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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments ML20217G4111999-10-12012 October 1999 Informs of Changes to Big Rock Point Defueled Emergency Plan, That Meet Requirements of 10CFR50.54(q) & Can Be Made Without NRC Approval.Changes to Plan Are Listed ML20212L9051999-10-0404 October 1999 Forwards Environ Assessment & Finding of No Significant Impact Re 990511 Application for Amend,As Supplemented on 990603 & 0728.Proposed Amend Would Make Changes to TSs by Deleting Definition,Site Boundary & Use 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 ML20217C5111999-09-30030 September 1999 Forwards Info Re Management & Funding of Irradiated Fuel Notification,Per 10CFR50.54(bb),in Response to NRC Telcon Rai.Revs to Original 990811 Submittal Are Indicated by Redline/Strikeout Method ML20217C2761999-09-30030 September 1999 Forwards Big Rock Point Plant Annual Rept of Facility Changes,Tests & Experiments,Iaw 10CFR50.59(b)(2).Rept Provides Summary of Changes to Facility Performed Since 981001.No Activities Classified as Tests or Experiments ML20212K7561999-09-30030 September 1999 Forwards Insp Rept 50-155/99-05 on 990731-0921,site Insp & 990929 Public Meeting.No Violations Noted 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 ML20211G1011999-08-25025 August 1999 Confirms Discussions & Agreement to Have Mgt Meeting in Region III Office on 990929.Purpose of Meeting to Discuss Decommissioning Activities,Priorities,Challenges & Successes & to Preview Plans & Schedules for Next Year ML20210V0561999-08-17017 August 1999 Advises of Plan to Stop Using Ofc Complex at Plant,Which Consumers Energy Co Had Provided for NRC Resident Inspectors Under 10CFR50.70(b)(1) 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 ML20210S6961999-08-12012 August 1999 Forwards Insp Rept 50-155/99-04 on 990609-0730.No Violations Noted.No Safety Issues or Enforcement Items Were Identified During Insp ML20210S6291999-08-11011 August 1999 Forwards Notification to NRC for Review & Approval of Program Intending to Manage & Provide Funding for Mgt of All Irradiated Fuel at Big Rock Point Until Title of Fuel Is Transferred to Secretary of Energy for Disposal ML20210L0321999-08-0303 August 1999 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety & Documents Listed in App B Being Released in Part (Ref FOIA Exemption 6) 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 ML20210H2701999-07-28028 July 1999 Informs That Big Rock Point Commits to Listed Actions with Regard to 990511 Amend Request to Delete Definition of Site Boundary & Remove Site Map,Based on Discussion with NRC on 990728 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 ML20209D6951999-07-0707 July 1999 Ack Receipt of Which Requested That NRC Reconsider Decision to Move NRC Resident Inspector from Big Rock Point Plant.Determined Decision to Be Correct One ML20210L0491999-06-30030 June 1999 Partially Deleted Request for FOIA Documents Re Source of High Alarms Generated by Radiation Effluent Detector or Detectors in Discharge Canal at Big Rock Point on 980314,15 & 25.Partially Deleted Info 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 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 ML20196E1601999-06-21021 June 1999 Forwards Insp Rept 50-155/99-03 on 990416-0608.No Violations Noted.Overall,Reactor Decommissioning Activities Performed Satisfactorily ML20209D7011999-06-21021 June 1999 Requests That NRC Reconsider Decision to Move Resident Inspector from Big Rock Point NPP 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 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 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 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 ML20195D0371999-06-0303 June 1999 Forwards Revised Defueled Ts,Per 990511 Util Request.Page Format in Attachments 1 & 2 of Submittal Do Not Agree with Current Facility Defueled TS Format.Replacement of Encl Pages Requested ML20207F6631999-06-0303 June 1999 Forwards Rev 33 of Big Rock Point Plant Security Plan,Which Incorporates Exemption from Certain Requirements of 10CFR73 That Reflect Permanent Shutdown & Defueled Condition of Facility.Encl Withheld IAW 10CFR73.21(c) ML20207D1151999-05-27027 May 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Reorganization,Division of Licensing Project Management Created 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 ML20206P4501999-05-11011 May 1999 Requests Transcript of 990413 Public Meeting in Rockville,Md Re Decommissioning of Big Rock ML20206P0921999-05-0707 May 1999 Responds to Discussing Impact That Delays to Wesflex Sys Approval Would Have on Big Rock Point Decommissioning Cost & Schedule ML20206H1011999-05-0404 May 1999 Forwards Safety Evaluation for Exemption from Certain Physical Protection Requirements.Enclosure Contains Safeguards Info & Being Withheld 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments ML20217G4111999-10-12012 October 1999 Informs of Changes to Big Rock Point Defueled Emergency Plan, That Meet Requirements of 10CFR50.54(q) & Can Be Made Without NRC Approval.Changes to Plan Are Listed 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 ML20217C2761999-09-30030 September 