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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6741999-10-0202 October 1999 Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data ML18066A6791999-10-0101 October 1999 Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants. ML18066A6621999-09-30030 September 1999 Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS ML18066A6601999-09-29029 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18066A6471999-09-17017 September 1999 Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs ML18066A6331999-09-0202 September 1999 Forwards Monthly Operating Rept for Aug 1999 & Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18066A6261999-08-26026 August 1999 Forwards Addl New Valve Relief Request as Alternative to Code Requirements That Will Provide Acceptable Level of Quality & Safety.Request Would Allow Use of App II, Check Valve Condition Monitoring Program, of ASME OM Code-1995 ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML18066A6111999-08-13013 August 1999 Requests Exemption from Certain Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101. Request Concerns Oil Collection Sys Requirements for PCP Motors ML18066A5881999-07-30030 July 1999 Provides Rev to Instrument Channel Drift Measurement Submitted on 990611,in Response to NRC Comments on Util RAI Response for Sections 3.3,3.5 & 3.6 & Editorial Changes Revs Necessary for Consistency within ITS ML18066A5921999-07-30030 July 1999 Forwards Results of Review by Consumers Energy of Two NRC Draft Repts Entitled, Evaluation of Air-Operated Valves at Light-Water Reactors & Study of Air-Operated Valves in Us Nuclear Power Plants. ML18066A5971999-07-30030 July 1999 Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments ML20210G8351999-07-29029 July 1999 Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in PDR ML18066A5651999-07-19019 July 1999 Forwards Corrections to Previously Submitted TS Section 3.7, Plant Systems, Converting to Its,Per NUREG-1432.Licensee Realized That Certain Provisions of CTS Had Been Inappropriately Replaced with Provisions from STS ML18066A5111999-06-29029 June 1999 Provides Voluntary Confirmation of Facility Readiness as Outlined in GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure & Response Encl ML20209B2081999-06-29029 June 1999 Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901 ML20210G8791999-06-23023 June 1999 FOIA Request for All Document Communications Between NRC & Region III Involving R Landsman,B Jorgensen & R Caniano & NRC Staff Under Their Supervision & All Communications in Their Possession to & from Consumers Power Re Plant ML18066A5061999-06-17017 June 1999 Forwards Responses to NRC Questions for ITS LCOs 3.6.3 & 3.6.6 of 990126 Submittal.One Editorial Change in Addition to Those Made in Response to NRC Comments & Conforming Changes Made to Associated Bases,Encl ML18066A4991999-06-11011 June 1999 Forwards Responses to NRC Comments Re ITS Section 3.3 & Associated Revs to ITS Sections 1.0,3.3,3.4 & 3.9 of 990126 ITS Conversion Submittal.One Technical Change & Several Editorial Changes Unrelated to NRC Comments,Also Provided IR 05000255/19970181999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18066A4921999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18068A6011999-06-0808 June 1999 Forwards Description of Recent Changes Made to Palisades Site Emergency Plan,Excluding Minor & Editorial Changes Not Requiring Further Explanation ML18066A4881999-06-0404 June 1999 Provides Responses to NRC Questions & Associated Editorial Revs for ITS LCOs 3.6.1,3.6.2,3.6.4,3.6.5 & 3.6.7 of 980126 Submittal.Responses to Comments on Remaining Section 3.6 LCOs Will Be Submitted Separately ML18066A4801999-05-24024 May 1999 Forwards Copy of Rev to NPDES Permit Number MI0001457 Renewal Application as Submitted to Mi Dept of Environ Quality on 990513 ML18066A4721999-05-18018 May 1999 Informs That During Period from 981101-990430,there Were No NPDES Permit Violations & No Repts of Oil,Salt or Polluting Matl Losses Were Made to Govt Agencies ML18066A4651999-05-17017 May 1999 Forwards ISI Program Relief Request 14 for NRC Approval in Accordance with 10CFR50.55(a)(3) as Requirement for Which Proposed Alternative Provide Acceptable Level of Quality & Safety.Rev 0 to SIR-99-032 Rept Also Encl ML18066A4611999-05-14014 May 1999 Requests Approval to Use Alternative Requirements IAW 10CFR50.55a(a)(3)(i),proposing to Follow Requirements of ASME Boiler & Pressure Vessel Code Case N-566-1.IST Program Relief Request 6 for NRC Approval Encl ML18068A5831999-05-0303 May 1999 Forwards Proposed TS Section 3.5,in Response to NRC 990317 RAI Re Util 980126 TS Change Request Re Conversion to Improved Ts,Per NUREG-1432 ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20217A8191999-04-29029 April 1999 Forwards Listed Matls Related to Palisades Plant June 1999 Initial License Exam ML20206E8271999-04-28028 April 1999 Forwards Palisades Plant Annual Radiological Environ Operating Rept for 1998. There Were No Reportable Events During This Period ML20207B4661999-04-23023 April 1999 Forwards Copy of Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981201 for Palisades Npp.No Deficiencies Noted.Seven New Arcas Identified ML18066A4531999-04-0707 April 1999 Forwards ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1,as Requested by NRC 990406 Telcon,Per TS Change Request Submitted 980126.Change Submitted Does Not Alter Conclusions of No Signficant Hazards Considerations ML18066A4481999-04-0202 April 1999 Responds to Violations Noted in Insp Rept 50-255/98-06. Corrective Actions:Nuclear Performance Assessment Dept Has Reviewed Observations & Agrees That Field Observations by Qualified Personnel Are Important Aspect of Program ML18066A4471999-03-30030 March 1999 Confirms Completion of Util