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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
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consumers Power Kenneth W Berry Director POWERING Nuclear Licensing MICHIGAN'S PROGRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (5H) 788-1636 March 20, 1990 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
PROPOSED FTOL TERMINATION DATE (TAC No. 11218)
Consumers Power Company began construction of the Palisades Nuclear Plant on July 18, 1967. On March 24, 1971 Consumers Power Company was granted a low power testing license for the Palisades Plant by the AEC, under the interim hearing provisions then in effect. The "interim" designation was removed upon the issuance of Amendment 3 to Operating License No. DPR-20 on September 1, 1972. On October 16, 1972 the Commission amended the operating license to allow full power operation. In January 1974, Consumers Power Company submitted a request that it be granted a full term operating license (FTOL) for the Palisades Plant.
In its January 1974 request, the Company sought issuance of a full term operating license that, in accordance with the Commission's policy at the time, would expire 40 years from the date of the construction permit issuance.
However, the Commission has since determined that the 40 year license term specified as the maximum term by Section 103.c of the Atomic Energy Act of 1954 (42 USC 2133(c)) may commence with the issuance of the operating license. In a number of instances, the Commission has approved requests to amend existing operating licenses to extend their terms beyond the original expiration date.
Consumers Power Company requests that the Commission, in issuing the full term operating license requested in January 1974, specify an expiration date that is 40 years from the date of issuance of the operating license, i.e., March 24,
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SUMMARY
The planned life of the Palisades Plant, as specified and analyzed in the FSAR, was for forty years of commercial service. The siting, original equipment design *specifications, fabrication, an.d plant construction were all based on an assumed useful operating life of forty years. Since the issuance of the provisional operating license (POL), Consumers Power Company has maintained various maintenance and testing programs to ensure plant equipment and OC1289-014S-NL01 ~vo\
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Nuclear Regulatory Commission 2 Palisades Plant Proposed FTOL Termination Date March 20, 1990
- --structures continue to meet the applicable design requirements. In addition to complying with the original regulatory requirements for a plant of its design and vintage, the Palisades Plant has been evaluated under NUREG 0660, NUREG 0737, the Systematic Evaluation Program (SEP), the Equipment Environmental Qualification Program (EEQ), and the Safety System Functional Inspection Program (SSFI). Each of these programs was developed by the NRC to ensure the safe operation of older nuclear power plants. Where these programs have shown that plant equipment or procedures required modification to ensure the health and safety of the public or to meet revised or updated licensing criteria, those modifications have been performed or scheduled. The Palisades Plant is currently participating in the Seismic Qualification Utility Group (SQUG). Implementation of the program developed by SQUG, and approved by the NRC, will ensure that vital plant equipment is capable of withstanding an operating basis earthquake and safely shutting down the plant.
'In support of the position that the FTOL should be granted for the fuil forty-year design life of the Palisades Plant, Consumers Power Company offers the following additional information regarding the environmental impact of plant operation and the design and maintenance-of plant equipment.
SUMMARY
OF ENVIRONMENTAL IMPACT The information and analyses presented in the Palisades Plant Final Environmental Statement (FES), dated June, 1972 were based on an assumed plant life of 40 years. The FES *has been reviewed to identify any significant changes to the Palisades Plant since the FES was issued that could change the
'original conclusions of that document. That review shows there have been no changes to the plant, plant facilities, or operation of the Palisades Plant that could cause any significant increase in the environmental 'impact of plant operation as described in the FES or that would materially change the conclusions presented in the FES.
Description of Plant and Plant Site The Palisades Plant is located on the eastern shore of Lake Michigan in Covert Township, Van Buren County, Michigan approximately four-and-one-half miles south of the southern city .limits of South Haven, Michigan. The* site area consists of rolling sand dunes which extend inland about 5,000 feet. The area adjacent to the site is primarily agricultural land and is sparsely populated.
