Re Containment Air Room ML18057A3561990-07-26026 July 1990 Forwards Certification of Financial Assurance for Decommissioning ML20055J1421990-07-26026 July 1990 Responds to Commitment Oversight Issue Resulting from Insp Rept 50-255/90-08.Commitment Mgt Seminar Training Will Be Complete Prior to 901001 ML18057A3411990-07-18018 July 1990 Forwards Revised Proposed Tech Spec Page 6-3,now Designated as Page 6-1b,adding Section 6.3.4,now Designated as Section 6.3.5 to Remove Organization Charts,Per Generic Ltr 88-06 ML18057A3381990-07-16016 July 1990 Advises That Util Does Not Foresee Need to Rely on Section V.C of App G to Remain in Compliance W/Upper Shelf Energy (Use) Requirements Re Use of Matl in Reactor Beltline ML18057A3281990-07-13013 July 1990 Responds to Request for Addl Info Re Second 10-yr Interval Insp Program,Per 900418 Telcon.Util 900329 Response Revised to Reflect That Certain Components in Class 2 Sys Should Not Be Exempted,Per IWC-1220 of 1974 ASME Code Section XI ML18057A3191990-07-0909 July 1990 Forwards Performance Indicator Trend Graphs for Jan 1989 - May 1990 ML18057A3201990-07-0606 July 1990 Discusses Reassessment of Control Room Temp Following Station Blackout Event.Results of Analysis Indicate That Control Room Temp Will Remain Below 112 F for 4 H After Onset of Blackout ML18057A3171990-07-0303 July 1990 Provides Summary of Upgrades Made to Plant Electrical Distribution Sys,Per 870714 Loss of Offsite Power Event When Inadvertent Actuation of Water Deluge Spray Sys for 1-2 Startup Transformer Resulted in Bus to Ground Fault ML20058K3771990-07-0202 July 1990 Forwards Rev 26 to Security Plan.Rev Withheld (Ref 10CFR73.21(c)) ML18057A3101990-06-25025 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements on Corrective Actions. ML18057A3111990-06-25025 June 1990 Forwards Endorsements 116 & 117 to Nelia Policy NF-179 & Endorsements 102 & 103 to Maelu Policy MF-50 ML18057A3031990-06-22022 June 1990 Provides Addl Info Re Environ Qualification of Instrument Circuit Associated W/Steam Generator Pressure Channel PT-0752D,per Insp Rept 50-255/90-05.Circuits Spliced Directly to Pigtail from Electrical Penetration Connector ML18057A3001990-06-21021 June 1990 Concurs W/Nrc Change in Terminology & Submits Revised Proposed Section 4.14 of Tech Specs ML18057A2771990-06-15015 June 1990 Forwards Corrected NRC Form 474 Re Simulation Facility Certification,Indicating Exceptions to Ansi/Ans 3.5 ML18057A2901990-06-13013 June 1990 Forwards Application for Amend to License DPR-20,revising Tech Spec 3.3.1.b Re Safety Injection Tank Min Level ML18057A2941990-06-12012 June 1990 Advises That Submittal of Second Interval Inservice Insp Program Delayed from 900615 to 900715,per 900418 Telcon ML18057A2641990-06-11011 June 1990 Provides Response to NRC Requalification Exam Rept Dtd 900410 on NRC Concerns Re Facility & Training Ctr Staffing. Adequate Staffing Will Be Maintained to Ensure Operator Requalification Program Successful ML18057A2591990-06-11011 June 1990 Forwards Palisades Simulator Certification Submittal. ML18057A2711990-06-11011 June 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.1.1i