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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 company General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * {517) 788-0550 December 28, 1984
- Director, Nuclear Reactor Regulation US Nuclear Regulatory Connnission Washington, DC 20SSS DOCKET S0-2SS - LICENSE DPR PALISADES PLANT - FIRE PROTECTION - COMPLIANCE - 10 CFR S0.48 AND APPENDIX R TO 10 CFR SO - REVISION S Consumers Power Company and NRC staff representatives participated in a conference call October S, 1984, concerning our exemption request for instrument separation inside containment (Attachment 14, July 16 1984 submittal). The purpose of this submittal is to provide supplementary information requested by the NRC Staff. In addition, revisions have been made to fire-protection-related information as follows:
Attachment 1, "Appendix R Review Process" is revised to address Consumers Power Company's understanding of allowable manual operator actions in the fire area where the fire started. A detailed description of manual*
operator actions which may be needed after a fire will be submitted in a subsequent letter.
Appendix A of Attachment 1, "Illustrations, Appendix R Review Process" is hereby submitted as an Appendix to Attachment 1. (Formally, this informa-
. tion was included in Attachment 1.)
Attachment 14, "Exemption Request - Section III. G. 2 of Appendix R to 10 CFR SO, Instrument Separation Inside Containment is revised to provide supplementary information requested by NRC Staff.
L?~~
Brian D Johnson ,- B50i02033Ef8.lff22B \*I*'I Staff Licensing Engineer 1 PDR ADOCK 05000255 I'
\ F PDR. lJ CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades OC1184-0002-NL02
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consume11 Power company General Offices: 1945 West Pernell Road, Jackson, Ml 49201
- 1517) 788-0550 December 28, 1984 Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - FIRE PROTECTION - COMPLIANCE - 10 CFR 50.48 AND APPENDIX R TO 10 CFR 50 - REVISION 5 Consumers Power Company and NRC staff representatives participated in a conference call October 5, 1984, concerning our exemption request for instrument separation inside containment (Attachment 14, July 16 1984 submittal). The pµrpose of this submittal is to provide supplementary information .requested by th~ NRC Staff. In addition, revisions have been made to fire-protection-related information as follows:
Attachment 1, "Appendix R Review Process" is revised to address Consumers Power Company's understanding of allowable manual operator actions in the fire area where the fire started. A detailed description of manual operator actions which may be needed after a fire will be submitted in a subsequent letter.
Appendix A of Attachment 1, "Illustrations, Appendix R Review Process" is hereby submitted as an Appendix to Attachment 1. (Formally, this informa-tion was included in Attachnient 1.)
Attachment 14, "Exemption Request - Section III.G.2 of Appendix R to 10 CFR 50., Instrument Separation Inside Containment" is revised to provide supplementary information requested by NRC Staff.
Brian D Johnson (signed)
Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, *USNRC NRC Resident Inspector - Palisades OC1184-0002-NL02
l
~
Director, NRR Palisades Plant FIRE PROTECTION REV 5
- 2 December 28, 1984 Attachments OC1184-0002-NL02
FIRE PROTECTION - EXEMPTION REQUESTS AND MODIFIED COMMITMENTS - REVISION 5 INDEX FOR ATTACHMENTS December 28, 1984 NRC NEW INFORMATION APPROVAL THIS SUBMITTAL ATTACHMENT STATUS (YES/NO) TITLE 1 N/A YES APPENDIX R REVIEW PROCESS (Original Submittal April 23, 1984 - Rev 1 July 16, 1984 -
- Rev 2 August 10, 1984 Rev 3, December 28, 1984)
Appendix A N/A YES ILLUSTRATIONS, APPENDIX R REVIEW PROCESS of Attach I (Original Submittal December 28, I984) 1 IA OPEN Nb ESSENTIAL EQUIPMENT FOR SAFE SHUTDOWN POST-FIRE (Original Submittal August 10, I984) lB N/A NO FIRE AREA IDENTIFICATION, AUTOMATIC FIRE SUPPRESSION COVERAGE, AND FIRE DETECTOR COVERAGE (Original Submittal July 16, I984 - Rev 1 August IO, I984)
