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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] |
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- General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 April 14, 1989 Nuclear.Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
REVISED RESPONSE TO INSPECTION REPORT 88020 VIOLATION 1 - EXAMPLES A AND B AND VIOLATION 2 NRC Inspection Reports dated January 18, 1989 transmitted 3 notices of violation for the Palisades Plant. Consumers Power Company submittal, dated February 17, 1989, provided our response to those violations. NRC letter dated March 20, .1989 stated that there were no further questions regarding our response to Violation 1, examples c., d., and e., and Violation 3.
However, the March 20, 1989 letter also stated that a revision to our response to Vioaltion 1, examples a. and b. and Violation 2 would be required and that during telephone conversations on March 10, 1989 and March 14, 1989 with Palisades Plant Staff a commitment was made to make this revised submittal by April 14, 1989.
In addition, the March 20, 1989 letter requested that for items that we committed to making a decision at a future date, we should provide a docketed response within 30 days of the decision date.
The revised responses are attached and the items which -require docketed response within 30 days of their decision dates are identified along with the dates for the docketed response in the additional information section of this submittal. Changes from our February 17, 1989 response are marked by vertical lines in the margin.
Kenneth W Berry Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment OC0489-0002-NL02 8904250342 890414 PDR ADOCK 05000255 A CM5 ENERGY COMPANY Q PDC
ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 REVISED RESPONSE TO INSPECTION REPORT 88020 April 14, 1989
- OC0489-0002-NL02 13 Pages
1 Viola~ion (255/88020~01A-F)
- 1. 10CFRSO Appendix B, Crit1;r_ion V as implemented by Consumers Power Qual.ity Assurance Program Section 5, requires that activities be prescribed by -
procedures or drawings appropriate to the circumstances and accomplished in accordance with those procedures or drawings.
This is a Severity Level IV Violatiori.
Example
- a. A safety evaluation check of Temporary Modification 88-052 for 10CFR50.59 applicability-was not performed as required by Administrative Procedure 3.07, "Safety Evaluation" Revision 1, Attachment 1. (255/88020-0lA)
Reason For Violation
- a. On May 27, 1988 Temporary Modification (TM)88-052 was initiated to jumper the leads from SPI number 16 data logger_ input. This action was initiated as a prelude to corrective maintenance on SPI number 16 which was providing sporadic, erroneous alarms to operators. Init_iation of a TM was deemed to be the most appropriate course of action in that:
- 1. Repairs could not be completed until Plant shutdown.
- 2. Without the TM, Operators would continue to be provided with erroneous alarms. Human factor considerations require erroneous alarms be removed.
- 3. Simply defeating the SPI number 16 data logger input would cause erroneous rod group alarms.
- 4. The SPI system alarm annunciator does not have reflash capability such that operators may not be alerted to a valid alarm-if SPI number 16 already had an erroneous alarm in.
A safety review was completed for TM 88-052 as required. by Administrative Procedure 9.31, "Temporary Modification Control". In completing the safety review, individuals involved reviewed appropriate FSAR sections and Technical Specifications (TS) and concluded that no change to the facility was involved. This conclusion was based on the guidance provided in Administrative Procedure 3.07 regarding maintenance activities and the _
determination that the system description provided in the FSAR was that of a completely operable SPI system. Therefore, the SPI system description provided in the FSAR, like that for other components described in the FSAR, is not accurate when structures, systems or components are inoperable.
Administrative Procedure 3.07 Revision 2 provides guidance in the determination of need for and proper completion of the safety evaluation, a IEIR 88020-01
2
- process to ensure compliance with 10CFR50.59. Step 5.2.6.b provides guidance for determining whether a proposed activity represents a change to the facility as described in the FSAR. This step identifies that most oaintenance activities (including: *calibration, refurbishment, replacement with identical components, etc) do not require review under 10CFR50.59 as systems of components removed from service.for maintenance activities are covered by Plant TS for allowable outage times, permissible mode conditions and permitted redundancy reduction.
Based on conversations between Consumers Power and the NRC on March 10, 1989 and upon further review of TM 88-052 and the FSAR have res.ulted in Consumers Power concluding that while initiation of the TM was a prelude to
. future corrective maintenance, the* action of jumpering the leads from SPI number 17 to SPI number 16 data logger input did constitute a modification to the facility. as described in FSAR Section 7. 6 .1. 3. The FSAR states that the "Secondary Position Indication (SPI) data processor utilizes the output of a voltage divider network controlled by a series of reed switches. The reed switches are actuated by a magnet which is connected to the moving control rod. Position information is supplied to. a typewriter for printout.
