|
---|
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 ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
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 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 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. 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 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 ML18066A4141999-03-18018 March 1999 Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles 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 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)) 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 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 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 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 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 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 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 ML18057A3911990-08-17017 August 1990 Forwards Replacement Pages,To Palisades Second 10-Yr Interval Inservice Insp Program. 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 ML18057A3841990-08-17017 August 1990 Provides Addl Info Re Transfer of Plant Ownership to Palisades Generating Co,Per NRC 900725 Ltr 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 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 ML18057A3561990-07-26026 July 1990 Forwards Certification of Financial Assurance for Decommissioning 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)) ML18057A3111990-06-25025 June 1990 Forwards Endorsements 116 & 117 to Nelia Policy NF-179 & Endorsements 102 & 103 to Maelu Policy MF-50 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. 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 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 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. 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
consumers Power company General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550 November 16, 1982 Dennis M Crutchfield, Chief Operating Reactor Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commisssion Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - REQUEST FOR RELIEF FROM SPECIFIC ASME B & PV CODE REQUIREMENTS Pursuant to 10 CFR 50.55a(g) and Palisades Technical Specification 4.3.c relief requests from certain provisions of Section XI of ASME B & PV Code are being submitted for NRC review and approval. This relief request is in addition to a relief request by letter dated June 13, 1978.
The specific areas where relief is requested and the basis for that request are presented in Attachment 1 to this letter. These requests have been reviewed and approved by plant management and the PRC and will be incorporated into the Palisades Nuclear Plant 40-year Master Inservice Inspection Plan upon approval by the NRC.
Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades fllJrA
/loV7 8211220006 821116 PDR ADOCK 05000255 G PDR OC1182-0012A-NL02
ATTACHMENT 1 PROPOSED REQUEST FOR RELIEF FROM THE PROVISIONS OF ASHE B & PV CODE SECTION XI PURSUANT TO 10 CFR 50.55a(g)
OC1182-0012A-NL02
( PALISADES NUCLEAR PLANT INSERVICE INSPECTION Review and Approval For Proposed Requests for Relief from the Provisions of ASME B&PV Code,Section XI, Pursuant to 10CFR50 50.55a
~L General Office T-ec...,hll_.,_i,,..c"'"a-1-'lf-"R-e-...v_.i_ew~~---*
.LL
~
Initiated by (NPS (ISI Coordinator) echiliCa1~v~NPS) ~~D te Administrative Review Date (Tech Supt)
( /-h7/8L 0\2.~~~ ~2- 4LR c, -\b-1'1.-
~ Plant R~ew Committee Date (QA-05#)
q /,5'ffl...
Date Note: The attached document is to be incorporated into the Palisades Nuclear
- Plant 40-Year Master Inservice Inspection Plan upon review/approval.
/,.--,,
J. . .o, 1982 RELi EF REQUEST PALISADES NUCLEAR PLANT Area of Sec XI. Safety Re I i er Category Component Function Class Relief Requested Testing Substituted Implementation I B1.21 B-A Vessel Closure Head Primary Pressure Boundary 1 Longitudinal Meridional and Circum Welds in Rx Vessel Heads Inacces-sible for Volumetric a.
b.
c.
Vessel Hydros Vessel Coupons B1.10, 81.20, B1.30, B1.40 a.b. Tech Specs
- c. 40-Year Plan Exam Testing Vessel Bottom Head Primary Pressure 1 Meri d i ona I & C 1*rcum a. Vessel Hydros a.b. Tech Specs B1.21 B-A b. Vessel Coupons c: 40-Year Plan Boundary Seam Welds Generally
.e B1.22 c. B1 . 10, B1
- Inaccessible for Volumetric Exam B1.30, B1.40 Testing I B5.10 B-F Vessel Safe End Welds (Nozzle Safe End)
Primary Pressure Boundary 1 Not a Dissimilar Metal Weld Welds Covered as 89.11 8-J 40-Yea r PI an Not a Dissimilar Metal Welds Covered as 40-Yea r PI an I B5.30 B-F Steam Generator Safe End Welds (Nozzle Safe End)
Primary Pressure Boundary 1
Weld B9.11 B-J B7.10 B-G-2 CROM Bolting Primary Pressure 1 Nonperipheral CROM a. Vessel Hydros a. Tech Specs Boundary Bolting Inaccessible b. 81.11 Testing b. 40-Year Plan for VT-1 PCS-42-RCL-1H1-2LD, Primary Pressure 1 Inaccessible for UT a. Hydros a. Tech Specs B9.11 B-J b. Remaining B-J b. 40-Year Plan B9.12 3LU, 3, 3LO Boundary PCS-42-RCL-2H1-2LO, We Ids In System 3LU, 3, 3LO
- a. Hydro a. Tech Specs I B9.11 B9~ 12 B-J PCS-42-RCL-1H-1,2 PCS-42-RCL-2H-1,2 PCS-30-RCL-1A-15, 15L0-1, 15LD-2, Primary Pressure Bounds ry 1 Inaccessible for surface Exam (Volumetric Exam To Be Done From ID) b.
c.