in Order to Maintain Plant in Hot Shutdown While Repair Made to Pressurizer Heater Power Supply.Request Based on 900608 Failure of Heater Transformer 15 ML18057A2631990-06-10010 June 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.1.1i to Enable Plant to Be Maintained in Hot Shutdown While Repair Made to Pressurizer Heater Power Supply.Waiver Requested for 900611-18 ML18057A2571990-06-0808 June 1990 Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-255/90-12.Corrective Actions:Continuing Training Program Will Be Developed for Supervisors That Will Discuss Fire Protection Program Implementation Topics ML20043D0601990-06-0404 June 1990 Forwards Rev 25 to Security Plan,Including Changes to Security Plan Drawings to Clarify Protected Area Boundary within Plant Security Bldg & Vital Area Boundaries in Other Specific Vital Areas of Plant.Rev Withheld (Ref 10CFR73.21) ML18057A2581990-06-0101 June 1990 Forwards Revised Response to Violations Noted in Insp Rept 50-255/89-26.Concurs That Tests Performed Using Instrumented Insp Technique During 1988 Refueling Outage Considered Invalid ML18057A2561990-05-31031 May 1990 Advises That No NPDES Notifications Required Nor Any Repts of Oil or Salt Occurred During Nov 1989 - Apr 1990 ML18057A2541990-05-30030 May 1990 Forwards Response to Technical Evaluation Rept EGG-NTA-8333 Which Evaluated Plant Compliance w/NUREG-0737,Item II.D.1 & Requested Addl Info Re New PORVs & Block Valves No Later than Jan 1990 ML18057A2511990-05-30030 May 1990 Forwards Final Response to Concerns Re Porv/Block Valve Mod, Per 900308 Meeting.Bechtel Technical Rept Withheld ML18057A2501990-05-29029 May 1990 Forwards Investigation Rept Re Unsatisfactory Performance Testing of Fitness for Duty Program Blind Performance Test Samples ML18057A2411990-05-24024 May 1990 Forwards Revised Application to Amend License DPR-20, Consisting of Revised Attachments 1 & 5 to 890227 Amend Request,Reflecting Transfer of Plant Ownership ML18057A2311990-05-17017 May 1990 Forwards Analysis of Reactor Pressure Vessel Fast Neutron Fluence & PTS Ref Temps for Palisades Nuclear Plant. Rept Concludes That PTS Screening Criteria Will Be Exceeded at Axial Welds in Sept 2001 as Opposed to Mar 2002 ML18054B5861990-05-0707 May 1990 Forwards Monthly Trend Graph Rept for Jan 1989 - Mar 1990 Covering Safety Status Performance Indicators for HPSI, Auxiliary Feedwater,Emergency Ac Power,Lpsi,Containment Spray & Svc Water Sys ML18054B5801990-04-30030 April 1990 Responds to Request for Addl Info on Proposed Administrative Changes to Tech Spec Section 3.0.4,per Generic Ltr 87-09. Licensee Will Implement Program to Assure Appropriate Level of Mgt Approval Required When Operating Conditions Changed ML18054B5741990-04-25025 April 1990 Requests That Correspondence Re 890227 Application for Amend to License DPR-20 to Permit Transfer of Ownership of Plant Be Sent to Listed Address 1990-09-06
[Table view] |
Text
_____ ___ _ _ _ _ -
o p
. seear
~ cr b . .:=, y .
consemtns H v..
. P ..,.Gra ve.
. ,,,.d.,,,,, ,
,\ se..ti . ,
.. p0Wer Wg
. ce,eralc w nt i
.. . ,...h..
Generil allOrney Company R.s e ver.