Review of Design Engineering Contractor Cable Ampacity Evaluation.Evaluation Available at Plant for NRC Review ML18066A4411999-03-30030 March 1999 Forwards Response to NRC 990126 RAI Re TS Section 3.7 of Util 980126 LAR Request for Conversion to Its.Licensee Received Permission to Delay TS Section 3.6 Response to Allow for Addl Time for Preparation & Internal Review ML18066A4441999-03-26026 March 1999 Submits Certification of Financial Assurance for Decommissioning of Palisades Nuclear Plant.Certified Rept of Status of Consumers Energy Co Decommissioning Funding & Trust Agreement Encl as Attachments 1 & 2 ML18066A4401999-03-25025 March 1999 Forwards Revised Best Estimate Fluence Evaluation Using Industry Data, Providing Justification for Using Industry Data to Determine Best Estimate Fluence.Review of Info & SE Requested ML18066A4191999-03-23023 March 1999 Forwards 1998 Annual Radioactive Effluent Release & Disposal Rept, for Palisades Plant,Providing Summary of Quantities of Radioactive Liquid & Gaseous Effluent Releases & Solid Radioactive Waste Processed During 1998 ML18066A4231999-03-22022 March 1999 Forwards Answers to 990311 Telcon Request for Addl Clarification & Revs Re ITS Section 3.4.Markups of Previously Submitted TS Pages & Revised Pages for Section 3.4 Also Encl ML20204F2091999-03-18018 March 1999 Requests That Listed TS Change Requests (Tscrs) Be Issued with Allowance That Tscrs Be Fully Implemented within Sixty Days of Issuance.Request Will Allow Time for Completion of Final Training & Procedure Changes Associated with Amend ML18066A4121999-03-18018 March 1999 Concludes That Mod to Provide Automatic Switchover of Control Room Heating,Ventilation & Air Conditioning (CRHVAC) Sys to Emergency Mode Is Not Needed to Meet Regulatory Requirements.Mod Commitment Cancelled ML18066A4141999-03-18018 March 1999 Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML18066A4131999-03-11011 March 1999 Responds to NRC 990210 Ltr Re Violations Noted in Insp Rept 50-255/98-22.Corrective Actions:Analytical Evaluation, EA-C-PAL-98-1067-01, P-50A Case to Cover Stud Evaluation, Was Submitted to NRC on 981220 ML18068A5241999-02-12012 February 1999 Resubmits Relief Request 12,with Addl Info That Includes Specific Locations Where Relief Request Would Be Applied,Per 10CFR50.55a(g)(5)(iii) ML18068A5211999-02-11011 February 1999 Informs NRC That Implementation of Formal Industry Position on Severe Accident Mgt at Palisades Plant Was Completed on 981217 ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6741999-10-0202 October 1999 Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data ML18066A6791999-10-0101 October 1999 Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants. ML18066A6621999-09-30030 September 1999 Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS ML18066A6601999-09-29029 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18066A6471999-09-17017 September 1999 Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs ML18066A6331999-09-0202 September 1999 Forwards Monthly Operating Rept for Aug 1999 & Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18066A6261999-08-26026 August 1999 Forwards Addl New Valve Relief Request as Alternative to Code Requirements That Will Provide Acceptable Level of Quality & Safety.Request Would Allow Use of App II, Check Valve Condition Monitoring Program, of ASME OM Code-1995 ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML18066A6111999-08-13013 August 1999 Requests Exemption from Certain Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101. Request Concerns Oil Collection Sys Requirements for PCP Motors ML18066A5971999-07-30030 July 1999 Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A5881999-07-30030 July 1999 Provides Rev to Instrument Channel Drift Measurement Submitted on 990611,in Response to NRC Comments on Util RAI Response for Sections 3.3,3.5 & 3.6 & Editorial Changes Revs Necessary for Consistency within ITS ML18066A5921999-07-30030 July 1999 Forwards Results of Review by Consumers Energy of Two NRC Draft Repts Entitled, Evaluation of Air-Operated Valves at Light-Water Reactors & Study of Air-Operated Valves in Us Nuclear Power Plants. ML18066A5651999-07-19019 July 1999 Forwards Corrections to Previously Submitted TS Section 3.7, Plant Systems, Converting to Its,Per NUREG-1432.Licensee Realized That Certain Provisions of CTS Had Been Inappropriately Replaced with Provisions from STS ML18066A5111999-06-29029 June 1999 Provides Voluntary Confirmation of Facility Readiness as Outlined in GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure & Response Encl ML20210G8791999-06-23023 June 1999 FOIA Request for All Document Communications Between NRC & Region III Involving R Landsman,B Jorgensen & R Caniano & NRC Staff Under Their Supervision & All Communications in Their Possession to & from Consumers Power Re Plant ML18066A5061999-06-17017 June 1999 Forwards Responses to NRC Questions for ITS LCOs 3.6.3 & 3.6.6 of 990126 Submittal.One Editorial Change in Addition to Those Made in Response to NRC Comments & Conforming Changes Made to Associated Bases,Encl ML18066A4991999-06-11011 June 1999 Forwards Responses to NRC Comments Re ITS Section 3.3 & Associated Revs to ITS Sections 1.0,3.3,3.4 & 3.9 of 990126 ITS Conversion Submittal.One Technical Change & Several Editorial Changes Unrelated to NRC Comments,Also Provided IR 05000255/19970181999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18066A4921999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18068A6011999-06-0808 June 1999 Forwards Description of Recent Changes Made to Palisades Site Emergency Plan,Excluding Minor & Editorial Changes Not Requiring Further Explanation ML18066A4881999-06-0404 June 1999 Provides Responses to NRC Questions & Associated Editorial Revs for ITS LCOs 3.6.1,3.6.2,3.6.4,3.6.5 & 3.6.7 of 980126 Submittal.Responses to Comments on Remaining Section 3.6 LCOs Will Be Submitted Separately ML18066A4801999-05-24024 May 1999 Forwards Copy of Rev to NPDES Permit Number MI0001457 Renewal Application as Submitted to Mi Dept of Environ Quality on 990513 ML18066A4721999-05-18018 May 1999 Informs That During Period from 981101-990430,there Were No NPDES Permit Violations & No Repts of Oil,Salt or Polluting Matl Losses Were Made to Govt Agencies ML18066A4651999-05-17017 May 1999 Forwards ISI Program Relief Request 14 for NRC Approval in Accordance with 10CFR50.55(a)(3) as Requirement for Which Proposed Alternative Provide Acceptable Level of Quality & Safety.Rev 0 to SIR-99-032 Rept Also Encl ML18066A4611999-05-14014 May 1999 Requests Approval to Use Alternative Requirements IAW 10CFR50.55a(a)(3)(i),proposing to Follow Requirements of ASME Boiler & Pressure Vessel Code Case N-566-1.IST Program Relief Request 6 for NRC Approval Encl ML18068A5831999-05-0303 May 1999 Forwards Proposed TS Section 3.5,in Response to NRC 990317 RAI Re Util 980126 TS Change Request Re Conversion to Improved Ts,Per NUREG-1432 ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20217A8191999-04-29029 April 1999 Forwards Listed Matls Related to Palisades Plant June 1999 Initial License Exam ML20206E8271999-04-28028 April 1999 Forwards Palisades Plant Annual Radiological Environ Operating Rept for 1998. There Were No Reportable Events During This Period ML20207B4661999-04-23023 April 1999 Forwards Copy of Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981201 for Palisades Npp.No Deficiencies Noted.Seven New Arcas Identified ML18066A4531999-04-0707 April 1999 Forwards ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1,as Requested by NRC 990406 Telcon,Per TS Change Request Submitted 980126.Change Submitted Does Not Alter Conclusions of No Signficant Hazards Considerations ML18066A4481999-04-0202 April 1999 Responds to Violations Noted in Insp Rept 50-255/98-06. Corrective Actions:Nuclear Performance Assessment Dept Has Reviewed Observations & Agrees That Field Observations by Qualified Personnel Are Important Aspect of Program ML18066A4471999-03-30030 March 1999 Confirms Completion of Util Review of Design Engineering Contractor Cable Ampacity Evaluation.Evaluation Available at Plant for NRC Review ML18066A4411999-03-30030 March 1999 Forwards Response to NRC 990126 RAI Re TS Section 3.7 of Util 980126 LAR Request for Conversion to Its.Licensee Received Permission to Delay TS Section 3.6 Response to Allow for Addl Time for Preparation & Internal Review ML18066A4441999-03-26026 March 1999 Submits Certification of Financial Assurance for Decommissioning of Palisades Nuclear Plant.Certified Rept of Status of Consumers Energy Co Decommissioning Funding & Trust Agreement Encl as Attachments 1 & 2 ML18066A4401999-03-25025 March 1999 Forwards Revised Best Estimate Fluence Evaluation Using Industry Data, Providing Justification for Using Industry Data to Determine Best Estimate Fluence.Review of Info & SE Requested ML18066A4191999-03-23023 March 1999 Forwards 1998 Annual Radioactive Effluent Release & Disposal Rept, for Palisades Plant,Providing Summary of Quantities of Radioactive Liquid & Gaseous Effluent Releases & Solid Radioactive Waste Processed During 1998 ML18066A4231999-03-22022 March 1999 Forwards Answers to 990311 Telcon Request for Addl Clarification & Revs Re ITS Section 3.4.Markups of Previously Submitted TS Pages & Revised Pages for Section 3.4 Also Encl ML20204F2091999-03-18018 March 1999 Requests That Listed TS Change Requests (Tscrs) Be Issued with Allowance That Tscrs Be Fully Implemented within Sixty Days of Issuance.Request Will Allow Time for Completion of Final Training & Procedure Changes Associated with Amend ML18066A4141999-03-18018 March 1999 Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles ML18066A4121999-03-18018 March 1999 Concludes That Mod to Provide Automatic Switchover of Control Room Heating,Ventilation & Air Conditioning (CRHVAC) Sys to Emergency Mode Is Not Needed to Meet Regulatory Requirements.Mod Commitment Cancelled ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML18066A4131999-03-11011 March 1999 Responds to NRC 990210 Ltr Re Violations Noted in Insp Rept 50-255/98-22.Corrective Actions:Analytical Evaluation, EA-C-PAL-98-1067-01, P-50A Case to Cover Stud Evaluation, Was Submitted to NRC on 981220 ML18068A5241999-02-12012 February 1999 Resubmits Relief Request 12,with Addl Info That Includes Specific Locations Where Relief Request Would Be Applied,Per 10CFR50.55a(g)(5)(iii) ML18068A5211999-02-11011 February 1999 Informs NRC That Implementation of Formal Industry Position on Severe Accident Mgt at Palisades Plant Was Completed on 981217 ML18066A4051999-02-10010 February 1999 Requests Copy of Consumers Energy (Palisades) Formal Response to RAI Dtd 990512 (USI A-46) ML18066A3921999-01-29029 January 1999 Forwards Licensee Interpretation of TS Requirements for Performance of SRs as Applied to Instrumentation Channel Calibr.Ltr Established No New Commitments ML18066A3891999-01-28028 January 1999 Submits Response to Concern Expressed in Insp Rept 50-255/98-06 Re Whether Palisades ISI Program Was Being Conducted IAW Applicable Requirements 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML18057A4811990-09-17017 September 1990 Confirms 900718 Telcon Notification Re Westinghouse Agreement to Join Utils as Equity Investor in Plant ML18057A4551990-09-0606 September 1990 Forwards Proprietary Info Re Dept of Labor Decision on Discharge of Former Employee of Util,Per NRC 900809 Request. No 10CFR50.7 Violation Occurred Since Job Performance Was Reason for Discharge.Encl Withheld (Ref 10CFR2.790(a)(6)) ML18057A4521990-09-0404 September 1990 Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated IR 05000255/19900101990-09-0404 September 1990 Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated ML18057A4371990-08-31031 August 1990 Forwards Analysis Concluding That Plant Reactor Beltline Matl Upper Shelf Energy Will Remain Greater than 50ft-lbs Until Yr 2032,per 900716 Commitment ML18057A4381990-08-31031 August 1990 Forwards Info Re Contamination of South Radwaste Area,Per 10CFR20.302,in Response to NRC 900112 Request.Approval Requested to Dispose of Low Level Radwaste in Place ML20059E0001990-08-29029 August 1990 Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990 ML18057A4201990-08-24024 August 1990 Forwards Revised Application for Amend to License DPR-20, Changing Tech Specs Re Incore Analysis Program.Request Revised Per NRC Comments During 900709 Meeting ML18057A4021990-08-22022 August 1990 Forwards Missing Pages from Decommissioning Funding Rept, Consisting of Pages 25 & 26 of Attachment a to Exhibit E ML18057A4241990-08-21021 August 1990 Forwards Application for Amend to License DPR-20,changing Tech Spec 4.5.1 Re Statement on Integrated Leak Rate Test ML18057A4071990-08-21021 August 1990 Forwards Tech Specs Change Request to License DPR-20,to Remove Redundant Requirements & Change Basis Statements No Longer Applicable ML18057A4121990-08-21021 August 1990 Forwards Application for Amend to License DPR-20,changing Tech Specs to Revise Wording for Reactor Protective Sys Trip Setting Limits for Steam Generator Low Water Level ML18057A4181990-08-21021 August 1990 Forwards Description of Changes Being Made to Plant Site Emergency Plan & Emergency Plan Changes.Change Allows Reduction in Shift Staffing During Cold Shutdown for Stated Staff ML18057A3911990-08-17017 August 1990 Forwards Replacement Pages,To Palisades Second 10-Yr Interval Inservice Insp Program. ML18057A3851990-08-17017 August 1990 Forwards Addl Info in Support of NRC Development of SER for full-term OL for Plant,Including Date of SER Providing Provisional OL to Plant & Summary of Valid Exemptions from 10CFR Regulations,Per Telcon ML18057A3841990-08-17017 August 1990 Provides Addl Info Re Transfer of Plant Ownership to Palisades Generating Co,Per NRC 900725 Ltr ML18057A3821990-08-14014 August 1990 Requests That Bechtel-KWU Rept 128901/MJS, Full Flow Testing of Motor-Operated Valve MO-1042A, Be Withheld (Ref 10CFR2.790(b)(1)) ML18057A3721990-08-0808 August 1990 Forwards Addl Info Re Util Request for Exemption from Separation Criteria of 10CFR50,App R,Section III.G.2 Re Containment Air Room ML20055J1421990-07-26026 July 1990 Responds to Commitment Oversight Issue Resulting from Insp Rept 50-255/90-08.Commitment Mgt Seminar Training Will Be Complete Prior to 901001 ML18057A3561990-07-26026 July 1990 Forwards Certification of Financial Assurance for Decommissioning ML18057A3411990-07-18018 July 1990 Forwards Revised Proposed Tech Spec Page 6-3,now Designated as Page 6-1b,adding Section 6.3.4,now Designated as Section 6.3.5 to Remove Organization Charts,Per Generic Ltr 88-06 ML18057A3381990-07-16016 July 1990 Advises That Util Does Not Foresee Need to Rely on Section V.C of App G to Remain in Compliance W/Upper Shelf Energy (Use) Requirements Re Use of Matl in Reactor Beltline ML18057A3281990-07-13013 July 1990 Responds to Request for Addl Info Re Second 10-yr Interval Insp Program,Per 900418 Telcon.Util 900329 Response Revised to Reflect That Certain Components in Class 2 Sys Should Not Be Exempted,Per IWC-1220 of 1974 ASME Code Section XI ML18057A3191990-07-0909 July 1990 Forwards Performance Indicator Trend Graphs for Jan 1989 - May 1990 ML18057A3201990-07-0606 July 1990 Discusses Reassessment of Control Room Temp Following Station Blackout Event.Results of Analysis Indicate That Control Room Temp Will Remain Below 112 F for 4 H After Onset of Blackout ML18057A3171990-07-0303 July 1990 Provides Summary of Upgrades Made to Plant Electrical Distribution Sys,Per 870714 Loss of Offsite Power Event When Inadvertent Actuation of Water Deluge Spray Sys for 1-2 Startup Transformer Resulted in Bus to Ground Fault ML20058K3771990-07-0202 July 1990 Forwards Rev 26 to Security Plan.Rev Withheld (Ref 10CFR73.21(c)) ML18057A3111990-06-25025 June 1990 Forwards Endorsements 116 & 117 to Nelia Policy NF-179 & Endorsements 102 & 103 to Maelu Policy MF-50 ML18057A3101990-06-25025 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements on Corrective Actions. ML18057A3031990-06-22022 June 1990 Provides Addl Info Re Environ Qualification of Instrument Circuit Associated W/Steam Generator Pressure Channel PT-0752D,per Insp Rept 50-255/90-05.Circuits Spliced Directly to Pigtail from Electrical Penetration Connector ML18057A3001990-06-21021 June 1990 Concurs W/Nrc Change in Terminology & Submits Revised Proposed Section 4.14 of Tech Specs ML18057A2771990-06-15015 June 1990 Forwards Corrected NRC Form 474 Re Simulation Facility Certification,Indicating Exceptions to Ansi/Ans 3.5 ML18057A2901990-06-13013 June 1990 Forwards Application for Amend to License DPR-20,revising Tech Spec 3.3.1.b Re Safety Injection Tank Min Level ML18057A2941990-06-12012 June 1990 Advises That Submittal of Second Interval Inservice Insp Program Delayed from 900615 to 900715,per 900418 Telcon ML18057A2711990-06-11011 June 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.1.1i in Order to Maintain Plant in Hot Shutdown While Repair Made to Pressurizer Heater Power Supply.Request Based on 900608 Failure of Heater Transformer 15 ML18057A2641990-06-11011 June 1990 Provides Response to NRC Requalification Exam Rept Dtd 900410 on NRC Concerns Re Facility & Training Ctr Staffing. Adequate Staffing Will Be Maintained to Ensure Operator Requalification Program Successful ML18057A2591990-06-11011 June 1990 Forwards Palisades Simulator Certification Submittal. ML18057A2631990-06-10010 June 