1999 Forwards Big Rock Point Plant Annual Rept of Facility Changes,Tests & Experiments,Iaw 10CFR50.59(b)(2).Rept Provides Summary of Changes to Facility Performed Since 981001.No Activities Classified as Tests or Experiments ML20217C5111999-09-30030 September 1999 Forwards Info Re Management & Funding of Irradiated Fuel Notification,Per 10CFR50.54(bb),in Response to NRC Telcon Rai.Revs to Original 990811 Submittal Are Indicated by Redline/Strikeout Method 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 ML20210S6291999-08-11011 August 1999 Forwards Notification to NRC for Review & Approval of Program Intending to Manage & Provide Funding for Mgt of All Irradiated Fuel at Big Rock Point Until Title of Fuel Is Transferred to Secretary of Energy for Disposal ML18066A5971999-07-30030 July 1999 Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A5921999-07-30030 July 1999 Forwards Results of Review by Consumers Energy of Two NRC Draft Repts Entitled, Evaluation of Air-Operated Valves at Light-Water Reactors & Study of Air-Operated Valves in Us Nuclear Power Plants. ML18066A5881999-07-30030 July 1999 Provides Rev to Instrument Channel Drift Measurement Submitted on 990611,in Response to NRC Comments on Util RAI Response for Sections 3.3,3.5 & 3.6 & Editorial Changes Revs Necessary for Consistency within ITS ML20210H2701999-07-28028 July 1999 Informs That Big Rock Point Commits to Listed Actions with Regard to 990511 Amend Request to Delete Definition of Site Boundary & Remove Site Map,Based on Discussion with NRC on 990728 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 ML20210L0491999-06-30030 June 1999 Partially Deleted Request for FOIA Documents Re Source of High Alarms Generated by Radiation Effluent Detector or Detectors in Discharge Canal at Big Rock Point on 980314,15 & 25.Partially Deleted Info Encl 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 ML20209D7011999-06-21021 June 1999 Requests That NRC Reconsider Decision to Move Resident Inspector from Big Rock Point NPP 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 ML20195D0371999-06-0303 June 1999 Forwards Revised Defueled Ts,Per 990511 Util Request.Page Format in Attachments 1 & 2 of Submittal Do Not Agree with Current Facility Defueled TS Format.Replacement of Encl Pages Requested ML20207F6631999-06-0303 June 1999 Forwards Rev 33 of Big Rock Point Plant Security Plan,Which Incorporates Exemption from Certain Requirements of 10CFR73 That Reflect Permanent Shutdown & Defueled Condition of Facility.Encl Withheld IAW 10CFR73.21(c) 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 ML20206P4501999-05-11011 May 1999 Requests Transcript of 990413 Public Meeting in Rockville,Md Re Decommissioning of Big Rock 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 ML20206E7821999-04-29029 April 1999 Forwards Annual Radioactive Environ Rept for 1998 for Big Rock Point Plant. Rept Includes Summaries,Interpretations & Statistical Evaluation of Results of Radiological Environ Monitoring Program ML20206E8271999-04-28028 April 1999 Forwards Palisades Plant Annual Radiological Environ Operating Rept for 1998. There Were No Reportable Events During This Period 05000155/LER-1992-008, Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable1999-04-26026 April 1999 Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable ML20207B4661999-04-23023 April 1999 Forwards Copy of Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981201 for Palisades Npp.No Deficiencies Noted.Seven New Arcas Identified ML18066A4531999-04-0707 April 1999 Forwards ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1,as Requested by NRC 990406 Telcon,Per TS Change Request Submitted 980126.Change Submitted Does Not Alter Conclusions of No Signficant Hazards Considerations ML18066A4481999-04-0202 April 1999 Responds to Violations Noted in Insp Rept 50-255/98-06. Corrective Actions:Nuclear Performance Assessment Dept Has Reviewed Observations & Agrees That Field Observations by Qualified Personnel Are Important Aspect of Program ML18066A4411999-03-30030 March 1999 Forwards Response to NRC 990126 RAI Re TS Section 3.7 of Util 980126 LAR Request for Conversion to Its.Licensee Received Permission to Delay TS Section 3.6 Response to Allow for Addl Time for Preparation & Internal Review ML18066A4471999-03-30030 March 1999 Confirms Completion of Util Review of Design Engineering Contractor Cable Ampacity Evaluation.Evaluation Available at Plant for NRC Review ML20196K7881999-03-29029 March 1999 Forwards Rept on Certification of Financial Assurance for Decommissioning for Big Rock Plant,Per 10CFR50.75(f)(1).Copy of Trust Agreement Between Consumers Energy & State Bank & Trust Co,Included in Rept 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 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L0161990-09-18018 September 1990 Forwards Corrected Monthly Operating Rept for Aug 1990 for Big Rock Point Plant,Consisting of Corrections to Grey Book ML18057A4811990-09-17017 September 1990 Confirms 900718 Telcon Notification Re Westinghouse Agreement to Join Utils as Equity Investor in Plant ML20059K2381990-09-0707 September 1990 Forwards Info in Response to Request for fitness-for-duty Policy & Procedures,Per NRC 