H , t . Clash f.ne.e.eest Of'ar ns: 217 Wasa.t Mac.eisynre Avenue. JacHors. Mac,hager 4's?') . Arca Ccsce 6t? 794. Otto C . E Meentt o . x . eri....n S. H. Rednee
- w. t , w..n.,
December 20, 1971 sur..o. att e rs ,
J L . Bacon /
A. D. Dass C . D . On-son R . , . G od tro ut I ,' : ",',l", AFC DOCKET NO. 50-255 - PALISADES PUdC A . D. McCallunt W. R . MsHs 1 J . K. Restrick D. R. Hood J . M . S en.t h 4- t r, A. T. Udays
'"' ~
Mr. Samuel W. Jensch, Chairman Dr. Clarke Williams Atomic Safety and Licensing Board Brookhaven National Laboratory U. 3. Atomic Energy Co.miusion Upton, L.I., New York 11973 Washington, D. C. 20545 Mr. Warren E. Nyer Idaho Nuclear Corporation P.O. Box 1845 Idaho Falls, Idaho 83401 Gentlemen:
In view of the AEC Regulatory Staff's December 10, 1971
/ letter to the Board, in which corrosion of the Palisades reactor vessel closure studs was mentioned, I an enclosing a copy of our formal report (required under the reportin6 requirements of Opera-ting License No. DPR-20) of the problem.
As the report states, corrosion was found on many of the studs, stud nuts, vashers and holes, and on the head and vessel flange surfaces. The corrosion was caused by an accumulation of borated water during venting operations conducted after filling the primary system. Venting equipmer', is being modified to pre-vent recurrence.
During nondestructive magnaglo testing, 20 of the 54 studs ~ ,
exhibited " linear indications." Staff counsel has mistakenly re-ferred to these indications as " cracking. " Metallurgical examination by Co:::bustion Engineering, Inc. in Chattanooga, Tennessee has verified that the indications were not defect indications, but rather indi-cations resulting from magnetic permeability variations probably C'
8306130069 720128 (J6 PDR S
ADOCK 05000255 pyg ,
Cuh ' ~
m X,,(
~
O O
Mr. Samuel W. Jensch, Chairran P.r. Warren E. Nyer Dr. Clarke Williams Decc=ber 20, 1971 caused by slight variations in surface cold work induced by machining and possibly intensified by heating incurred in phos-phate coating and in service. The metallurgical examination confirmed that the studs are fit for service.
Yours very truly,
\. . :: .'
., e JLB:bbm [ Jupd L. Eacon CC: Myron M. Cherry, Esq.
Lewis D. Drain, Esq.
Parvin F. Metge, Esq.
Joseph S. Scinto, Esq.
George F. Trowbridge, Esq.
Mr. Stanley T. Robinson, Jr.
Curtis G. Beck, Esq.
Algic A. Wells, Esq.
Nathaniel H. Goodrich, Esq.
Eric V. Brown, Sr., Esq.
[ % Consumers Power (s.OyCompany
%g;,,
\ . IQW d ff c.n.,a ome.s. 2i2 w u u.chsgan Avenue Jackson. Mich. gen 49201. Area Code 517 788-OSSO December 17, 1971 Dr. P. A. Morris, Director Re: Docket 50-255 Division Reactor Licensing License No DPR-20 United States Atomic Energy Commission Washington, DC 20545
Dear Dr. Morris:
The purpose of this letter is to formnlly report the difficulty experienced in removing the nuts from the reactor vessel studs at our Palisades Plant.
During the investigations of and repairs to the control rod drive mechanisms (reference our Special Report No 1 dated December 3, 1971), it was decided to remove the reactor vessel head in order to inspect the hanger sections of the control blades.
However, there were difficulties experienced in removing the nuts from the reactor vessel studs.
These difficulties were reported to the Division of Com-pliance representatives who subsequently reviewed and witnessed the inspection and rework program on these reactor vessel studs.
The cause of this problem, the results of subsequent in-vestigations and the nature of the rework of these studs follow.
The reactor vessel head removal process revealed that 41
! of the 54 reactor vessel stud nuts were frozen to the studs to the extent that they could not be removed using the stud tensioner. The stud tensioner has a very low mechanical advantage for turning the nuts. The studs and nuts were removed with the use of bolt heaters and a special slugging wrench under the supervision of Combustion Engineering, Inc personnel. The difficulty experienced in unbolting theheadwasattributedtocorrosionand/orcorrosionproductson the stud shank and threads. Corrosion products were also observed on the head flange stud holes, head flange surface, reactor flange surface, exterior of nuts and inner circle of the stud washer.