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.1.1i to Enable Plant to Be Maintained in Hot Shutdown While Repair Made to Pressurizer Heater Power Supply.Waiver Requested for 900611-18 ML18057A2571990-06-0808 June 1990 Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-255/90-12.Corrective Actions:Continuing Training Program Will Be Developed for Supervisors That Will Discuss Fire Protection Program Implementation Topics ML20043D0601990-06-0404 June 1990 Forwards Rev 25 to Security Plan,Including Changes to Security Plan Drawings to Clarify Protected Area Boundary within Plant Security Bldg & Vital Area Boundaries in Other Specific Vital Areas of Plant.Rev Withheld (Ref 10CFR73.21) ML18057A2581990-06-0101 June 1990 Forwards Revised Response to Violations Noted in Insp Rept 50-255/89-26.Concurs That Tests Performed Using Instrumented Insp Technique During 1988 Refueling Outage Considered Invalid ML18057A2561990-05-31031 May 1990 Advises That No NPDES Notifications Required Nor Any Repts of Oil or Salt Occurred During Nov 1989 - Apr 1990 ML18057A2541990-05-30030 May 1990 Forwards Response to Technical Evaluation Rept EGG-NTA-8333 Which Evaluated Plant Compliance w/NUREG-0737,Item II.D.1 & Requested Addl Info Re New PORVs & Block Valves No Later than Jan 1990 ML18057A2511990-05-30030 May 1990 Forwards Final Response to Concerns Re Porv/Block Valve Mod, Per 900308 Meeting.Bechtel Technical Rept Withheld ML18057A2501990-05-29029 May 1990 Forwards Investigation Rept Re Unsatisfactory Performance Testing of Fitness for Duty Program Blind Performance Test Samples ML18057A2411990-05-24024 May 1990 Forwards Revised Application to Amend License DPR-20, Consisting of Revised Attachments 1 & 5 to 890227 Amend Request,Reflecting Transfer of Plant Ownership ML18057A2311990-05-17017 May 1990 Forwards Analysis of Reactor Pressure Vessel Fast Neutron Fluence & PTS Ref Temps for Palisades Nuclear Plant. Rept Concludes That PTS Screening Criteria Will Be Exceeded at Axial Welds in Sept 2001 as Opposed to Mar 2002 ML18054B5861990-05-0707 May 1990 Forwards Monthly Trend Graph Rept for Jan 1989 - Mar 1990 Covering Safety Status Performance Indicators for HPSI, Auxiliary Feedwater,Emergency Ac Power,Lpsi,Containment Spray & Svc Water Sys ML18054B5801990-04-30030 April 1990 Responds to Request for Addl Info on Proposed Administrative Changes to Tech Spec Section 3.0.4,per Generic Ltr 87-09. Licensee Will Implement Program to Assure Appropriate Level of Mgt Approval Required When Operating Conditions Changed ML18054B5741990-04-25025 April 1990 Requests That Correspondence Re 890227 Application for Amend to License DPR-20 to Permit Transfer of Ownership of Plant Be Sent to Listed Address 1990-09-06
[Table view] |
Text
,.,_*
consumers Power POWERIN&
NllCHl&AN'S PRO&RESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550 June 30, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION A November 3, 1986 NRC letter requested additional information pertaining to the implementation of the ATWS rule at Palisades. The enclosure to this letter provides the responses to the NRC concerns. Included in the response are three sets of drawings for the proposed. modifications and information from our supplier of relays to be used as electrical isolation devices. The relay supplier, Telemecanique, considers the information proprietary; therefore, as required by 10CFR2.790(b), an Affidavit attesting to the proprietary nature of the Telemecanique report is also enclosed which provides the necessary information to support withholding from public dis.closure.
Although we have chosen to delay installation of the ATWS modifications until the second refueling outage from now, we wish to resolve the NRC concerns within the next few months. We, therefore, request the NRC to apply appropriate priority to thi~ *response consistent with your November 3, 1986 letter which indicated 60_,days as necessary for NRC review.
Thomas C Bordine Staff Licensing Engineer CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachments re7o7o7o.339 e7ob3o *.
i . PPD*R ADqCK 05000255.,,
PDR OC0687-0088-NL02 r
ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 ATWS ENCLOSURE RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION June 30, 1987 6 Pages AT0687-0088-NL04
ATWS ENCLOSURE RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION The following discussion is in response to your request dated November 3, 1986 for additional information regarding diversity, electrical independence and reliability/testability at power. This discussion is supplemented by the attached Table 1 and Figures 1 and 2.
Drawings for the proposed modification are being ~upplied for your review.
Changes for this modification are typically shown with a "balloon" to differentiate from the sections of existing circuits/logic that are not being changed and an 8- is added to the base number to signify that the drawings are part of an active project. A short description of the enclosed drawings and their changes are provided to facilitate your review.
DRAWING DESCRIPTION Logic diagram 8-El7, sheet 21A and schematic diagram 8-E-238, sheet 4 show the changes we are proposing to provide electrical diversity for the AFAS.
Solenoid valve SV-0522B is normally energized from preferred DC bus Dll and blocks the normal and/or backup air supply to control valve CV-0522B. In the event of Dll's failure, SV-0522B will open and provide air to CV-0522B causing the steam driven auxiliary feed pump to start. The Auxiliary Feedwater flow control valves CV-0727 and CV-0749 are air-to-close valves. On loss of power from DC bus DlO (D20) to the flow control circuits or loss of the flow signal, these valves will fail open. A path for auxiliary f eedwater will be maintained on loss of power or instrument signal to the flow control valves.