Remaining B-J Welds 100% UT of Pipe b.c. 40-Year Plan
~
16LU-1, 16LU-2, 16 Thickness
- PCS-30-RCL-1B-13, 13LD-1, 13L0-2, 14LU-1, 14LU-2, 15 PCS-30-RCL-2A-14, 14L0-1, 15LU-1, 15LU-2, 16 PCS-30-RCL-2B-14, 14L0-1, 14LD-2, 15LU-1, 15LU-2, 16 Reactor Coo I ant Primary Pressure 1 Inaccessible & Not a. Hydros a. 40-Year Plan B12. 10 B-L-1 Pump Casing Welds Bounds ry lnspectable With Volumetric Technique rp0682-0111a-46-155
- ,,,,.....,._. *\
..* 1~A'.. ~.\
r:-:-,
' J(. .o, 1982 Area ..
of . Sec XI Safety Rel lef Categor~ Com12onent Function Class Relief Reguested Testing substituted lm12lementatlon I B12,20 B-L-2 Reactor Coolant Pump Casing Internal Surfaces Primary Pressure Boundary 1 Inaccessible a. Hydros . a. 40-Year Plan C5.11 C*F ESS-24-SIS*SH1-201, Pressure Boundary 2 Inaccessible for UT a. Hydro a.b. 40-Year Plan 202, 203, 204 b. C5.10, C5.20 Testing on Re*
mainder of System C5.11 C*F ESS-24*SIS-SH2-201, Pressure Boundary 2 Inaccessible for UT a. Hydro a.b. 40-Year Plan 202, 203, 204 b. *cs. 10, CS.20 Testing on Re*
mainder of System e
85.20 B*F Piping Welds Primary Pressure 1 Util lzation of Hole None - Examinations 40-Year Plan
. 85.40 Boundary Type UT Reflectors for Performed as 85.50 Thick Piping Scheduled 89.11 B-J Piping Welds* Primary Pressure 1 Utll ization of Hole None - Examinations 40-Year Plan 89.12 Boundary Type UT Reflectors for Performed as Thick Piping Scheduled C5.21 C-F Piping Welds Pressure 2 Utilization of Hole None - Examinations 40-Vear Plan C5.22 Boundary Type UT Reflectors for Performed as Thick Piping Scheduled rp0682*0111a*46-155
(* . Notes on Relief Requests RR-1 Items Bl.21, Bl.22 (Long, Cir and Meridional Welds in Rx Vessel Heads)
BASIS STATEMENT The dollar plate weld in the closure head is inaccessible for .
volumetric examination due to control rod guide tube constraints.
Meridional welds in the closure head are partially accessible for volumetric examination.
An attempt will be made to volumetrically inspect the meridional and
- circumferential seam welds in the bottom head during the next refueling outage in which mechanized inspection is performed on the Rx vessel.
REMARKS See CE Dwg E-232-139-1.
IMPLE!'lENTATION & RELIEF REQUESTED Meridional welds in the bottom heads and circumferential welds in the bottom head may be accessible for volumetric examinations. The dollar plate weld in the closure head is ~xempt from volumetric examination and shall be visually examined during the system pressure test.
RR-2 Items B5.10, B5.30 (Nozzle to Safe End Welds)
I BASIS STATEl'lENT The transition pieces between the carbon steel nozzles and the carbon steel piping are also carbon steel and thus not dissimilar metal safe ends. The nozzle to safe end welds are therefore classed as B9.ll, B-J I welds rather than B5.10 or B5.30, B-F welds.
See CE Dwg E-232-119-11.
IMPLE!'lENTATION & RELIEF REQUESTED These welds should be included and inspected to Category.B-J requirements with the restriction that the inspection be expanded to include 100% of each weld during each inspection interval. However, this examination could be included in the 25% examination requirements of Category B-J welds.
rp0682-0lllc-46-155
.--~*****-.!-*--*-**** '-*~--:~-** - ___ . , ____ ,___ ,
June 10, 1982
(.. RR-3 Item B7.10 (Pressure Retaining Bolting)
BASIS STATEMENT N~nperipheral CRDM bolting is not accessible for VT-1 examination.