All studs were sent to the stud manufacturer for assessment of corrosion and rework. Two nuts acecmpanied the studs. These nuts u were selected as visual examples of the most corrosion. The corrosion on the studs was centered on the shank area and the first few threadsp nw ==s M&c" + e+A
O O 2 Dr. P. A. Morris December 17, 1971 adjoining the shank on each end of the chank. Approximately three (3) threads on the bottom (vessel end) of the shank showed heavy corrosion while approximately six (6) threads were affected on the top end of the stud. From visual appearance of the corroded threads, it was ob-vious that not more than one (1) to two (2) corroded threads were en-Saged in the nut or the vessel flange. The balance of the threads was unattacked. They exhibited a coating of lubricant with some heavy lubricant buildup in the th*ead roots. The lower end of the stud shank showed a corrosion band on all studs that was approximately 1-1/2" wide.
When lower end thread corrosion was added to shank corrosion, a band of approximately 1-3/4" was noted. This corrosion was fairly uniform over all studs. This band width corresponds to a countersunk area on the vessel flange.
Corrosion products were either a low-temperature aqueous red oxide believed to be aFe00H or a high-temperature hard gray deposit believed to be aFe203 . The stud chanks had general corrosion. In many cases, there was a streaming pattern indicating corrosion fres a vapor phase since the streaming patterns were from the bottom of the stud to the top. The two nuts that were sent were Ihr:bers 51 and 52.
They had a heavy deposit of salt (believed to be boric acid salt) on the exterior flats. Only minor corrosion was evident on the nut thread leads. There was corrosion on the inner circle of the washers, the vessel flange and the head flange. Stud holes in the head flange were
, corroded and showed evidence of streaming like that found on the stud
! shank. The threads in the vessel flange were only slightly affected l by the corrosion. Tbere was only minor corrosion to the thread lead and the bottom of the stud holes showed some slight evidence of cor-rosion products.
Rework procedures were d?veloped to refurbish the studs as follows:
I. Removal of Corrosion Products A. Machine heavily corroded areas on shank next to threads on both ends. Permission was received from CE, Chattanooga, to reduce the shank diameter by a maximum of 0.020" below present drawing limits. The stud manufacturer planned to remove 0.015" maximum.
B. Grind the corroded threads to clean them. Permission was re-ceived from CE, Chattanooga, to reduce the minor diameter by a maximum of 0.010".
C. Re=aining corrosion spots were to be hand polished.
D. Corrosion product cleanup and the stripping of the Parkerizing were to be completed by blasting with steel shot.
Dr. P. A. Morris 3 December 17, 1771 II. Nondestructive Testing The studs were to be magnetic-particle tested by the "magnaglo" method after shipping. Testing is done to ASTME-138-63 and CE Specifications.
III. Parkerizing A magnesium phosphate Parkerized coating is to be applied to the studs.
IV. Uut and Washer Work The only work required on the nuts and washers was removal of the corrosion products.
The rework has been completed and the studs returned to the Palisades Plant for reinstallation. During the nondestructive testing phase of the rework of the studs, 20 of the 54 studs exhibited several linear indications. All indications were in the shank portion of the studs and were in a circumferential orientation. Two of the studs showing these indications were shipped to Chattanooga, Tennessee, for metallurgical investigations to detemine the cause of these linear indications. A description of the metallurgical investigations con-ducted and their results are contained in Attachment I.
From the metallurgical investigations perfomed, it was verified conclusively that the circu=ferential "magnaglo" indica-tions on these studs were not defect indications. The sensitive "magnaglo" test revealed indications resulting frcm magnetic permeability variations probably caused by slight variations in surface cold work induced by machining and possibly intensified by heating incurred in phosphate coating and in service. .