The low population zone (LPZ), as defined by 10 CFR 100, extends a distance of 4,820 meters, or 3 miles, from the plant site. The minimum exclusion area distance to an uncontrolled area is 677 meters (2200 feet). The minimum exclusion. area and LPZ distances form the bases for the site evaluation in accordance with 10 CFR Part 100 (FSAR Section 2.0). There are approximately 432 acres within the site boundary, all currently owned by Consumers Power Company. Consumers Power Company has sole control of the area within the site boundary for the purpose of excluding personnel or property.
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Nuclear Regulatory Commission 3 Palisades Plant Proposed FTOL Termination Date March 20, 1990 The area within the owner controlled area, minimum exclusion area distance, and the tow population zone distances have not changed since the issuance of the FES.
Population Changes Section 2.1.2 of the Palisades FSAR discusses the population density in and around the Parisades Plant. Table 2.10 of the Palisades FSAR provides current and estimated population density for all counties within a 50-mile radius of the Palisades Plant through the year 2000. A comparison of the FSAR data and the most current census and population growth estimates indicate that the data presented in Table 2.10 of the FSAR accurately estimated population changes to date. Although there are no reliable estimates for the population in the three counties (Berrien, Van Buren; and Allegan) immediately adjacent to the Palisades Plant site for the years between 2000 and 2011, recent population growth and economic trends for southwestern Michigan do not indicate any significant change in population growth trends or to the economic composition of the.area.
Offsite Radiation Exposure The probable offsite radiation exposure received by a member of the general public from the operation of the Palisades Plant was assessed and is documented in the Palisades FSAR and the FES. This assessment was based on an assumed 40-year life for the plant. The FES concluded that the operation of the Palisades Plant will contribute only an extremely small increment to the radiation dose that area residents receive from natural background. The FES also noted: "Since fluctuations of the natural background dose may be expected to exceed the small dose increment contributed by the Plant, this increment will be unmeasurable in itself and will constitute *no demonstrable meaningful risk .*.. " To ensure that exposure of members of the general public to radioactive material released by the operation of the Palisades Plant is kept as low as is reasonably achievable, the Plant maintains a radiological environmental monitoring program in compliance with the requirements of Section IV of Appendix I to 10 CFR 50.
Based on the operating history of the Palisades Plant and the conclusions of the FES, the total radiation dose to any member of the general public is not expected to be significantly affected by the continued operation of the Palisades Plant through March 2011.
- 1. The transfer of ownership of the Palisades Plant from Consumers Power Company (CPCo) to the Palisades Generating Company (PGC), currently expected in early 1991, will include less than the current 432 acres.
However, the property interests transferred will give the. PGC control of the minimum exclusion area, and between them the two licensees will control the entire 432 acres.
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Nuclear Regulatory Commission 4 Palisades Plant Proposed FTOL Termination Date March 20, 1990 Onsite Radi~tion Expo~u~e All plant employees are exposed to radiation caused by plant operation. The total exposure received by individual employees depends to a great extent upon the work assignment of the employee. To ensure that employee exposure is minimized, the Palisades Plant has implemented an effective ALARA (As Low As Reasonably Achievable) Program. In addition, the plant has instituted administrative limits that require that the exposure received by individual employees remain within the guidelines of 10 CFR Part 20. It is not expected that the term of the FTOL will materially affect employee exposure.
Generation of Radioactive Waste The amount of radioactive waste that would be generated by the operation of the Palisades Plant was analyzed and discussed in the FES. The FES assumed, based on the experience of similar plants, that the Palisades Plant would generate approximately 10,000 cu ft (283 cu. meters) per year of solid waste over the operating life of the plant. The FES concluded that the impact of routine releases of rad-ioactive materials from the Palisades Plant would be negligible.
In order to minimize the amount of solid radioactive waste requiring off site disposal, ~he Palisades Plant has institut~d an aggressive waste reduction program. Over the past several years the total° amount of solid low-level radioactive waste generated by the Palisades Plant has decreased from 450 cubic meters in 1985 to 197 cubic meters in the first 6 months of 1989. The waste reduction program is expected to result in further decreases in the amount of normal waste generated. The Palisad,es Plant also is in the design and licensing phase of a. project to construct an on-site dry cask spent fuel storage facility which will e~sure the plant has sufficient spent fuel storage capacity for the entire term of the license proposed by this letter.