IC N/A NO EMERGENCY LIGHTING (Origin~! Submittal, July I6, I984) 2 N/A NO MODIFICATIONS TO PREVIOUS FIRE PROTECTION COMMITMENTS (Original Submittal April 23, 1984 - Revision I July 16, 1984 Rev 2 August 10, 1984) 3 OPEN NO EXEMPTION REQUEST - SECTION III.G.2 OF APPENDIX R TO IO CFR 50 SERVICE WATER PUMP SEPARATION IN INTAKE STRUCTURE (Original Submittal April 23, I984 - Revision I July I6, I984) 4 OPEN NO EXEMPTION REQUEST - SECTION III.G.2 OF APPENDIX R TO IO CFR 50 ENGINEERED SAFEGUARDS AREA (Original Submittal April 23, 1984 - Revision 1 July I6, 1984) 5 OPEN NO EXEMPTION REQUEST ~ SECTION III.G.2 OF APPENDIX R TO 10 CFR 50 RATED BARRIERS (Original Submittal April 23, 1984 - Revision I July I6, I984)
Appendix A N/A NO TEST REPORTS WHICH SUBSTANTIATE ATTACHMENT 5 - ITEMS a,b,c and d Of Attach 5 (Orig1-nal Submittal July I6, I 984)
I 1
FIRE PROTECTION - EXEMPTION REQUESTS AND MODIFIED COMMITMENTS - REVISION 5 INDEX FOR ATTACHMENTS December 28, 1984 NRC NEW INFORMATION APPROVAL THIS SUBMITTAL ATTACHMENT STATUS YES/NO TITLE 6 OPEN NO EXEMPTION REQUEST - SECTION III.G.2 OF APPENDIX R TO 10 CFR 50 COMPONENT COOLING WATER ROOM (Original Submittal April 23, 1984 - Revision 1 July 16, 1984) 7 OPEN NO EXEMPTION REQUEST - SECTION III.G.2 AND III.G.3 OF APPENDIX R TO 10 CFR 50 - CHARGING PUMPS P-55B AND P-55C (Original Submittal April 23, 1984 - Revision 1 July 16, 1984) 8 OPEN NO
SUMMARY
, PLANT MODIFICATIONS RESULTING FROM "APPENDIX R SELF-AUDIT" (Original Submittal April 23, 1984 - Revision 1 July 16, 1984) 9 OPEN NO EXEMPTION REQUEST - SECTION III.G.3 OF APPENDIX R TO 10 CFR 50 ENGINEERED SAFEGUARDS PANEL ROOM (Original Submittal July 25, 1983 - Revision 1 July 16, 1984) 10 OPEN NO EXEMPTION REQUEST - SECTION III.G.3 OF APPENDIX R TO 10 CFR 50 CORRIDOR BETWEEN CHARGING PUMP ROOM AND SWITCHGEAR ROOM lC (Original Submittal July 25, 1983 - Revision 1 July 16, 1984) 11 Approved NO EXEMPTION REQUEST - SECTION III.G.3 OF APPENDIX R TO 2/8/83 10 CFR 50 CONTROL ROOM (Original Submittal July 1, 1982 - Revision 1 July 16, 1984) 12 Withdrawn NO EXEMPTION REQUEST - SECTION III.G.l.a OF APPENDIX R TO 4/23/84 10 CFR 50 REPAIR PROCEDURE HOT SHUTDOWN INSTRUMENTATION (Original Submittal December 6, 1982 - Revision 1 July 16, 1984) 13 OPEN NO EXEMPTION REQUEST - SECTION III.L.4 OF APPENDIX R TO 10 CFR 50 LOCAL TENDING OF EMERGENCY DIESEL GENERATORS (Original Submittal August 10, 1984)
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/;
FIRE PROTECTION - EXEMPTION REQUESTS AND MODIFIED COMMITMENTS - REVISION 5 INDEX FOR ATTACHMENTS December 28, 1984 NRC NEW INFORMATION APPROVAL THIS SUBMITTAL ATTACHMENT STATUS YES/NO TITLE 14 OPEN YES EXEMPTION REQUEST - SECTION III.G.2 OF APPENDIX R TO 10 CFR 50 INSTRUMENT SEPARATION INSIDE CONTAINMENT (Original Submittal July 16, 1984 - Rev 1 December 28, 1984) 15 OPEN NO EXEMPTION REQUEST - SECTION III.G.2 OF APPENDIX R TO 10 CFR 50 CABLE SEPARATION INSIDE CONTAINMENT (Original Submittal July 20, 1984)
T"'T"of'\ I 0 I. """ 1 T 'J.TT "'l
ATTACHMENT 1 Consumers Power Company Palisades Plant - Docket 255 EXEMPTION REQUEST - SECTION III.G.2 OF APPENDIX R TO 10 CFR 50 INSTRUMENT SEPARATION INSIDE CONTAINMENT Original Submittal - July 16, 1984 Revision 1 - December 28, 1984 Revision 2 - August 10, 1984 Revision 3 - December 28, 1984 2 Pages FP0484-0001C-NL02
ATTACHMENT 1 APPENDIX R REVIEW PROCESS REVIEW PROCESS The review process included the following steps:
- a. Develop a comprehensive understanding of Appendix R to 10 CFR 50.
Our understanding of Appendix R requirements is illustrated by Attachment 1 of our January 18, 1984 submittal. This understanding is supplemented by the following:
0 Cable Separation - Cold Shutdown Engineering judgement and analysis may be used to demonstrate that one train of cold shutdown equipment is free of fire damage (i.e. it is conservative but overly restrictive to apply Appendix R,Section III.G.2 separation criteria to cold shut-down eq~ipment). (NRC Staff Guidance, April 24, 1984 meeting, Bethesda, Maryland.)