It has been concluded that the corrosion in all cases re-sulted either directly or indirectly from borated water finding its way to the vessel flange (outside the sealing rings). All signs in-dicate that the aqueous solution had lain on the flange and countersunk areas around the stud holes. The solution vaporized upon vessel heatup and/orevaporatedupthroughtheheadflangetocorrodetheareaatthe top of the studs and the washer. There is no evidence to indicate that the solution attacked the studs by getting underneath the washer or nut.
All evidence indicates the corrosion to be due to attack by boric acid solution. The Parkerized coating offers no special corrosion protection in this case.
The source of the borated water was primary coolant which accumulated on the vessel flange during venting operations conducted after filling the pricary system. Venting equipment at the Palisades Plant is being modified such that there is no possibility of getting
Dr. P. A. Morris 1+
December 17, 1971 borated water on the reactor vessel flanges during venting operations in the future.
The effects of the reduction in the cross section of the studs (resulting from refurbishing) were considered during the de-velopmental stages of the rework procedures. This analysis indicated an acceptable change. The final Stress Report will be supplemented to include the changes due to refurbishing. The two studs that under-vent further metallurgical investigations will be documented separately in the final Stress Report.
The stud tensioning procedure has 'ceen reevaluated in li6ht of the slightly reduced stud cross sections. No revisions to this procedure are necessary since the differences in shaft extension during tensioning is negligible.
During discussions with Division of Compliance personnel, Consumers Power Ccmpany agreed to perfom additional inspections of the vessel studs and nuts during the first scheduled refueling outage.
This inspection will be performed in accordance with Item 1.8 of Table 1.3 1 of the Technical Specifications for the Palisades Plant. At 4
least ten (10) studs will be inspected. The surface examinations re-quired will be performed by the magnetic particle method. The first refueling outage is currently scheduled for September 1973 In addition, CE has agreed to establish a laboratory test program to further evaluate the compatibility of CE normal phosphate coatings and super moly-lubricant in the design environment of the studs. The details of this laboratory test program are currently being developed.
The cause of the corrosion to the reactor vessel studs has been eliminated. The thorough metallagraphic examinations conducted -
revealed that the studs are in good condition. All studs have been refurbished to eliminate similar future difficulties in removal.
Yours very truly, Robert L. Haueter (Signed)
RBS/dmb Robert L. Haueter Electric Production CC: Boyce H. Grier, Superintendent - Nuclear USAEC
o o ATTACREliT 1 REPORT OF II;VESTIGATION OF CLOSURE LEAD STUDS COI; SUERS PC' DER CO.vPANY PALISADES PLAITf C-E CO M ACT P.966A December U2, 1971
+ .
$r ,Y) d' ID,j))lhifg(N "
ve=,
O O December 12, 1971 CO:7 TRACT 2966A CONSUMERS POWER CO.
PALISADES PLMir CIOSURE HEAD STUDS INTRODUCTION It had become necescary to remove the vecsel head. Upon starting to remove the studs it was noted that a ructing condition was pre.sent, which was apparently caused by spillage of borated water and possibly a dichromate solution. Ee-cauce of the rusted condition, C-E concidered it desirable to closely examine the studs to determine whether or not there was any damage even though it was considered unlikely. C-E arranged for the removed studo to be sont to the stud manufacturer for clean up and careful examination by ".nagnaglo", and to have C-E personnel present.
In refurbishing the studs the manufacturer reground the threads, and machined the chank using a carbide tool removing 0.010 to 0.015 inches from the stud
~
shank diameter. Upon "engnaglo" testing, 20 of the total of 54 studs exhibited several linear indications. All indications were in the chank portion of the studs and were in a circumferential orientation. Liquid penetrant testing was also per-formed at the canufacturer and no indications were found in this orientation.