The plant life assumed in the FES was 40 years. Therefore, this request for an expiration date for the FTOL of March 24, 2011 will have no significant im~act on the total amount of waste that is generated or released from the plant.
- 2. Although the total amount of waste generated by normal plant operations is expected to decrease, the Palisades Plant is in the process of replacing the orginal steam generators. The effect of this project will be to temporarily increase the total amount or waste generated by the plant. This project has been the subject of previous correspondence to the Commission. That correspondence describes the radiological consequences of the project, the total amount of waste expected to be generated, and the method for the safe disposal of that waste.
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Nuclear Regulatory Commission 5 Palisades Plant Proposed FTOL Termination Date March 20, 1990 NPDES Permit System The Palisades Plant has been issued NPDES (National Pollutant Discharge Elimination System) Permit No. MI 0001457 by the State of Michigan. This permit was issued on May 31, 1985 for a term not to exceed five years. The permit will he reissued during 1990 for a further five-year period. Since the permit was issued, only minor changes to the plant waste stream, governed by that permit, have occurred. The Michigan Department of Natural Resources has determined that none of these changes was significant enough to require that the permit be amended and reissued. A copy of the permit detailing the parameters monitored and the reporting requirements was forwarded to the Administrator, NRC Region III by Consumers Power Company letter dated August 1, 1985.
ORIGINAL PLANT DESIGN Containment Building* and Other Plant Structures
- Plant structures includtng the containment building, auxiliary building, turbine building and service water building were constructed of reinforced concrete and steel. The service life of these structur~s is well in exces~ of forty years. Plant structures were designed in accordance with the design criteria. identified in Chapter 5 of the Palisades Plant FSAR. Specific design criteria for the containme~t building are discussed in Section 5.8. The design criteria for other CP Co Design Class 1 structures*are discussed in Section 5.9 of the FSAR.
Assurance that the containment building is c_apable of performing its safety function is* provided by performance of periodic integrated leak r.ate tests (ILRTs). To provide a realistic appraisal of the integrity of the containment under accident conditions, this periodic leak rate test is performed without preliminary leak .detection surveys or preliminary leak repairs. Since this program will continue throughout the lifetime of the plant, assurance is '
provided that the containment building will continue to meet its original design requirements.
Primary Coolant. System All components of the Primary Coolant System are located within the containment building. The major Primary Coolant System companents were designed considering a 40-year service life (see FSAR, Section 4.1). To achieve this, strict quality control assurance standards, as outlined in the Palisades FSAR Sections 4.5.4 and 4.5.5, were followed. Component design also considered environmental protection, adherence to established operating procedures, effects of thermal and mechanical cycling, an<l irradiation effects on the material.
The design, fabrication, construction, inspection, testing and classification of all reactor coolant system components are in accordance with the ASME Boiler OC1289-014S-NL01
... Nuclear Regulatory Commission 6 Palisades Plant Proposed FTOL Termination Date March 20, 1990
.. and J>ressure Vessel Code-,Section III, 1965 edition-, including all addenda through Winter 1965 (ASME B&PV Code,Section III, 1965, W65a), and the Code for Pressure Piping, ASA B31.1, 1955. The codes adhered to and component classifications are listed in Table 4-2 of the Palisades FSAR.
Reactor Vessel The reactor vessel and top head were designed in accordance with ASME B&PV .
Code,Section III, Class A, 1965, W65a. The continued integrity of the reactor vessel is demonstrated by compliance with 10 CFR 50.61 and 10 CFR 50 Appendices G and H and the plant technical specifications. The irradiation surveillance program is outlined in the Palisades FS.AR Section 4.5.3.