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)) ML20059F5031990-09-0505 September 1990 Forwards Description of Scope & Objectives for 1990 Emergency Exercise Scheduled for 901204.Region III Will Participate IR 05000255/19900101990-09-0404 September 1990 Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated ML18057A4521990-09-0404 September 1990 Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated ML18057A4381990-08-31031 August 1990 Forwards Info Re Contamination of South Radwaste Area,Per 10CFR20.302,in Response to NRC 900112 Request.Approval Requested to Dispose of Low Level Radwaste in Place ML18057A4371990-08-31031 August 1990 Forwards Analysis Concluding That Plant Reactor Beltline Matl Upper Shelf Energy Will Remain Greater than 50ft-lbs Until Yr 2032,per 900716 Commitment ML20059E0001990-08-29029 August 1990 Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990 ML18057A4201990-08-24024 August 1990 Forwards Revised Application for Amend to License DPR-20, Changing Tech Specs Re Incore Analysis Program.Request Revised Per NRC Comments During 900709 Meeting ML20059B6221990-08-22022 August 1990 Forwards Missing Pages 25 & 26 Omitted from Facility Decommissioning Funding Rept,Consisting of Attachment a to Exhibit E ML20059B6321990-08-22022 August 1990 Forwards Revised Engineering Analysis of Generic Ltr 88-01 on Plant Temp Pressure Limits in Support of Licensee 900110 Tech Spec Change Request,Per NRC Request ML20059B6371990-08-22022 August 1990 Forwards Correction to 900628 Response to Generic Ltr 90-04 Re Status of Generic Safety Issues (Gsis).Response Contained Some Errors in That Some Palisades Plant Related Info Inadvertently Substituted Into GSI Table for Big Rock Point 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 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 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 ML18057A4071990-08-21021 August 1990 Forwards Tech Specs Change Request to License DPR-20,to Remove Redundant Requirements & Change Basis Statements No Longer Applicable 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 ML20058L9891990-08-0606 August 1990 Provides Util Comments Re SALP 9 Board Rept.Declining Trend in Radiological Controls Noted in Cover Ltr Needs to Be Reevaluated ML20056A3491990-08-0303 August 1990 Updates Response to NRC Bulletin 90-002, Loss of Thermal Margin Due to Channel Bow 05000155/LER-1990-002, Requests Extension of Due Date for Radiation on-the-job Training to 901101,per 900518 LER-90-002 Describing Violation Involving Unqualified Technician Assigned to Shift Compliment.Delay Due to Forced Outage1990-08-0101 August 1990 Requests Extension of Due Date for Radiation on-the-job Training to 901101,per 900518 LER-90-002 Describing Violation Involving Unqualified Technician Assigned to Shift Compliment.Delay Due to Forced Outage ML20055J3841990-07-26026 July 1990 Forwards Certification of Financial Assurances for Decommissioning ML20055J1421990-07-26026 July 1990 Responds to Commitment Oversight Issue Resulting from Insp Rept 50-255/90-08.Commitment Mgt Seminar Training Will Be Complete Prior to 901001 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)) ML20055E0211990-06-29029 June 1990 Requests NRC Approval of Encl Simulation Facility Application for Plant,Per 10CFR55.45(b) 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 ML18057A2591990-06-11011 June 1990 Forwards Palisades Simulator Certification Submittal. 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 ML18057A2711990-06-11011 June 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.1.1i in Order to Maintain Plant in Hot Shutdown While Repair Made to Pressurizer Heater Power Supply.Request Based on 900608 Failure of Heater Transformer 15 ML18057A2631990-06-10010 June 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.1.1i to Enable Plant to Be Maintained in Hot Shutdown While Repair Made to Pressurizer Heater Power Supply.Waiver Requested for 900611-18 ML18057A2571990-06-0808 June 1990 Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-255/90-12.Corrective Actions:Continuing Training Program Will Be Developed for Supervisors That Will Discuss Fire Protection Program Implementation Topics 1990-09-07
[Table view] |
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consumers Power Kenneth W Berry Dirtctor POWERIN& Nuclear licensing MICHl&AN'S PRO&RESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 o (517) 788-1636 October 19, 1989 Nuclear Regulatory Connnission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -
DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
TOPICAL REPORT CPC-2A (REVISIONS 9 AND 10) QUALITY ASSURANCE PROGRAM DESCRIPTION FOR OPERATIONAL NUCLEAR POWER PLANTS Attached are Revisions 9 and 10 of Consumers Power Company Topical Report CPC-2A, Quality Assurance Program Description for Operational Nuclear Power Plants. Revision 9, dated April 1, 1989, and Revision 10, dated October 1, 1989, are Consumers Power Company's annual report being submitted in accordance with 10CFR50.54(A)(3). Also enclosed as Attachments 1 throu~h 4 are lists of affected pages in Revisions 9 and 10 and change matrices comparing Revision 9 with Revision 8 and Revision 10 with Revision 9.