REFERENCE CE Dwg 2966-SE~2554.
REMARKS CRD.H bolting is not generally accessible for VT examination due to the configuration of the CRmfs. The peripheral CRDM bolting is accessible.
All nonperipheral CRDM bolting is not accessible for VT examination.
IMPLEMENTATION & RELIEF REQUESTED Peripheral CRD:H pressure retaining bolting will be VT-1 examined.
However, if the inner CRmf assemblies are disassembled or the bolting removed, visual examination as required by the code shall be performed.
RR-4 Items B9.ll, B9.12 (Pressure Retaining Piping)
BASIS STATEMENT Piping welds adjacent to the reactor vessel are buried in the cement and are inaccessible for OD examinations. The surface examination cannot be performed. The volumetric examination of these welds can be performed from the ID using a mechanized device.
REMARKS
'"'welds subject to this relief request are:
PCS-42-RCL-lH-1, 2 PCS-42-RCL-2H-1, 2 PCS-30-RCL-lA-15, 15LD-1, 15LD-2, 16LU-1, 16LU-2, 16 PCS-30-RCL-lB-13, 13LD-1, 13LD-3, 14LU-1, 14LU-2, *14 PCS-30-RCL-2A-14, 14LD-1, 14LD-2, 15LU-1, 15LU-2, 15 PCS".'30-RCL-2B-14, 14LD-1, 14LD-2, 15LU-1, 15LU-2, 15 IMPLE~1ENTATION & RELIEF REQUEST All welds identified above shall be examined from the ID volumetrlcal-ly. The weld will be 100~ examined (in lieu of the bottom 1/3 required by Section XI, 77578, Figure IWB-2500-8). The. surface exam will not be performed due to inaccessibility.
rp0682-0lllc-46-155
- June 10, 1982 RR-S Items BS.20, BS.40, BS.SO, B9.11, B9.12, B9.31, CS.21, CS.22 (Pressure Retaining Piping - Volumetric Examination)
BASIS STATEMENT ASME B&PV Code,Section XI, 1977 Edition with Addenda through Summer 1978, Paragraph IWA-2232(b) requires the utilization of Appendix III,Section XI for ultrasonic examinations of piping. Appendix III, Paragraph III-llOO(d) permits the utilization of alternative examina-tion techniques and calibration block design in accordance with IWA-2240 (Alternative Examinations). Consumers Power Company elects to utilize hold type reflectors in lieu of notch type reflectors required by Paragraph III-3430 for ultrasonic examinations performed on piping thicker than 0.400". In order to effect the change in .reflector type, Consumers Power Company elects, per IWA-2232, to conduct ultrasonic examinatio~s of piping welds in accordance with Article S,Section V, ASME Codes. The requirements of Article 5,Section V will be modified by the attached code applicability statements.
DISCUSSION Utilization of hole type reflectors for material thicker than 0.400" in lieu of notch type reflectors will increase the sensitivity of the examination by a factor of two (2) over the standard 45° angle beam examination.* Consumers Power Company will implement the two code applicability statements attached in order to affect this change in reflectors. The code applicability statements will enhance procedure and calibration control, and control of calibration block procurement/fabrication.
IMPLEMENTATION & RELIEF REQUESTS It is requested that relief be granted from the provisions of IWA-2232 with respect to calibration block design and calibration procedures and that the provisions of the two code applicability statements be substituted in lieu thereof.
RR-6 Items B9.ll, B9.12 (Pressure Retaining Piping)
BASIS STATEMENT Welds PCS-42-RCL-1Hl-2LD, 3LU, 3, 310 and PCS-42-RCL-2Hl-2LD, 3LU, 3, 3LD are located inside the cement reactor shield and are inaccessible for UT.
REMARKS The area between the last known weld (at the elbow entrance to the steam generator) and the reactor shield was visually examined; no welds were apparent in this region. Therefore, it is concluded that the welds are buried inside the reactor shield.
- e June 10, 1982 The application of IWB-2430 at.the Palisades Plant for the above listed welds will be as follows:
The application of IWB-2430 will be in accordance with the information submitted in CP Co letter to D L Ziemann, dated March 6, 1979, Attachment 2, Supplemental Information on Code Update and Code Implementation. It should be noted that the application of IWB-2430 at the Pa'lisades Plant is a two-step process*; ie, the first application of IWB-2430 generally adds the same number of welds (same Section XI item number) on the component/line of int.erest as was originally scheduled.