The design of the reactor vessel and reactor internals considered the effects of plant operation at full power with an 80% capacity factor or 32 effective full power years. Since the full power license was issued,' the plant has operated for the equivalent of 8 effective full power years. During that time the plant has completed'84 heatup-cooldown cycles. The* original plant design anticipated a total of 500 ,heatup-cooldown cycles. Based on the .number of effective full power years completed and the number of effective full power years available between 1990 and the proposed end of .the FTOL, the plant, if operated at the originally assumed 80% capacity, will. complete approximately 26 effective full power years by the end of the. proposed FTOL. This is well within the original design of the Palisades Plant.
The reactor vessel is the only component of the*Primary Coolant System which is exposed to a significant level of neutron irradiation. Based on the requirements of 10 CFR 50:61 and Regulatory Guide 1.99, Consumers Power Company has determined that the Palisades react.or vessel could exceed the Pressur.ized Therm?l Shock (PTS) screening criteria in early 2002. Therefore, flux reduction measures are being incorporated in the Cycle 9 fuel loading pattern.
Consumers Power Company will continue to monitor the neutron fluence received by th~ Palisades reactor vessel and will take whatever measures necessary, greater flux reduction, Regulatory Guide 1.154 analysis, etc., to ensure that the Palisades Plant will continue to operate safely.
Mechanical Equipment All safety-related mechanical equipment identified in Regulatory Guide 1.26, Revision 3 (1976), was designed to ASME B&PV Code sections III and VIII, 1965.
The initial design and construction of safety related mechanical equipment assumed a nominal 40 year operating life for that equipment. Subsequently, that equipment has been inspected and tested iri accordance with the Inservice Inspection and Testing Program described in Section 4.5.6 and Section 6.9 of the Palisades FSAR.
The Inservice Inspection and Testing Program in conjunction with the Technical Specification Surveillance and Preventative Maintenance Programs ensure that all safety-related mechanical equipment will continue to perform their design function for the design life of the plant.
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Nuclear Regulatory Commission 7 Palisades Plant Proposed FTOL Termination Date March 20, 1990 Electrical Equipment Safety-related electrical equipment at the Palisades Plant has been reviewed in accordance with the requirements of 10 CFR 50.49, "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants". A report entitled, "Environmental Qualification of Safety Related Electrical Equipment -
Palisades Plant" was submitted to the NRC on September 1, 1980. On April 25, 1983, the NRC issued the Safety Evaluation Report (SER) for the Palisades Electrical Equipment Qualification (EEQ) program. The SER contained a Technical Evaluation Report prepared by the Franklin Research Institute. These reports document the life expectancy of safety related electrical equipment, in most cases 40 years, and_identified the most severe environmental operating conditions that equipment is likely to be subjected to. A final SER, dated January 31, 1985, prepared by the NRC Staff stated that the Palisades Plant EEQ program is in compliance with 10 CFR 50.49. The initial design codes used for safety-related electrical equipment are described in Tables 5.2-4 and 5.2-5 of the Palisades FSAR.
The EEQ program in conjunction with the Inspection, Surveillance and Maintenance Programs required by Plant Technical Specifications ensure that safety-related electrical equipment will continue to perform their design function for the design life of the plant.
CONCLUSION The impacts on the environment described in the Final Environmental Statement assumed a forty-year operational life for the Palisades Plant. The original design of the Plant and its equipment also assumed a forty-year operational life. The combination of original plant design, Inservice Inspection, preventative maintenance, and Technical Specification required operational surveillance programs all combine to ensure that plant equipment will continue to meet its operational and safety requirements for the design life of the plant. Consumers Power Company believes that the requested license extension is consistent with Section 103.c of the Atomic Energy Act of 1954 and with 10 CFR 50.51 of the Commission's rules and regulations.* Based on the information presented, Consumers Power Company has shown that the Palisades Plant can be safely and reliably operated for the entire 40-year term of the proposed FTOL, subject to the satisfactory resolution of future safety concerns.
Therefore, Consumers Power Company requests that the expiration date of the Full Term Operating License for the Palisades Plant be March 24, 2011.
Kenneth W Berry Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades OC1289-014S-NL01