The SPI provides alarms to alert the operator to abnormal control rod control patterns." In that SPI number 16 was no longer prov::i.ding position indication for control rod number 16, the TM was indeed a change to the facility and was not within the framework of maintenance as SPI number 16 .
could not simply be taken out-of-service. *As presented above, simply defeating SPI number 16's data logger input would have resulted in erroneous rod group alarms. Therefore, the failure to identify the actions completed under TM 88-052 as a change to the facility, as described in the FSAR, was due to misinterpreting the modification as a maintenance activity.
Corrective Actions Taken and Results Achieved Consumers Power has reviewed this specific example and the nature of TMs and maintenance activities and concluded that for an activity to be considered maintenance, the activity must not involve initial action beyond removing the affected equipment from service. While jumpering SPI number 17 output to SPI number 16 data logger input was indeed a prelude to maintenance, this required a change to its normal operational configuration and constituted a modification.
Corrective Action To Be Taken To Avoid Further Non-Compliance In Consumers Power's original response dated February 17, 1989, a commitment was made to revise Administrative procedure requirements to require a written Safety Analysis be performed for all TMs. Upon further review, Consumers Power does not believe this conservative action to be entirely appropriate regarding the screening process utilized and defined by Administrative Procedure 3.07. By requiring the written safety analysis for each TM, the intent of the. screening process would be precluded and a special circumstance would be created for TMs.
Consumers Power originally implemented the use of the Administrative Procedure 3.07 screening process (defined by 10CFR50.59(a)(i)) to minimize IEIR 88020-01
3 the completion of written safety analyses when not required. While we encourage the completion of a written analysis in accordance with 10CFR50.59(a) (2) and 10CFR50.59(b) (1), we believe the completion of unnec~~sary analyses will not e~hance the overall safety evaluation process or those completed specifically for TMs. When the screening process identifies a written safety analysis to be required, the preparer is aware of its significance.
- rn recognizing that a change is inherent to the word modification, Administrative Procedure 3.07 will be revised to provide specific guidance relative to TMs. This guidance will include a discussion relative to the inherent change being made to the facility if a TM is being performed and how it is expected.that completion of the screening process will identify the need for a written safety analysis. Additional guidance will also be provided regarding the need to consider potential impact on structures; systems and components (SSCs) which may be indirectly .affected by the TM, while the specific TM may not represent a change to the facility described in the FSAR, the effect of the TM may alter other SSCs described in the FSAR and therefore require a written safety analysis.
A training memo will be issued to aid in ensuring Plant staff will be knowledgeable of this philosophy.
Date When Full Compliance Will Be Achieved Administrative Procedure 3.07 will be revised by June 12, 1989. The letter to qualified 10CFR50.59 preparers will be issued by April 28, 1989, Example
- b. Various termination points in diesel generator control panel C-22 had three terminal lugs secured by holding nuts that lacked full thread
.engagement and engineering approvals had not been obtained as required by Permanent Maintenance Procedure MSE-E-12, "Cable Terminations" Revision 2 .. This condition existed for an indeterminate length of time. (255/88020-0lB)
Reason For Violation
- b. During observation of maintenance and modification activities associated with diesel generator 1-1 the NRC inspector noted that 10 separate terminals in panel C-22 (diesel generator 1-1) had three wires connnected to one termination point. Investigation by Consumers Power identified five cases where the three wire terminations occurred in C-22 and four in panel C-26 (diesel generator 1-2), all of which are shown on design drawings. Industry practice normally calls for no more than two terminations at any one point. Maintenance Procedure MSE-E-12 identifies that no more than two terminal lugs shall be placed at one.
terminal post unless approved by Engineering. Based on MSE-E-12 and observation of three wire terminations in C-22, the NRC inspector concluded Palisades was in violation of Plant procedure requirements.
IEIR 88020-01
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- Three wire terminations have previously been identified at Palisades and analyzed by engineering personnel as being acceptable for continued use. The majority of three wire terminations existing in the Plant, including those identified by the inspector associated with diesel generator control panel C-22, are from original construction or previous Plant modifications. When three wire terminations are found not to be on design drawings, Engineering or Maintenance personnel evaluate the terminations against established criteria and, if applicable, will update prints to reflect actual configurations *
. Cable termination procedure MSE-E-12 established in May 1983 requires that no more than two termination lugs be at the same point and that deviation from this requirement be approved and documented by analysis.
The intent of MSE-E-12 is to provide requirements for proper termination of all types of wire connections. The procedure also requires specific action when three wire terminations are used. Should a three wire termination exist and be shown on design documentation, it is concluded that analyses were previously performed and the termination approved for use.
cSince all three wire terminations identified within panels C-22 and C-26 are shown on design documentation, Consumers Power concludes that no violation of procedure exists.