The second application of IWB-2430 (required by the detection of a defect in the examinations added pursuant to finding the original defect) results in the remainder of the line/component (with the same Section XI item number) being examined.
CP Co will.implement IWB-2430 on these inaccessible welds only after the first set of additional examinations has revealed defects.
IMPLEMENTATION & RELIEF REQUESTED The welds identified above shall be visually inspected by observing the general area after a four-hour hold at the pressure test requirements stated in Section VI, IWA/IWB-5000. This exemption does not apply in the event that Paragraph IWB-2430 of Section XI is applicable.
RR-7 Item C5.11 (Pressure Retaining Piping)
BASIS STATEMENT Welds encased in steel plate missile shield; welds inaccessible for NDT examination.
REMARKS Basis statement applicable to the following welds:
ESS-24-SIS.-SHl-201, 202, 203, 204 ESS-24-SIS-SH2-201, 202, 203, 204 The application of IWC-2430 at the Palisades Plant for the above-listed welds will be as follows:
The application of IWC-2430 will be in accordance with the information submitted in CP Co letter to D L Ziemann, dated March 6, 1979, Attachment 2, Supplemental Information on Code Update and Code Implementation. It should be noted that the application of IWC-2430 at the Palisades Plant is a two-step process; ie, the first application of IWC-2430 generally adds the same number of welds (same Section XI item number) on the component/line of interest as was originally scheduled.
The second application of IWC-2430 (required by_ the detection of a defect in the examinations added pursuant to finding the original rp0682-0lllc-46-155
('"***
defec.t) results in the remainder of the line/component (with the same Section XI item number) being examined.
CP Co will implement IWC-2430 on these inaccessible welds only after the first set of additional examinations has revealed defects.
IMPLEMENTATION & RELIEF REQUESTED All welds identified shall be examined visually for evidence of leakage by observing the general area after the four-hour -hold at the pressure test requirements as stated in IWC-5000. This exemption does not apply in the event that Paragraph IWC-2430 of Section XI is applicable.
RR-8 Item B12.10 (Pump Casing Welds)
BASIS STATEMENT The Palisades Plant has four (4) reactor coolant pumps which are welded to the 30-inch recirculation loop. These pumps function during normal reactor operation to provide forced recirculation through the core.
The ASME Code,Section XI, 77S78 Addenda requires that the casing welds on one pump be volumetrically examined and dye penetrant examined each inspection interval. The inspection of these pumps is considered to be impractical based on the following rationale:
- 1. Approximately 1,000 man-hours and over 100 manrem would be required to perform the examination. The man-hour *estimate is based only on onsite outage work performed by maintenance, operations and NDT personnel. The estimate does not include engineering time or pre-outage job planning. The manrem estimate is* based on an expected dose rate of 30-40 Rem/hr. Additionally, man-hours will be ex-pended by Radiation Protection personnel providing direct coverage ..
The time required to perform the inspection would be at least two weeks of critical path time. All work-would have to be performed under full face mask or "supplied air" conditions.
- 2. The pump casing is fabricated from cast stainless steel (ASTII A351, Grade ~FSM). The material is essentially a cast Type 316 stainless steel. This material is widely used in the nuclear industry and no industry failures of this type material have been. noted. The presence of delta ferrite (typically 15% or more) impacts increased resistance to intergranular stress corrosion cracking (IGSCC). The delta ferrite also improves re~ista?ce to pitting corrosion.
- 3. The coarse grain structure inherent in large.thick casting pre-cludes the use of Ultrasonic Testing (UT).
- 4. The design configuration of the pump corresponds to a Type E pump illustrated in Figure NB-3442.5-1 (1977 Edition, AS~IE B&PV Code,Section III). The presence of the diffuser vanes precludes Radio-graphic Testing (RT). The vanes prevent placement of th~ RT film rp0682-0lllc-46-155
. . .e J'une 10, 1982 cassettes inside the pump (as also does the radiation field in terms of film exposure and personnel radiation exposure) . . Place-ment of the film on the outside of the pump is feasible but there is no radiographic source suitable for placement inside the pump.
Standard radiation sources, eg, Co-60 are too weak to penetrate the thick casting and the background radiation from the inside surface of the pump would serve to uniformly fog the film (ie, a bad signal to noise ratio).
It is further requested that no dye penetrant examination be required during,plant iife due to as-cast surface texture of the pump.
RR-9 Item B12.20 (Pump Casing)
BASIS STATEMENT The same basis applies to this relief request as applied to RR-8 above.