The matrices present the changes made, the reasons for the changes, and the basis for concluding they do not constitute a reduction in our QA Pro~ram commitments. Some of the changes had previously been submitted for, and received, NRC approval. These are clearly indicated in the matrix.
Kenneth W Berry Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspectors - Big Rock Point & Palisades Attachments OC1089-0209-NL04 cr- ~ 10~1--o121--
r- \...._1: ~ .* ~: ; :**~~: *' (.._,.,".
ATTACHMENTS Consumers Power Company Big Rock Point & Palisades Plants Dockets 50-155 & 50-255
- 1. Attachment 1 ~~List of pages changed in Rev 9
- 2. Attachment 2 - Matrix drawing changes made from Rev 8 to Rev 9
- 3. Attachment 3 - List of pages changed in Revision 10
- 4. Attachment 4 - Matrix showing changes made from Rev 9 to Rev 10
- 5. Information copies of CPC-2A, Rev 9
- 6. Information copies of CPC-2A, Rev 10 October 19, 1989 193 Pages OC1089-0209-NL04
- -*---*---*~---- ____- : - : : - :,.~
ATTACHMENT 1 List of CPC-2A pages changed in Revision 9 Statement of Responsibility and Authority Approval Page 2
3 4
5 6
8 9
10 14 15 23
ATTACHMENT 2 QUALITY ASSURANCE PROGRAM DESCRIPTION (CPC-2A)
Basis for Conclusion Revision 9 Reason for Change Revision 8 1 , I
,1.
CllVt!f Ltitl('I' Covr.r 1.ett11r 2nd Paragraph 5.nd llaragrnEh This change recognizes that the The organization described I have delegated the authority I have delegated the authority in the QAPD continues to for the establishment and main- VP-NO is part of the management for the establishment and main- chain with the responsibility meet Criterion I of 10CFR50 tenance of the Quality Assurance tenance of the Quality Assurance Appendix B, in that no Program Description through the and authority for the QA Program.
Program Description to the This has always been the case, changes to the previously Senior Vice President, Energy Senior Vice President, Energy approved organization Supply to the Vice President, but the cover letter did not Supply for operational phase show it. structure have been made.
activities and plant modifi- Nuclear Operations for opera-cations, and in turn to the tional phase activities and plant Director, Quality Assurance. modifications, and in turn to the The Director, Quality Assurance Director, Quality Assurance. The is also authorized to verify Director, Quality Assurance is the effective implementation also authorized to verify the of the Quality Assurance effective implementation of the Program Description. Quality Assurance Program Des-cription.
2 Page 21 Page 2, 1.2.2.a, 5th and 6th Paragraph 1.2.2.a, 5th Paragraph This change recognizes that the Changes related to QA for pro-.
At Big Rock Point, procurement Control of plant initiated pro- curement were reviewed by NRC curement, including preparation, organizational restructuring planning for the plant includ- for procurement that was as part of its review of Revi-ing preparati.on of and obtain- reviews and approval of purchase sion 8. Subject to the clari-requests for spares, replacement recognized in Revision 8 for ing the required reviews and Palisades has now been im- fications indicated in its approval of purchase requests items, consumables, and materi- letter dated August 2 1 1989, als, items and services. Con- plemented at Big Rock Point for spares, replacement items Plant, as well. NRC has determined that the and consumables; and materials, trol also includes submittal of CP Co QAPD continues to meet items and services for minor purchase requests to Purchasing, 10CFR50 1 Appendix B.
modifications; and submittal vendor surveys for urgent pro-of purchase request packages curements, planning and execu-tion of source surve 11 lance or to Purchasing for procurement inspection, receiving inspection, actions. and review of supplier quality-At Palisades, control of pro- related documentation.
curement for plant, including preparation, reviews and approval of purchase requests for spares, replacements items, consumables, and materials, items and services for minor modifications. Control also includes submittal of purchase requests to Purchasing, vendor surveys for urgent procurements, planning and execution of source surveillance or inspection, re-*
ceiving inspection, and review of supplier quality-related documentation.
MI0989-0125A-QA01
ATTACHMENT 2 . '
QUALITY ASSURANCE PROGRAM DESCRIPTION (CPC-2A)
Revision 8 Revision 9 Reason for Change Basis for Conclusion fa9e 2
, , 2.11 1 6th P1m11r11ph Not addressed. Functioning as the Company de- This change completes an INPO The QAPD, as revised, con-sign and configuration control commitment to clearly identify tinues to meet Criterion I of authority for compliance of each plant as having design Appendix B, in that the plant modifications and design and configuration control authorities and duties of per-changes to existing plan.t
- authority. sons and organizations per- .
design criteria. forming activities affecting the safety-related functions of structures, systems and components are clearly estal>-
blished and delineated in 4 writing.
Page 2, 1.2.2.a, 7th Paragraph Page 2, 1.2.2.a, 7th Paragraph Project responsibility for minor Project responsibility for modi- In conjunction with item (3), See Item 3.
modifications including design, fications, including design, and other changes herein, this procurement, construction and procurements, construction and change recogn.izes the plants as testing activities, whether testing activities as assigned having ultimate control of modi-performed by CP Co or by out- by the Plant General Manager/ fications, and also removes the side contractors. Manager. distinction between "major" and "minor."