Corrective Action Taken And Results Achieved
- b. An investigation into the C-22 panel for three wire terminations was performed and it was identified that these connections are represented on appropriate drawings.
By letter dated March 20, 1989 the NRC requested that Consumers Power evaluate the lack of full thread engagement for the three wire terminations specifically noted within the violation.
Investigation by Consumers Power into the partial thread engagements identified within IE Inspection Report 88020 revealed two specific terminals in panels C-22 and C-26 as having partial engagement. In all cases the nuts identified as being partially engaged were only utilized to secure terminal numbering tags and the nuts securing wire termination lugs were properly engaged by a second nut below the numbering tag. In these specific instances, the extra nut and tag have been removed and all nuts associated with the three wire terminations identified within panels C-22 and C-26 have been verified as being properly secured by nuts having full thread engagement.
The NRC letter of March*20, 1989.further identified that Consumers Power should either include the identification and engineering analyses of three wire terminations for terminal blocks being inspected under the Configuration Control Project (CCP) or ensure that evaluations of identifie~ three wire terminations are conducted* in accordance with procedural requirements.
IEIR 880Z0-01
5
- Based on a telephone conversation between the NRC an:d Consumers Power (referenced in the March 20, 1989 letter), Consumers Power is strength~ni.ng the inspection and documentation of terminals having more than two lugs connected at the terminal. The program which includes verification of full thread engagement will be completed .based on the
- points listed under Corrective Action To Be Take*n To Avoid Further Non-Compliance. It should further be noted that prior to IE Inspection Report 88020, criteria had been established which required a check of wire terminations where there were two or more lugs connected to a terminal.
Corrective Actions To Be Taken To Avoid Further Non-Compliance
- b. 1. Specific acceptance criteriawhich defines acceptable configuration and thread engagement for terminations will be used for inspection of terminations having. more than two lugs *. The accep.tance criteria addresses proper contact of the lugs, lug angle relative to the face of the nut/stud* and proper thread engagement. Configurations not meeting this criteria will be specifically evaluated for acceptability or modified to meet the acceptance criteria. Thi!:!
acceptance criteria has been established based on applicable codes and standards and practices in use at other facilities.
- 2.
- The CCP will identify, log and evaluate terminations with more than two lugs identified during walkdowns which are currently identified within the project scope against the established acceptance criteria. Inspections will include panels previously inspected by CCP and future inspections currently within the CCP scope.
- 3. Maintenance work packages which involve work on or near wire terminations, having the potential to identify these types of termination configurations will contain instructions to identify, assess and appropriately document any terminations where more than two lugs are connected.*
- 4. Maintenance Procedure MSE-E-12 will be revised to show acceptable configurat.fon for terminations having more than two lugs attached.
This revision will not eliminate the need to have prior Engineering approval prior to adding new lugs to terminals.
- 5. A department policy memo has been written which requires future maintenance work p_ackages to contain instruction and acceptance criteria for evaluation of these termination configurations.
- 6.
- Each termination with more than two lugs which is identified through the CCP walkdowns or through normal maintenance activities will be documented. This information will be consolidated into a single list which will provide specific information concerning the configuration and acceptability of terminations which have been previously identified and evaluated.
IEIR 88020-01
l 6
. This program to identify, evaluate and document existing terminations associated with more than two lugs will remain in place until high confidence has been established that most or all terminations of this configuration have been *identified and documented. As a minimum, this program will be maintained in place until the current scope of the CCP has been completed.
Date When Full Compliance Will Be Achieved
- b. 1. This acceptance criteria has been established.
- 2. Walkdowns associated wit4 currently defined CCP scope, which will include review for three wire terminations, are to be completed by March 1991.
- 3. Instructions regarding the identification, assessment and subsequent documentation of terminations containing more than two lugs is being included in applicable work packages.
- 4. Maintenance Procedure MSE-E-12 will be revised by December 1, 1989. -
- 5. Development of a list of identified terminations with more than two lugs will be initiated by ~une 1, 1989.
Description Of Violation (255/88020-04)
- 2. 10CFR Appendix B, Criterion VI, as implemented QY Consumers Power Quality Assurance Program Section 6, requires in part that measures be established to control the issuance of drawings, including changes thereto, and that these measures shall assure that drawings, including changes, are distributed to and used at the-location where the prescribed activity is performed.
Contrary to the above, the licensee failed to establish measures to inform the Document Contr'ol Center (DCC) about changes to drawings caused by modifications to hardware. As a result, the inspectors observed that work on diesel *generator panel C-21 was accomplished in accordance with the incorrect revision of drawing 950W48Ml2, Sheet 96. (255/88020-04)
This is a Severity Level IV violation.