Schematic diagram 8-E-121, sheet 1 shows the normal turbine trip solenoid 20/AST and its associated initiation devices. 20/AST is powered from DC bus D21. Schematic diagram 8-E-121, sheet lA and logic diagram 8-E17, sheet 9 illustrates the redundant and diverse emergency trip solenoid 20/ET. 20/ET will be energized by ATWS-1 contacts among others and will be powered from DC bus D205. 20/ AST and 20/ET employ different principals of. operation and will be powered from independent DC supplies.
Schematic diagram 8-E-84, sheet 2 shows the changes made to include _the ATWS trip as part of the pressurizer pressure control and measurement channel instrumentation. Schematic diagram 8-E-84, sheet 2A contains the matrix relays, initiating contacts, and the fuses used to provide electrical isolation between ATWS circuits and Class lE circuits. Schematic diagram 8-E-212, sheet 3 contains the matrix relay contacts in the *2-out-of-4 logic for the ATWS trip. It also contains hand switch HS-0102D contacts that will inhibit the ATWS-1 trip relay to facilitate testing and/or maintenance. The ATWS-1 relay is powered from preferred AC panel Y230A which is powered from DC bus D205 to provide electrical independence. The ATWS-1 relay output contacts AT0687-0088-NL04
2 are used as electrical isolation devices between the ATWS circuitry and the Class lE reactor trip circuitry. The ATWS-1 relay is a Telemecanique 600V Class JlOA industrial control relay. Telemecanique documentation is enclosed with this submittal to justify our use of this relay as a Class lE isolation device.
Schematic diagram 8-E-122, sheet 1 shows the ATWS-1 reactor trip contacts in series with the undervoltage trip circuit breaker, and the existing redundant reactor trip push button #2 in each of two channels. The ATWS-1 turbine trip contact was discussed above. Vendor schematic diagram 8-950Yl8l*MlQ, sheet 1198 is included to expand on 8-E-122, sheet 1 and to assist in showing the required diversity.
Annunciator schematic diagram 8-E-295(Q), sheet 5 illustrates the alarm that will be annunciated and continuously displayed if any of the matrix relays are energized or if the ATWS channel is bypassed by HS-0102D.
ADDITIONAL INFORMATION RESPONSES AFAS, RPS and ATWS all use 2-out-of-4 sensor channel logic to detect an "off normal" condition. AFAS employs a l-out-of-2 channel logic for actuation. The RPS employs a l-out-of-2 taken twice actuation logic. ATWS utilizes a single actuation channel. A point by point response to your required information request follows:
- 1. Diversity from the Existing Reactor Trip System Table.l lists the components, manufacturer and part number, power supply; power source and design principle as applicable in each case. The table includes components from the sensor to the final actuation device in each of the three systems where diversity is required. Figures 1 and 2 further illustrate that diversity.
Bis tables The bistables for the two existing systems and one proposed system under consideration are made by different manufacturers. All have different principles of operation. All three bistables are powered from the AC vital busses. RPS and AFAS fail to tripped condition on loss of AC. The ATWS design is energized to trip.
Matrix Relays The matrix relays are all made by different manufacturers and all employ different principles of operation. RPS and ATWS systems are powered by the AC vital busses while the AFAS is powered from the DC vital busses.
The RPS system matrix relays fail to tripped condition on loss of power source. The AFAS and ATWS are both energized to trip. Although the AFAS matrix relay is energized to start the AFW pump, an intervening actuation AT0687-0088-NL04
3 device (solenoid valve) is de-energized to start. *Thus, on loss of control power, once of the three AFW pumps will auto start.
Initiation Relays Initiation relays are present in only the AFAS and ATWS systems.
Diversity is not required between these systems.
Actuation Devices Actuation devices in the three systems are all made by different manufacturers. The RPS and ATWS systems are powered from the AC vital buses. The AFAS system is powered by the DC vital bus. The RPS and ATWS systems are de-energized to trip. The AFAS is energized to trip.
2 . . Electrical Independence from the Existing Reactor Trip System (RTS)
ATWS Station battery D204 will provide the preferred power to AC panel Y230A via inverter Y210 (see Palisades P&ID Dwg ES Sh 3). D204 is not used to provide power to the RTS components and, therefore, satisfies the electrical independence requirement.
As discussed in our March 19, 1986 meeting with NRR, the matrix relays for the ATWS system are powered from the preferred AC busses. Each matrix relay is fused inside the respective channel from which it receives power. These fuses are sized to protect the integrity of safety related circuits from failures in the ATWS circuits.
AFAS DC control power for the auxiliary feed pump start circuits is provided from the same source as the RTS circuits. Electrical independence for the AFAS is provided by changing the logic and operation of air supply solenoid valve SV0522B *. Electrical independence is provided by the
- following method: With DC p9wer and associated AC inverter available, all three auxiliary feed pumps will function as designed when the signal for auxiliary feed automatic start is received. When DC power is not available, SV0522B will de-energize opening the normal or backup air supply line to the "air to open" steam supply valve CV522B which provides steam to the auxiliary feedwater pump turbine driver K-8. Thus, with DC power and associated AC inverter available, the auxiliary feed pumps will function as designed to.supply auxiliary feedwater and when DC power becomes unavailable the steam-driven auxiliary feedpump will automatically start due to the loss of the DC power.
AT0687-0088-NL04
4
- 3. Reliability and Testability at Power
- a. Periodic testing of RPS and AFAS while at power is accomplished by use of the Technical Specification Surveillance Program. New Technical Specification tests will be generated to test the ATWS circuit. The proposal for testing will include provisions to:
(1) check each of four pressure indicators for comparison each shift, (2) test each meter relay by applying a test signal every month, and (3) test each meter relay by applying a test signal to verify sensor to trip device actuation logic each refueling.