5 Page 3 Page 2 1.2.2.a, 9th Paragraph 1.2.2.a, 9th Paragraph Development and maintenance of Developing and maintaining Plant This change is p1Jrely editorial, See Item 3.
Plant Security Plans and Security Plans and administering at the request of the involved contract administration for the contract(s) for the security management, to make the wording the security force, force. parallel that of the remainder of the Section.
6 Page 3, Page 3 Paragraph 1.7 1.2.2.1, 17th Paragraph Not in this revision. Developing and maintaining The responsibility for this See Item 3.
Plant l"ire Protection Plans. function was shifted from the Facilities and Automotive Department, as formerly indi-cated in Section 1.2.4.a, to each plant. See item 14.
MI0989-0125A-QA01
. . --.:....... ~.*..~ ... i., . .*. *-*~
ATTACHMENT 2 QUALITY ASSURANCE PROGRAM DESCRIPTION (CPC-2A)
Revision 8 Revision 9 Reason for Change Basis for Conclusion 7
~ ~
~b, 1st Paragraph ~b, 1st and 2nd Paragraphs Performance of the offsite Performance of the offsite This change clarifies the re- See Item 3.
r 1*
safety review functions for safety review functions for sponsibilities of the NSSD with v.j. ~
the nuclear power plants as the nuclear power plants as re*spect to PRA and its uses in described in plant technical described in plant technical severe accident management and specifications, and probabi- specifications. plant reliability improvement.
listic *risk assessment.
Development and maintenance of nuclear plant probabilistic risk assessment models and application of PRA technology to severe accident management and plant reliability improve-ment.
8 Page 4
!.:1.:2 The Vice President, Energy The Vice President, Energy This change, in conjunction with See Item 3.
Supply Services (see Figure 6) Supply Services (see Figure 6) item (3) and others herein, is responsible to the Senior is responsible to the Senior recognizes the plants as "design Vice President, Energy Supply Vice President, Energy Supply authority," and clarifies that for certain services, includ-* for certain services, including ESS will perform such work as ing standards for calibration standards for calibration of authorized and requested by of M&TE, operating the per- M&TE, operating the personnel Nuclear Operations.
sonnel dosimetry laboratory dosimetry laboratory and per-and major modifications to forming assigned modifications CP Co nuclear power plants. to CP Co nuclear power plants.
Directors and Managers re- Directors and Managers report-porting to him are responsible. ing to him are responsible for for directing the performance .directing the performance of of activities in accordance ' activities in accordance with with QA Program requirements. QA Program requirements.
9 Page/ ~
- b, 1st Paragraph ~b, 1st Paragraph Performing the construction, Performing the construction, See Item 8. See Item 3.
preoperational testing and preoperational testing and overall project management overall project management of of generating plant major assigned generating plant modi-modification projects. fication projects.
MI0989-0125A-QA01
' ... -~.-: ....._.l.* . . . . . . . . . . . . . . - .
ATTACHMENT 2 QUALITY ASSURANCE PROGRAM DESCRIPTION (CPC-2A)
Basis for Conclusion Reason for Change Revision 8 Revision 9 10 Page 6 Page 5 1.2.3.c 1.2.3.c See Item 3.
The Manager, Field Maintenance See Item 8.
The Manager, Field Maintenance Services provides Field Main-Services provides Field Main- tenance Services for assigned tenance Services for major modifications and plant outages.
modifications and plant outages.
11 Page 6 Page 6 1.2.3.d, 1st Paragraph 1.2.3.d., 1st Paragraph See Item 8. Since each plant See Item 3.
Performing the engineering of Performing the engineering is designated as "design generating plant modification associated with genera.ting
- authority," it will determine plant modification projects which organization, if not projects. This includes as assigned by the Plant functioning, as appropriate, itself, may handle lead design as either the lead design General Manager/Manager. or design reviewer functions.
organization when such projects In all cases, the plant will are engineered in-house or as retain its "design authority."
the Company's design reviewer when those projects are done by outside engineering organizations.
12 Page 6 Page 6 1.2.3.e, 1st Paragraph 1.2.3.e, 1st Paragraph This change is.editorial, at the See Item 3.
Maintaining the Records Manage- Maintaining the Records Manage-ment System including required request of the involved manage-ment System including required retention, protection and re- ment, to provide a more clearly retention, protection and re- worded treatment of responsibili-trievability, operating the trievability, operating the General Office (offsite) ties.
General Office (offsite) Document Control Center and Document Control Center and Engineering Records Center, for ma~ntaining the Uniform and for maintaining the Uniform File Index. This includes collecting, storing, main- File Index. Thfs includes collecting, storing, maintaining, taining, distributing and distributing and controlling controlling plant engineering/
design documents through the plant engineering/design Engineering Records Center. documents.