Reason For Violation On August 8, 1988 Plant modification FC-627-2, "Replace Diesel Generator Annunciators and Contactors" was authorized.for implementation. The modification involved the removal of existing local annunciator panels and replacement with new panels which contain reflash capabilities.
Additionally, existing starters in local diesel generator starter panels were being replaced as an electrical equipment upgrade.
IEIR 88020-01
7 A~ part of FC-627-2, work requiring outage conditions was initiated for diesel generator 1-1 panel G-21 *on August 23, 1988.. By September 22, 1988 Drawing Change Requests (DCRs) were initiated for affected schematics and Plan.t Piping and Instrumentation Drawings* (P&IDs), post modification tests were completed and equipment operabilj_ty authorizations granted. As noted in the inspection report, the NRC inspector observed Plant electricians troubleshooting diesel*generator panel G-21 circuitry on September 23, 1988 utilizing. record wiring diagrams not yet revised to reflect the modifications of FC-627-2 completed the day before. Subsequently, a DCR for the affected diagram was completed and transmitted for update on October 19, 1988. Revisions were completed and the affected diagram transmitted to the Palisades Document Control Center (DCC) ort December 12, 1988.
The use of the out of date drawing was the result of Administrative Procedure 9.03, "Facility Change - Minor", not requiring the initiation of revision to affected record wiring diagrams until just *before modificatton package closeout. As indicated in the following Modification Milestone Summary, this stage of Plant modification comes after operability authorization of affected s.tructures, systems and components.* The failure to maintain accurate drawings was compounded by the fact that Administrative Procedures do not require notifications be made of upcoming drawing revisions resulting from physically completed modifications.
Corrective Actions Taken And Results Achieved In response to the difficulties identified by the NRC at the time of the inspection and the realization that an extended period of time (up to 90 days) could expire between operability authorization being granted for a completed modification and modification package closeout (the latest time DCRs for all affected drawings* are to be initiated), Administrative Procedure 9.03 was revised. This revision now requires that a more complete DCR be submitted as part of the "Critical Document Update" stage of the Plant modification which includes; a) full markup of affe~ted record schematics and P&IDs, and b) stamping all Plant DCC filed record drawings (including wiring diagrams) which are affected by the modification to indicate that revisions are in progress per a particular Plant modification. These actions ensure that Plant staff are aware of the status of filed record as-built drawings that may have been affected by Plant modifications.
Administrative Procedure 10.44, "Design Document Control and Distribution",
was also revised to align with the changes made to Administrative Procedure 9.03. Consumers Power believed that stamping of drawings just prior to operability authorization being granted was the appropriate p.oint for such actions as construction and testing activities would be complete.
Therefore, the actual impact on record drawing files would be known with confidence.
.~=J~.-,
In response to Notice of Violation 88020-04, Consumers Power committed to implementing an enhancement to our document control process which would flag documents which could be temporarily incorrect due to modifications IEIR 88020-01
8 being installed. Subsequent to tnis response the NRC questioned the need for Consumers Power to take interim action until the. permanent methodology could be implemented. I In response to this concern, Consumers Powe*r conducted an evaluation of the need for such action and concluded that no,interim actions were required.
I This conclusion is based on the following:*
- 1. Currently, on going modification.activity involves justification, I
approval or conceptual engineering type work. No new facility changes were identified which were found ready for installation. Further, all facility changes installed d-uring the past refueling outage. have been declared operable allowing documents to be updated. Therefore, the risk of a drawing bei.ng out of date due to the installation of a modification before the improved drawing control process is implemented is considered very low.
Subsequent to this review, plans were established for installation of.a modification, deferred from a previous refueling outage, to the upcoming 1989 Maintenance Outage. The project engineer for this.
modification has specifically.been informed, as well as all other Engineering and Maintenance, to work closely with Pianning personnel regarding drawing changes and to provide planners with a copy of the design document. checklist which identifies drawings to be changed.
- 2. Modifications installed during the past refueling outage were considered as possible candidates where documents have yet to be updated. To further assess this aspect, a sampling of site DCC drawings from modifications performed during this outage were reviewed for completion of drawing updating. All drawings reviewed indicated that required updates had been made. This sampling is broadly estimated to be approximately five percent to ten percent of the total drawings affected by facility changes. *
- 3. The Plant has*administrative requirements to immediately stop work should a repairworker or technician identify Plant or component configurations.which do not conform to documents contained in work package instructions. These requirements hav.e been in place for a number of years and are continuously reinforced by management due to their importance *
. 4. To improve awareness by Plant Engineering and Maintenance personnel, an internal memo, initiated by the Engineering and Maintenance Manager, has been sent to all Plant Engineering and Maintenance personnel. This memo discusses the subject of this violation, requests awareness by individuals developing/implementing modifications between now and June, reinforces the requirements in Administrative Procedure 5.01 to stop work if the as-found equipment configuration is not in accordance with work package information and requests supervisors to discuss the memo with persorin.el under their cognizance.