No indications were present in the threaded portion of the studs. The indications varied in length up to a taxitum of 1-3/h inch. These studs are 7 inches diameter and 56 inches long. They are made to requirements of C-E Specifications as follows:
Material and Ultrasonic Testing C-E Purchase Spec. No. P0H16(c)
A540 Grade B24 Class 3 "Magnaglo" Testing (both before and after threading)
C-E IGP Spec. No. 2.4.2.5(a) and ASTM E138-63 Phosphate Coating C-E 162 Spec. No, h 4.4.l(a)
On Friday, December 10, 1971, two of the refurbiched studs were received for metallurgical investigation. One of the two was representative of the most pronounced "magnaglo" indications (ykk), and the other stud was representative of the average "magnaglo" indication appearance (#43). The stud ph4 exhibited 13 indications, mostly in the central section of the shank. These varied in circumferential length from 1/8 inch to 1-3/4 inch.
4 O O CONCLUSIONS
- 1. Indications were disclosed by "nagnaglo" testing. These were cir-cumferentially oriented.
- 2. Examination of the indication areas by metallography (both etched and un-etched), at the original surface and to depths at which the "tagnaglo" indication disappeared, revealed that no " defect" was present at any stage.
- 3. The "tagnaglo" indications are present in a right hand thread pitch orientation of soneuhat steeper helix angle than that of the present surface finish. The indications result fron slight differences in taterial magnetic permeability properties probably caused by slight variations in surface cold work induced in earlier tachining steps and possibly intensified by heating incurred in phosphate coating and in service.
4 "Magnaglo" indications of virtually identical appocrance were present in a stud of the same size frca another contract manufactured with the same procedure, and subjected to a hydrostatic test use but not service. The "tagnaglo" test was also perforned after removal of the phosphate coating.
- 5. The extensive examination confirms that, without any doubt, the subject studo are satisfactory for use.
Stud Manufacture C-E purchased the raterial for these studs es 7-1/2 inch diameter round bars on C-E Purchase Order No. h6 60lb4 The vendor is believed to have straightened the bar stock on a " bulldozer" (press) and not to have used a rotary straightener.
The bars were assigned C-E Code No. D-3816. C-E subcontracted the nachining on C-E Purchase Order No. 46 62329 Machining and "magnaglo" testing vere per-forted and the studs returned to Chattanooga where they were phosp' ate coated on C-E Purchase Order No. 47 47464 After phosphate coating no further "magnaglo" testing was performed.
The stud manufacturer ground the threads, and machined the shank using a carbide tool. The rough cut on the chank was to a depth of 0.040" to 0.050" per side using a 0.015" to 0.018" feed. The finish cut on the shank was with a carbide tool with 1/32" nose radius at 200 feet per minute with 0.009'to 0.010" feed to a depth of 0.010" to 0.015" per side. The cut was in a right hand thread direction with the stud chucked at the top end and a steady rest near the bottom end threads.
Stud Use The studs have "seen" a total of four prestressing cycles - one at C-E on hydro-static test, and three at the job site. The studs had reached a tetperature in service of approximately 500 F. On each of these cycles a lubricant was used.
This lubricant is " Super-Moly". It contains an " inhibitor". It is molybdenum dicuphide with mineral oil base.
O O Other Studs Two studs of identical design available in Chattancoga from another contract were exanined simultaneously with the subject studo. These studs were of identical manufactire except the phosphate coating was perforted by a different vendor.
Each of these studs had been used on a shop hydrostatic test. One was "tagnaglo" tested with the phosphate coating left on and one after removal of the phosphate conting.
METALLURGICAL IUVESTIGATIOy Ittediately upon "tagnaglo" exatinatica by experienced personnel at C-E, it was recognized that the indications disclosed were note form of non-relevant indication and did not constitute a " defect". Evnninat. ion procedure by "tagnaglo" vas performed with equipment and technique duplicating that used by the stud manufacturer and with identical results, as confirced by an employee of Chattanooga Nuclear Quality Control Departtent who was present at the testing at the stud manufacturer and at the testing of the returned pieces at C-E laboratory.