MI0989-0125A-QA01
ATTACHMENT 2 QUALITY ASSURANCE PROGRAM DESCRIPTION (CPC-2A)
Basis for Conclusion Revision 9 Reason for Change Revision 8 Page 6 Page 6 '
1.2.4 1.2.4 j.
See Item 8. See Item 3.
Certain functions that consti- }
Certaf.n functions that consti-
~
tute part of the Nuclear Opera- tute part of the Nuclear Opera-tions QA Program are performed _tions QA Program are performed :*
by CP Co organizational units by CP Co organizational units outside the Nuclear Operations outside the Nuclear Operations Department or Energy Supply Department or Energy Supply Services, as follows: Services. Engineering and de-.
sign tasks executed in support of plant .activities are subject to review and acceptance by the associated plant organization responsible for that activity (as the-design authority).
14 Page 6
- 1. 2.4.a lbe responslbllty for develop- See Item 3.
The Manager, Facilities and Not in this revision.
ment and maintenance of fire Automotive (see Figure 5) is protection plans was transferred responsible through the Vice. to each plant. Since Facilities President, Corporate Services and Automotive had no other
- to the President and c.o.o. for identified functions, it ls developing and maintaining the deleted from CPC-2A.
Fire Protection Plans for the nuclear power plants.
15 Page 6 Page 6 1.2.4.b 1.2.4.a See Item 3.
The Manager, Administrative The Director, Administrative Title change only.
Opera~ions and Planning (see Operations and Planning (see Figure 5) is responsible Figure 5) is responsible through through the Vice President, the Vice President, Corporate Corporate Services to the Services to the President and President and C.O.O. for Chief Operating Officer for microfilming of specified microfilming of specified QA QA records and plant engi- records and plant engineering/
neering/design documents. design documents.
HI0989-0125A-QA01
ATTACHMENT 2 : .
QUALITY ASSURANCE PROGRAM DESCRIPTION (CPC-2A) .
.i
'*~*
Revision 8 Revision 9 Reason for Change Basis for Conclusion 16 ,.
~
r.2-:-51 9th Paragraph Not in this revisf.on. QA engineering associated with This change recognizes that the See Item 3.
modification design, procurement, functions identified could be construction and testing, in- performed by either (or both) cluding verification that plant or General Office QA staff.
quality-related test prerequi- Thus, the description is elevated*
sites have been accomplished, to be listed under the Director, identification and participa- QA, instead of twice under both tion in resolution of installa- plant and GO QA.
tion inspection and test problems and nonconformances, and maintenance and reporting of status of hardware and test quality and corrective action.
(This function will* be carried out by plant and/or general office QA staff, as assigned by the Director, QA.)
17 Page 9 Page 9 1.2.5.a, 5th Paragraph 1.2.5.a At Big Rock Point, review of Not in this revision. See Item 2. See Item 2.
and concurrence with quality requirements of procurement request packages for plant site-originated procurements.
18 Page 9 Page 9 1.2.5.a, 9th Paragraph 1.2.5.a, 6th Paragraph Plant site quality control Plant site quality control See Item 2. See Item 2.
inspe~tion program, including inspection program, including receiving inspection (at Big inspection of maintenance, Rock) and inspection of main- modifications, testing and tenance, modifications, fuel handling.
testing and fuel handling.
MI0989-0125A-QA01
ATTACHMENT 2 i;~**
~-'
QUALITY ASSURANCE PROGRAM DESCRIPTION (CPC-2A) f.,'*.
Revision 8 Revision 9 Reason for Change Basis for Conclusion 19 r11gt1 io ~
1.2.~.li r.r.-J."b i
Quality Assurance Support Quality Assurance Section Heads The listing for modification See Item 3.
Section Heads (Corporate Office) (Corporate Office) are responsi- design and* procurement was are responsible to the Director, ble to the Director, Quality elevated to the listing under Quality Assurance for the Assurance for the Nuclear the Director, QA. See Item 16.
Nuclear Operations QA Audit Operations QA audit program, Other changes are editorial Program, QA Program Dev.elop- QA program development, and only.
ment, Corporate Office QA special studies including the Engineering for modifications following:
Design and Procurement and Special Studies including the following:
20 Page 10 Page 10 1.2.5.b, 13th Paragraph 1.2.5.b Corporate Office QA Engineering Not in this revision. This item was elevated to be See Item 3.
associated with modification listed under the Director, QA, design a~d procurement, including as the function could be per-preparation of necessary quality formed by either plant or assurance plans for integration General Office QA, or both, as with project plans, performance directed. Some supplier veri-of source surveillance/inspection fications may also be performed at supplier facilities, review of by the plant staff per item (2).
supplier quality-related docu-mentation and maintenance and reporting of status of hardware and test quality and corrective action (offsite),
21 Page 14 Page 14 ',I I.
Figure 4 Figure 4 Title Box: Title Box: This change recognizes the dele- See Item 3.
tion of "support" as part of the "QA Support "General Office QA Department Title for QA. This Section Heads" Section Heads" is editorial; the reporting relationships previously existing were not affected.