IEIR 88020-01
9 Given this, Consumers Power believes the risk of a problem occurring before implementation of the formally revised control measures are extremely low and therefore, no interim program or control is necessary.
Corrective Actions To Be.Taken To Avoid Further Non-Compliance Although the period of time between the initiation of physical modification activities and stamping of affected record drawings is relatively short (typically two to four weeks), Consumers Power recognizes that a small potential still exists during this time period for troubleshooting activities involving wiring alterations utilizing record drawings not yet reflecting modification status. As a result, the aforementioned procedures will be revised to require the stamping when a modification is authorized for implementation.
Date When Full Compliance Will Be Achieved This change to Administrative Procedures 9.03 and 10.44 will be incorporated by June 1, 1989
10
- Modification Milestone Summary
¥.odification Milestone Commentary Impact On Record Dwg
- Authorization to Implement The design package is "Ap-proved for "Construction" Notice of Modification The *Responsible Engineer (RE) informs Plant staff of upcoming changes and dates for installation & Intended impact is testing. RE also identi- known. Impact is fies aff.ected procedures. subject to potential design change.
System Turnover to Isolation points are set Construction* to confine the modification and its effects.
Installat{on and Testing The modification is now Complete "serviceable" but not yet counted on for performing its s~fety function.
Critical Document Update Documents used to operate modified system are fully revised by markup. (These include record schematics, P&IDs, One-Lines.) All record drawings* affected by the modification* are stamped "Being Revised".
Operability Authorized The modified system is turned back over to Opera- Actual impact is tions for use and to be . known and fixed relied upon for design (not subject to function.* "Operability" change).
- is authorized only after verifying that critical documents are revised to reflect modification.
Documents Updated All project drawings** are sent to drafting via Document Change Request for inclusion of modi-fication into record drawings.
IEIR 88020"""01
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- Modification Milestone Summary Modification Milest~ne Commentary Impact On Record Dwg Package Closeout The modification package submitted for "Complete-ness" review and then filming.
J_
- Record Drawings - Drawings on file in the Plant DCC and General Office Engineering Records Center (ERC) representing Plant as-built condition.
- Project Drawings - Drawings copied from existing record drawings. Project drawings are given project-specific numbers and represent intended as-built until such time that the modification is constructed and tested. Project drawings are then sent to ERC via Drawing Change Request for revision and issue of new associated record drawings
12
- AdditionaJ Information The NRC letter of March.20, 1989 requested that "for items in your response (both initial and supplemental) for which you commit to making a decision at a future date, you will provide a docketed response to this office describing the results of the decision within 30 days of the decision date."
Based on a review of actions contained in Consumers Power's initial response to IE Inspection Report 88020, the following are considered commitments which involve decisions at a future date to which Consumers Power will provide a response within the requested 30 day time frame. The following are the commitments requiring future response with commitment completion and subsequent response due dates identified:
- 1. Commitment (255/88020-06A)
An evaluation will be performed to determine the need for the CCP scope to be updated to include identification and engineering analysis of three wire terminations on all terminal blocks currently being inspected.
RESPONSE
As discussed above in Item 1. b .1 the CCP activities now include identification, evaluation and documentation of terminals having more than two (2) lugs attached. Consumers Power feels this commitment is complete and no further response is necessary.
- 2. Commitment (255/88020-0lF)
A review of the PPAC program will be conducted to establish appropriate requirements to process PPACs which are tied to events, similar to those for PPACs having specific durations.
Dates:
Completion Date: September 1, 1989 Response Due Date: October 1, 1989
- 3. Commitment Evaluate engineering documentation of directions and decisions related to maintenance activities. Ensure direction and basis for the direction or decision are properly documented. Reference IE Inspection Report 88020, Section 3.3.2.2.
Completion Date: June 30, 1989 Response Due Date: . July 30, 1989 IEIR 88020-01
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- 4. Commitment Evaluate the current Quality Assurance inspection program and identify potential changes to audit plans such that inspection activities are focused into performance based concepts. Reference IE Inspection Report 88020, Section 3.5.1.
Dates:
Completion Date: October 1, 1989 Response Due Date: October 31, -1989 IEIR 88020-01