- b. The existing AFWS actuation circuitry is considered to meet the diversity requirements of the ATWS rule as shown in Table 1 and Figures 1 and 2. Testing at power for the AFWS will continue to be performed without changing the existing testing program which is presently covered by the Palisades Technical Specification Surveillance Testing Program (reference T~S. Section 4.9) *
. c. A hand operated keyswitch will affect the bypass of the turbine/
reactor ATWS trip relay to allow testing/maintenance. This bypass will be automatically annunciated and continually indicated on a main control board annunciator panel.
- d. Technical Specifications will be proposed that will require demonstration that the systems and equipment required by the ATWS rule will be adequately maintained and capable of performing thei~ desig~
functions in a reliable manner. The proposal will also include operability requirements which will specify the required operation and availability to ensure the necessary reliability of the equipment is maintained. This will be accomplished by:
( 1) checking each of the four pr'essure indicators for comparison each shift.
(2) testing each meter relay by applying a test signal every month.
(3) testing each meter relay by applying a test signal to verify sensor to trip device actuation logic each refueling.
(4) specifying the availability requirements' for the ATWS equipment.
(5) specifying the operability requirements for the ATWS equipment.
(6) identifying the Limiting Conditions for Operation when availability and operability requirements are not met.
- e. The only bypass feature is described in 3c above.
AT0687-0088-NL04
5
- f. As described in the paragraphs that follow, good Human Factor Engineering practices (consistent with NUREG-0700 "Guidelines for Control Room Design Reviews," Chapter 6 "Control Room Human Engineering Guidelines") have been incorporated into the design of ATWS prevention/mitigation system components located in the control room.
Control Room Alarm Both the ATWS "Trip" and "Bypass" condition is annl;lnciated on a common window located within the RPS annunciator panel. Sharing a common window is considered desirable since very few spare windows exist on this panel, and entering a bypass condition is a procedurally controlled evolution at the plant ensuring that the operator is informed of the bypass and its associated alarm prior to it being affected.
As indicated, the new alarm will be incorporated into the existing RPS .
annunciator panel which is locat_ed above the RPS controls and displays per NUREG-0700, Section 6.3.3.1. This panel currently features a small number
- of alarm windows sub-*grouped by function for ease of recognition according to the requirements of NUREG-0700, Section 6.3.3.3.d. Utilizing the existing panel ensures that the labeling and color/auditory coding scheme is consistent with.other RPS trip and bypass annunciation.
Control Room Indicators As described in our April 23, 1986 submittal, the four existing pressurizer indicator/alarms will be replaced with four redundant Versatile 9292 indicator/alarms each featuring an additional setpoint to initiate a channel ATWS signal. To maintain operator familiarity with specific indicator location, the new indicator/alarms will be installed at the control panel locations which will be vacated by removal of the existing units.
Each indicator/alarm features a vacuum fluorescent bargra~h display to optimize readability. A specific human factors review of this indicator has been conducted by Consumers Power Company Operations and Engineering personnel. The review consisted of comparing the readability of the Versatile bargraph display to other manufacturers' models featuring both conventional pointer-driven displays and bargraph displays. The review consensus indicated that the Versatile bargraphs provide superior readability in term~ of contrast, character dimensions and viewing angle.
It is concluded that the use of these meters will ensure that the readability requirements of NUREG-0700, Sections 6.1.2.2.e and 6.5.1.3 will be met.
Finally, the four new indicator/alarms will be identical in terms of display features such as bargraph display, fixed scale characterization, color coding and labeling according to the compatibility requirements of NUREG-0700, Section 6.5.1.5.d.
AT0687-0088-NL04
- 6 Control Room Controls The key-operated control switch, which will be used to: 1) bypass the ATWS initiating trip circuit:s-for maintenance or testing, and 2) reset the ATWS trip signal, will be located near the aforementioned Versatile indicators and within clear sight of the aforementioned trip/bypass alarm according to the requirements of NUREG-0700, Sections 6.9.1.1 and 6.9.1.2.
The switch design (ie, handle shape and relative locations of individual switch positions such as "reset" and "bypass") is similar to other switches already installed in the control room for similar purposes according to the requirements of NUREG-0700, Section 6.4.2.2.a, c and d. The key is removable only in the "normal" position in accordance with NUREG-0700, Section 6.4.4.3.e.
AT0687-0088-NL04
RPS TABLE 1
- AFAS PALISADES NUCLEAR POWER PLANT DIVERSITY TABLE FOR ATWS RULE ATWS (Existing) (Existing) (Proposed)
SENSOR TYPE High Pressurizer Low S.G. Level High Pressurizer Pressure Pressure MANUFACTURER Rosemount Rosemount Rosemount PART NO. 1153GD9 1153DD5 1153GD9 POWER SUPPLY Foxboro Lambda Foxboro POWER SOURCE AC Vital Bus AC Vital Bus AC Vital Bus BI STABLES MANUFACTURER Gulf Vitro Versatile PART NO. NT-4 2717-1076 9292 POWER SUPPLY Dynage Lambda/CEA N/A POWER SOURCE AC Vital Bus AC Vital Bus AC Vital Bus DESIGN PRINCIPLE Mercury Relay A to D Voltage Indicating Comparator Voltage Switch MATRIX RELAYS MANUFACTURER Ad lake Vitro Telemecanique PART NO. MW2600 2717-1081 J-10 A4012 POWER SUPPLY Dynage CEA N/A POWER SOURCE AC Vital Bus DC Vital Bus AC Vital Bus DESIGN PRINCIPLE Mercury Relay Solid State Logic Electromechanical Module Relay INITIATION RELAYS MANUFACTURER N/A Agastat Telemecanique PART NO. GPD-N-R J-10 A4012 POWER SOURCE DC Vital Bus Y-230A DESIGN PRINCIPLE Electromechanical Electromechanical Relay Relay ACTUATION DEVICE MANUFACTURER Allen-Bradley Agastat Westinghouse PART NO. 702-DAD94 E-7012-PC D-JA-2200.
w/UV Trip POWER SOURCE AC Vital Bus DC Vital Bus AC Vital Bus DESIGN PRINCIPLE Electromechanical Electromechanical U.V. Circuit Con tac tor Relay Interruptor With the exception of the sensors which are exempted from the ATWS rule, diversity of the RPS, ATWS and AFAS is shown in the above table and the attached block diagrams. All of the components in each system are from different manufacturers and, in several cases, use power from different sources.