MI0989-0125A-QA01
ATTACHMENT 2 QUALITY ASSURANCE PROGRAM DESCRIPTION (CPC-2A)
Basis for Conclusion Revision 9 Reason for Change Revision 8
\.
Page 15 Page 15 Figure 5 t:.
Figure 5 See Item 3.
One title box for Manager See Item 14 and Item 15.
Eliminated Manager Facilities Facilities and Automotive and Automotive from chart. under Vice President. Also Changed one title to Director Manager Administrative Opera-Administrative Operations tions and Planning.
and Planning.
23 Page 23 Page 23 Bd Bd See Item 3.
Authority and responsibility See Item 8.
Authority and responsibility for modification activities is for modification activities under the cognizance of the under the cognizance of the Nuclear Operations Department Nuclear Operations Department and the Energy Supply Services as described in Section l.O, Departments are described in ORGANIZATION. This authority Section 1.0, ORGANIZATION. and responsibility includes
'Illis authority and responsi- the preparation, review, approv-bility includes the prepara- al and verification of the following design documents:
tion, review, approval and a) System descriptions; b) verification of the following design documents: a) System Design input and criteria; c) Drawings-and specifications; descriptions; b) Design input and d) Engineering analyses and criteria; c) Drawings and and associated computer pro-specifications; and d) Engi-neering analyses and associated grams.
computer programs.
MI0989-0125A-QA01
ATTACHMENT ~
List of CPC-2A pages changed in Revision 10 Approval Page 4
5 9
16 20 53 67 69 70
ATTACHMENT 4 QUALITY ASSURANCE PROGRAM DESCRIPTION (CPC-2A)
Revision 9 Revision 10 Reason for Change Basis for Conclusion ... '..:/
Pase 4 ~ .
- *2* b, Paragraph I+ ~b, Paragraph I+ j.
r' Assessing the effectiveness of the Assessing the effectiveness of the Due to a reorganization, The function ls still Corporate Health Physics program Corporate Health Physics program the Dosimetry Laboratory being performed; it is and maintaining standards for con- and maintaining standards for con- now reports to the Corpor- just the responsibility trol of Radiological Materials and trol of Radiological Materials and ate Health Physicist who of a different department.
personnel exposure and recommending personnel .exposure and recommending is a member of the staff ....
program improvements to reduce on- program improvements to reduce on- of the Nuclear Safety *-:"
si te and of fsite radiation expos- si te and offsite radiation expos- Services Department.
ure caused by plant operations. ure caused by plant operations, operating the Dosimetry Laboratory
- and maintaining records of person- 11 I.
nel radiation exposure.
Page I+
1.2.3.
Page 4 1.2.3
- ,,~J The Vice President, Energy Supply The Vice President, Energy Supply The Dosimetry Laboratory See item above.
Services (see Figure 6) is respon- Services (see Figure 6) is responsi- is now under Nuclear Opera-sible to the Senior Vice President, ble to the Senior Vice President, tions rather than Energy Energy Supply for certain services, Energy Supply for certain services, Supply Services.
including standards for calibra- including standards for calibration tion of M&TE, operating the per- of M&TE, and performing assigned sonnel dosimetry laboratory and modifications to CPCo nuclear power performing assigned modifications plants. Directors and Managers to CPCo nuclear power plants.* reporting to him are responsible for Directors and Managers reporting to directing the performance of activi-him are responsible for directing ties in accordance with QA Program the performance of activities in requirements.
accordance with QA program requirements.
Page I+ Page 4 1.2.3.a 1.2.3.a The Manager, Laboratory and Field The Manager, Energy Supply Technical Title change. Merely a change in the Services (L&FTS) is responsible, Services (ESTS) is responsible, name of the department.
througJt personnel reporting to him, through personnel reporting to him, for: for:
ra~el
~
~a, Paragraphs I+ and 5 Controlling the calibration recall Controlling the calibration recall Title change. Merely a change in the system for Portable and Laboratory system for Portable and Laboratory name of the department.
M&TE owned by L&FTS, and other M&TE owned by ESTS, and other departments, as requested~ departments, as requested.
Maintaining a Master PL-M&TE List Maintaining a Master PL-M&TE List for L&FTS PL-M&TE and for other for ESTS PL-M&TE and for other departments, as requested. departments, as requested.
MI0909-0009A-QA06
ATTACHMENT 4 QUALITY ASSURANCE PROGRAM DESCRIPTION (CPC-2A)
Revision 9 Revision 10 Reason for Change Basis for Conclusion Page 5 Page S I 1.2.3.a, Paragraph 9 1.2.3.a, Paragraph 9 Operating the Dosimetry Laboratory Not in this revision. Resporis~~ility transferred See Item 1.
(including preparation arid main-tenance of occupational radiation and exposure records).