Procedures and examinations to confirn this conclusion are given below.
After the "tagnaglo" testing results obtained at the stud manufacturer were duplicated on equiptent at Metallurgical Research and Development Laboratory in Chattanooga, a series of tetallographic exeninations were tade directly on the
- stud surfaces at the location of "tagnaglo" indications. Exanination was performed after a minitum enount of total vaa renoved from the surface (0.001" to 0.003")
and after probe grinding to various depths up to 0.030" which partly or completely removed the "tagncE l o" indications. Probe grindins was controlled to expose completely the entire subsurface zone associated with "magnaglo" indications to direct metallogrcphic viewing. Quality of the metallographic finish and metallographic ctch vere fully ec= parable to conventional laboratory preparation of stall specimens. Viewing was with a binocular laboratory microscope of superior optical performance (Leitz ND) at tagnification of 50X to 1000X. The visual exanination through the microscope was fully comparable to laboratory bench metallegraphy in all respects and no compromise was necessary regarding thorou6h ness of exanination. For these reasons, it was not necessary to destructively section any of the studs to obtain unequivocal results and no further information is to be gained by destructive sectioning.
Stud Number h4, palisades Probe grinding 0.013" deep was perforced on stud #h4 by the stud manufacturer in an attempt to establish the depth of the condition causing the "tagnaglo" indications. As the rough surface appeared to obscure the "tcanaglo" results, this spot was carefully polished with COO grit to avoid more than 0.001 additional metal removal and to obtain a better surface for testing. Afterwards this spot was examined repeatedly at the sane test conditions used at the stud manufacturer and at higher and lover field strength.
.O . . .
O ..
IETAIJAT30I0AL IL"ESTIGATYOIl (Cont'd.) ,
"F.agnaglo" indications were not precent doun in the 0.013" deep excavation ~Nt could be seen at the edge of the excavation. Thisexcavationwas31-5/8"below top end.
An area showing indications, 32" from the top end of stud //44, was polished metallographically to a depth of 0.003" below the original cachined surface.
"!bgnaglo" indication was still present in this area after 0.003" metal removal.
This area was examined up to 1000X as polished and arter etching with nital.
Iio indications of defects were found.
One circumferential indication about 32 inches from the top end of stud //4h was l examined metallographically by grinding two dimples, about 0.020" deep, at the two ends of the indication until the "cacneglo" indications were no longer present, leaving the center portion unground. The dimples and the unground portion were then polished tetallographically, after markira the unground portion of the in-dication with a center punch. /d'ter poliching, the unground portion and the slope - , _
of the dimple were exnmined at magnifications up to 1000X, simulating the examination of a cross section throu6h the ind'. cation. Iio defects or other abnormalities were detected, either in the as-polished or etched condition.
Stud liumber 43, Palisades Areas showing circumferential indications in stud #43 were examined in a similar tanner. Two adjacent indications, about an inch long were ground and polished so as to leave an unground portion. After polishing to a depth of 0.013" and 0.029", the indications disappeared at the bottom of the dimples. The unground portion was punch marked to identify the indication line, then polished lightly (about 0.001"). Fleroscopic examination revealed no defects. The slope of the dinples was alco examined microscopically after metallographic polishing into the area shoving no "tagnaglo" indications. This slope area, which was in effect a cross section through the zone between indications and absence of indications, . . .
showed no evidence of defects.
Other Studs Two studs for another contract, which were in the shop and had not been in service, were also examined in a similar tanner. One stud, #52, showed "magnaglo" indications on the as-phosphated surface. Examination of the surface before polishing showed circumferential marking. On polishing, the visual evidence of the indication disappeared, although sone of the phosphate conversion coating was still present in spots. These spots disappeared after
_h_
o 9 polishing to a depth of 0.003", and no defects or abnormalitics were visible.