AT0687-0088-NL04
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Drawing Sheet Revision Title 8-El7 9 2 Logic Diagram, Turbine Gene-rator Trips and Fast Transfer 8-El .. *- 21A 1 Logic* Diagram, Auxiliary* Feed-water Pump PS~ Control 8-E84 2 2 Schematic Diagram, Pressurizer Pressure Control & Measurement Channel Instrumentation 8-E-84 2A 2 Schematic Diagram, Pressurizer Pressure ATWS 8-E-121 1 2 Schematic Diagram, Turbine Control 8-E-121 lA 2 Schematic Diagram, Turbine Control 8-E;...212 1 0 Schematic Diagram, Turbine Control 8-E-212 3 2 Schematic Diagram, Pressurizer Pressure ATWS 8-E-238 4 1 Schematic Diagram, Auxiliary Feedwater System 8-E-295 5 0 Schematic Diagram, Annunciator Reactor Protective Panel 8-950yl8l*MI-Q 1198 1 Reactor Protective System Schematic DWG0687-0088-NL02
I*
ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 TELEMECANIQUE RELAY INFORMATION CONTAINS PROPRIETARY INFORMATION June 30, 1987 52 Pages ATT0687-0088-NL02
A .F F J D A V I T STATE OF MARYLAND *.* ~)
) - SS. **
COUNTY OF CARROLL )
I, R~ W. Jones,* being duly s~orn, h~r~by say and depose:
- 1. I am Dfrect.C:ir -of. Operations for Telemec:_anique **Irie.~ *~
Westminster, MD*, :*here after. known as TE, and. ani authorized to exec.ute this Affidavit. ' ..
. 2. I am .fami-li.ar with TE's Corporate Procedures for preparatiOn*
arid c6ntrol of desi~~ documentat~pn:
Certification for *saf_ety Related JlO Relays" and TE Report*CC-14-386, "IEEE 323-1974 Certification for Safety Related JlO Relays", here after referred to as* "Documents~*. I.nformat.ion. contained .i_n these D9cuments ,have been classified as proprietary in. ac.cordance . .
with-- the procedures
. . .*... es ta bl fshed _by TE for the control and pr_otection of information;
- 4. The Documents contain *informatiori of a proprietary_ and corifidential *nature which is n6t available in public sources. Based on
. my experience, I ani**aware that other companies regard information o*f the kind contained in the Documents as p_ropri_~~ary and ~onfiden_ti_al_...
- The information c'ontained in.the Documents* are consider.ed by TE:to be proprietary because* it reveals Ge~tain distingui5hing aspects of TE's JlO relay product l.i-ne_, here after -referred* to as relay, and*test procedures *whhh secur~ competitive advantage to TE for safety re 1ated TELEMECANIQUE INC., 2002 BETHEL ROAD, WESH*~INSTER, MD 21157, (301.) 876-2214
- 1
. Jr-*1'*. ;;
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(_.r)*
c I electrical control circuits. The Documents also include information which affords TE an opportunity to obtain a tomp~titive advantage over those who do not or may not know or use the- information contained in the Doe1,1ments.
- 6. The Documents provide information which reveals strategic data for TE equipment qualification programs* develope*d over ~he :-past several y~ars_. TE_ has i nvest~d over one hundred thousand dollars and _many inan hours of effort in developing the Relay Qualification.
__ 7: The Documents cbntai n information which is vital as a competitive advantage to TE and woul~ be helpful *~o competiiors of TE. The di s*cl osure'i'0f the prop.rietary i nformati o~ contained in the Do~uments to a cqmpetjt_on would permit the competitor. to reduce its expenditure of money and*manpower and to impro~e its competitive.position by giving ~t valuable insights into the TE Qualificatfon,_Program.
- lt*would also result in substanti.al harm to the competitive P.Osi.ti on of TE.
8-. *Based o~_*my'_experi'ence, *~-do not_believe that the* background, data,.-and inc;entives of TE 1 s competitors.are suf'.iciently similar to the .
corre~ponding backgro~nd_,' data, and incehtiv*~*s of TE to reasonably expect such coinp~ti.tors to be in' a position to dupLicate TE 1 s proP,rietary informati on 1
contained-in the Documents without similar investments.
- 9. In accordanG_e with TE s policies_governing the protection 1
and control of information, -proprietary Tr:iform~tion contained in the Documents has been made ~vailable, on a_li~it~d basis, to other~ outside Tt only as required and under suitable agreement providing for noh-disclosure
-and 1imited use of the information.
TELEMECANIQUE INC., 2002 BETHEL ROAD, WE$TMINSTER, MD 21157; (301) 876-2214
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. lO.' -The Documents have been made avai.lable to the*u:s~* N-uclear*
Reguiat.ory Commiss{on in confidence, with the stipulation that the information contain-ed in the. Documents not be duplicated or djsclosed, in whole or in ;part, witho~t th~ ~xpress wrftten con~~nt of-telemeca~i~~e Inc~ -
- THAT the stateme~ts made hereinabove are, to the best-of.my
- knowledge, inforriiatfon., and belief, *truthful and complete ..
R.
- W. Jo DirectQ of.Operation~
.. Telemecanique Inc:
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SWORN TO AND SUBSCRIBED before me this a&~da~ of
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1987.
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"r.{oJARY* .PUBLIC My Commiss 1ori Expires: *
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- TELEMECANIQUE INC., 2002 BETHEL ROAD, WESTMINSTER, MD 21157, (301) 876-2214