~ ~
~a, Paragraph 5* *-i-~~a, Paragraph 5 Review and concurrence with pro- Review and concurrence with pro- Clarification of QC's role QC's responsibility has curement quality requirements for curement quality requirements for since receipt inspection not changed. This is nuclear fuel, source audit/surveil- nuclear fuel, source audit/surveil- is normally performed by just a clarification.
lance/inspection at fuel supplier lance/inspection at fuel supplier Material Management except facilities, fuel receiving inspec- facilities, fuel inspection upon
tion, and review of fuel supplier delivery, and review of fuel sup-quality-related documentation. plier quality-related documentation.
Page 16 Page 16 Figure 6 Figure 6 Title is Manager, Lab and Field Shows the title change to Manager, Title change. Merely a change in the Technical Services. Energy Supply Technical Services. name of the department.
Page 20 2.2.9.i Not in this revision. The Quality Assurance Department Agreement with NRC con- Prior NRC approval.
provides training in quality assur- tained in August 2, 1989 ance principles related to procure- letter from Chief, Opera-ment for those personnel performing tions Branch, Division of procurement documents, source veri- Reactor Safety, Region III.
fication and receipt inspection.
Page 53 15.2.1.e The Quality Assurance Department verif(es through audit or surveil-lance that, when it is not "the original inspection planning auth-ority, the dispositions of 15.2.1.b Page 53
- 15. 2.1.e The Quality Assurance Department reviews "use as is" or "repair"
-dispositions which result in devi-ation from original design or specification requirements.
Agreemunt tained in letter in letter of I
with NRC con*
August 2, 1989 response to our Hay 19, 1989.
Prior NRC approval per 8/2/89 letter.
- and the alternate acceptance cri-teria of 15.2.1.c are being prop-erly performed and reviewed.
HI0909-0009A-QA06
ATTACHMENT 4 QUALITY ASSURANCE PROGRAM DESCRIPTION (CPC-2A)
,1 Revision 9 Revision 10. Reason for Change Basis for Conclusion Pa15e 67 1fx.ccrlon/Int@rprl!t11tion 2.m Sec .1.15 '*
Not in this revision. Requirement The change allows greater Prior NRC approval per Plant procedures shall be reviewed flexibility in how the 8/2/89 letter.
by an individual knowledgeable in biennial r.eview require-the area affected by the procedure ment can be met. It will no less frequently than every two allow for follow-up reviews years to determine if changes are to be done by persons most necessary or desirable. likely to notice procedural ~ 'J inadequacies.
Exception/Inter~retation Based on amplif cation provided in ANSI/ANS 3.2-1982, Section 5.2.15, Consumers Power Company interprets that this requirement for routine follow-up review can be accomplished in several ways, including (but not limited to): documented step-by-step checkoff associated with it) or detailed scrutiny of the proce- _,;
dure as part of a documented train- ..."
ing program, drill, simulator exercise, or other s*uch activity. ,.~:
Page 67 . Page 67 Exception/Interpretation 2.m-2.o Exception/Interpretation 2.m-2.p See Revision 10. Renumbered due to new 2.m. Renumbering only. Renumbering only.
Page 69 and 70 Exception/Interpretation 3.b RG 1.33, Sec C.4.b Not in this revision. Requirement The change is requested to Approved per NRC establish scope and fre- letter of 8/2/89.
The conformance of facility quency controls for audits operations to provisions con- of plant Technical Specifi-tained within the technical cation requirements. It specifications and applicable provides for the division license conditions - at least of Tech Spec requirements once per 12 months. into specific areas, and the complete coverage of Exception/Interpretation the entire Tech Specs over a 5 year span (maximum).
Consistent with guidance pre- It is consistent with the sented in NRC letters dated NRC guidance referenced in March 29, 1983 (RLSpessard to the change.
JMTaylor) and January 30, 1984 HI0909-0009A-QA06
ATTACHMENT 4 QUALITY ASSURANCE PROGRAM DESCRIPTION (CPC-2A)
Revision 9 Revision 10 Reason for Change Basis for Conclusion ,
(JGPartlow to RLSpessard), Con-sumers Power Company interprets the comn1itment to audit techni-cal specification/license con-ditions contained in 18.2.2(a)
I of this QAPD, and in Section 6.5.2.S(a) of both Palisades r:**.
and Big Rock Point Technical Specifications, as follows:
.\:.
Consumers Power Company main-tains a matrix that identifies I, all applicable Technical Speci- ,*
fication line items to be audi- i~
ted. The matrix is updated annually to conform to approved Technical Specification changes.
During each 12 month period, a selected sample of line items in each of the following elements "
- ~
is audited:
- 1. Limiting Conditions for Operation
- 2. Limiting Safety System Settings
- 3. Reactivity Control Systems
- 4. Power Distribution Limits
- 5. Instrumentation
- 6. Reactor Coolant System
- 7. Emergency Core Cooling System
- 8. Containment Systems
- 9. Plant Systems
- 10. Electrical Power Systems
- 11. Refueling Operations
- 12. Special Tests
- 13. Onsite Committee
- 14. Offsite Committee
- 15. Administrative Controls Audits are scheduled so that all line items are covered within a maximum period of 5 years. The audit period for any of the above elements may be reduced depending on Technical Specification com-pliance history.
MI0909-0009A-QA06