Upon re-examination by "magnaglo", however, the indication una still present.
Another stud from the same contract, #53, was also examined after removing the coating by polishing in a lathe with emery paper. This stud also showed scattered circumferential indications by "mu6naglo" techniques. No further metallographic examination was performed on this stud.
Summary Close examination revealed that all of the circumferential1y oriented "magnaclo" indications are at a slight pitch angle at a slighth steeper helix angle than that of the present surface finish. This is probably the orientation of the pitch helix used in a cut previous to the final machining cut. The stud manufacturer reported use of a right hand pitch during their machining operation.
The "masnoglo" indications are also at a right hand pitch angle. The sensitive "magnaglo" test in undoubtedly revealing indications resulting frcm magnetic premeability variations probably caused by slight variations in surface cold work induced by tachining and possibly intensified by heating incurred in phosphate coating and in service. Such cold work may have been introduced by another fabrication operation not present 4 identified.
Results of the exncination described above have conclusively verified the judgment that circumferential "mcanaglo" indications on these studs are "non-relcvant" and are not defect indications.
Technical evaluation was performed prior to the removal, during refurbishing, of the 0.010" to 0.015" stock from the chank of the studs. The analysis indicated an acceptable change. The final Stress Report will be supplemented to include this change.
'er
)
_ = , -
w .yv %._ -m,. . _ _
Jc ..
' ' ~~~ ' ,
y *, n [ .y 4 T{ . ( ..
~.# - ,
' . ( ,,.;,;..
. .~~
d: ! .,. f
/'~s ., t. ! "
el c ,*', , , g- , + ..
E m m M3Mnhm MGCum S' L. Kornblith Jr CO , . Pa0LLUG AT PALICADES AND 'ww.u;i ICINT 3 Attached cro copica of the propo cd TZ3 plans for 9
4 'g;=e3 ,, g g,g;3ge gg'enj,g gg CO investiCatinc:
I n. T. Car 1 con # CO 1. Eclic: des Denetor Vesoel Stud.Corronion Problem.
" 2. Tu.:ty Ibint 3 nelief valve needer Isilure.
- 2. Jce Collins of the Tcchnical Oupport Branch 1 -
has been c:cicaca to tche the lead in these inven-ticstir as. 'C2e Inspection and Enforec=cnt Branches vill be hept inferr.ca of the at: cults of the inves-tication as it progresces.- A pro =pt referral of anY.e g infor:::stica to TC3 vhich would not normally cone to 1 our attenticn yould be apprcetated.
9, 'Ihe aboro investigntions and assignments have been 5 L' approved by Mr. L. D. Lov, Director, Division of 4: Ccsplicce.
cc: 11. D. I' armer, CO 9' , U. J. .C@ma, C0 l Willia:s D. Famer ,
~
Acting Chief t ,' Technical Support Br.
I c
T,
- 7M,1 12/17h1 .
i
~
k.
{1 i r .
I - ,
7
.4' E- ;., ..
1 - . ,
ts, .
~
...+ .
1 .
rt *-
r, m g ~,
t ..
L. ,
~
, 't %-
(-
.h.
..- j
- ] 4.
~ -
ou.
- p.
\ V 'g , '
\
HF L
l ..
- l (, (m.[
4
. go gf
..w a. .
4 .. y :i. k>
- n. .
r .
c vG ] omero.
. CO : TSB ..$.h.i... .
~ .......
3 l sSIhmer:rc .
. . , su m ur > . , . . . . . . . . . . . . . ,
u L k, ,
i
'.J ". , m , 12.../.1..7../.71... . . ..
. ... . .. ./. . . .'. .\. _.'- .- -
j
. . . . .ft U S Govt R.*MENI PJMNTb OFFCg 1971--416.469
' Form arc 3tB L ev.9 R 53) AECM 0240 l N t .c . ... ,
\. i
.a. .
,v,c.
^
-k l
/