REf'IARKS This request for relief appiies to the following pumps:
P-SOA P-SOB P-SOC P-SOD ItIPLEMENTATION AND RELIEF REQUESTS It is requested that relief be granted to not examine the pump casing due to the radiation exposure, the coarse su~face texture which precludes meaningful examination and since the pump is not expected to be disassembled for other reasons (see RR-8). The pump interior _will be inspected to the extent practical (in recognition ~f the vanes therein) should the pump be disassembled*for any other reason. As an alternate test, it is proposed that the pump be hydrostatically tested per Section XI (see RR-8).
rp0682-0lllc-46-155
.e June 10, 1982 ADDENDA TO RELIEF REQUESTS BASIS STATEMEt-.TTS CONCERNING CP CO CODE APPLICABILITY STATE~IENTS r..**
(
rp06S2-0llle-46-155_
- i June 10, 1982
( CODE USE FOR THIRD PERIOD FIRST INSERVICE INSPECTION INTERVAL Consumers Power Company Code Applicability Statement No 1
Subject:
Piping Examination I. The basic requirements for Ultrasonic Examination of piping shall be in accordance with the following:
Type of Material Nominal Thickness Applicable Code Austenitic and Fer- Greater than .4" to 6 11 Article 5 of ASME Section V ritic piping and with addenda through dissimilar metal Summer 1978 welds Austenitic and .1" to .4" Appendix III with Supple-Ferritic piping and ment 7 of ASHE Section XI dissimilar metal with addenda through welds Summer 1978 II. The following modifications of the requirements of Article 5 Section V,
( and Appendix III,Section XI, 77S78 addenda are applicable.
A. The following code cases shall be utilized:
- l. Code Case N-211, Recalibration of Ultrasonic Equipment upon Change of Personnel
- 2. Code Case N-234, Time Between Ultrasonic Calibration ChecksSection XI, Division 1
- 3. Code Case N-235, Ultrasonic Calibration Checks per Section V,Section XI, Division 1 B. For examinations conducted in accordance with Article 5 of ASME Section V, the basic calibration block for production material
. thickness 1.0" or less shall be as follows: The basic calibration block shall have the same nominal thickness as the production material or no more than 25~~ less than the nominal production material thickness or closer in thickDess to the production material than the 3/4-inch alternate thickness allowed by Article 5. This modification will assure a more accurate calibration than the basic calibration block design allowed by*the code.
C. Subparagraph T-535.l(d) (1) and (2) of Article 5 requires that trans-fer (attenuation compensation) be accomplished between the production material and the basic calibration block and a correction made for
( *~ .
the difference. In accordance with Code Interpretation V-78-01 and rp0682-0llle-46-l55
-.i'.,
~.....
- e. June 10 J 1982
( Code Case 1698 (N-92), the transfer method will not be used. Attenu-ation measurements will be recorded and considered during analysis and evaluation of indications; however, no attempt will be made by the examiner to compensate for any obs~rved difference before or during the Ultrasonic Examination.
D. For examination conducted on welds, the following requirements from Appendix III,Section XI 77S78 shall be used in lieu of Para-graph T-530,Section V, 77S78.
III-2300 Written Procedure Requirements III-2400 General Exmination Requirements III-3100 Instrument Calibration (To Include Supplement 5 and 6)
III-3210 System Calibration - General Requirements III-3300 Calibration Confirmation III-3500 Calibration Data Record III-4000 Examination E. Data shall be recorded as per IWA-2232 (b).
l
\
( ...
rp0682-0llle-46-155
l
- *June 10, 1982 CODE USE FOR THIRD PERIOD
(
FIRST INSERVICE INSPECTION INTERVAL Consumers Power Company Code Applicability Statement No 2
Subject:
UT Piping Calibration Blocks I. All new piping ultrasonic calibration blocks will be procured, designed and fabricated as follows:
A. Material Basic calibration block material shall conform to the requirements of Paragraph, III-3411,Section XI.
B. Radius of Curvature Basic.calibration blocks shall conform to the radius of curvature required by Paragraph III-3410,Section XI.
C. Thickness Basic calibration blocks shall conform to the requirements of Para-graph III-3410.
(
D. Calibration Reflectors
- 1. Thickness: .10" to .40" Calibration reflectors shall conform to the requirements of Paragraph III-3430,Section XI.
- 2. Thickness: Greater than .4" to 6 11 Calibration reflectors shall be holes and shall conform to the requirements of Paragraph T-533 (a), Article 5,Section V, 77S78 ASME B&PV Code.
(
rp0682-0llle-46-155