0 Manual Operator Actions in Fire Area of Concern In order to demonstrate safe shutdown capability, it is accept-able to rely on manual operator actions in the fire area of concern (e.g., room where fire initiated) provided the plant will not reach an unsafe or unrecoverable condition (i.e., if it can be demonstrated that sufficient time exists to detect fire, extinguish fire, and manually operate equipment prior to reaching an unsafe or unrecoverable plant condition, then such operator actions are consistent with Appendix R requirements.)
(Conference call Mr TV Wambach (NRC) and Mr L W Bauer (CPCO).)
- b. Identify rooms, barriers and penetrations in the plant. This process is illustrated by Appendix A, Figure 1. Figure 1 presents a hypothetical floor plan identifying rooms, barriers and penetra-tions.
- c. Define fire area (per Generic Letter 83-33, October 19, 1983). This process is illustrated by Appendix A, Figure 2. Rooms which are not separated by adequate fire barriers are considered to be "connected." A fire area is defined to be the set of interconnected rooms.
- d. Identify systems/trains/equipment necessary to perform each safety function described in Section III.L. of Appendix R to 10 CFR 50.
(The safety functions are: reactivity control, inventory control, heat removal, and process monitoring.) This process is illustrated by Appendix A, Figure 3. Figure 3 identifies a hypothetical functional group of equipment required to borate the primary coolant system. Each functional group of equipment belongs to a given "train."
FP 1184-0001-NL02
ATTACHMENT 1 APPENDIX R REVIEW PROCESS
- e. Document the location and cable route for each piece of equipment considered in the review. This process is illustrated by Appendix A, Figures 4A and 4B. Figure 4A is a hypothetical equipment location and cable route drawing. Figure 4B presents the Figure 4A informa-tion in tabular form.
- f. Evaluate cable separation. This process is illustrated by Appendix A, Figures S, SA and SB. Figure S demonstrates a flow chart for identifying potential common mode failures of redundant trains of equipment. Figures SA and SB illustrate how to determine if a train of equipment is potentially subject to fire damage. In the example provided, train "A" and train "B" each have equipment in the same fire area and therefore cannot be considered redundant systems in accordance with 10CFRSO, Appendix R requirements.
DIFFERENCES FROM APPENDIX R Differences exist between the protective measures prescribed by Appendix R and the protective measures available at Palisades Plant. Resolution is sought for each such difference. The methods used to resolve differences are:
- a. Modify the plant to ensure strict compliance with Appendix R.
Submit schedule exemption request where justified.
- b. Modify the plant to the extent necessary to ensure adequate protec-tion is provided which meets the intent of Appendix R. Submit technical exemption request and, where justified, submit schedule exemption request.
- c. Demonstrate that adequate protection is available which meets the intent of Appendix*R. Submit technical exemption request.
Plan modifications which are a direct result of Appendix R compliance are described in Attachment 8. Technical exemption requests are provided in Attachments as identified in the attachment index.
FP1184-0001-NL02
APPENDIX A OF ATTACHMENT 1 Consumers Power Company Palisades Plant - Docket 50-255 ILLUSTRATIONS, APPENDIX R REVIEW PROCESS Original Submittal - December 28, 1984 8 Pages FP0484-0001X-NL02
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ATTACHMENT 14 Consumers Power Company Palisades Plant - Docket 255 EXEMPTION REQUEST - SECTION III.G.2 OF APPENDIX R TO 10 CFR 50 INSTRUMENT SEPARATION INSIDE CONTAINMENT Original Submittal -July 16, 1984 Revision 1 -December 28, 1984 3 Pages FP0484-0001C-NL02
ATTACHMENT 14 EXEMPTION REQUEST - SECTION III G.2 OF APPENDIX R TO 10 CFR 50 INSTRUMENT SEPARATION INSIDE CONTAINMENT Approval Status NRC review ih progress.
Equipment Under Consideration Steam Generator "A" Pressure (PT-0751A,B,C & D); Steam Generator "B" Pressure (PT-0752A,B,C & D);
Pressurizer Level (LT-OlOlA,B, LT-0102A,B,C & D, LT-0103, LT-0105);
Pressurizer Pressure (PT-0101A,B, PT-0102A,B,C & D, PT-0103);
(Reference Drawings: E-350, E-382 detail C).
Safety Function(s) Of Equipment Process monitoring for steam generator and pressurizer.
Exemption Request III.G.2.d of Appendix R to 10 CFR 50 to the extent that redundant instrumen-tation is required to be separated by a minimum of 20 feet.
Necessary Plant Modification None Justification For Exemption Request A. The room is oddly shaped with a 13~ foot high ceiling extending up to 34 feet in the area of the staircase. Totai volume is approximately 14,420 cubic feet~ The walls, floor and ceiling are constructed of poured, reinforced concrete. The room is on the 590' elevation of containment.
The northeast corner contains a metal staircase which goes up only. There are two unrated, but substantial, steel doors in the room that lead to other areas of containment. The room is well ventilated by natural circulation supplemented by forced circulation (i.e. HVAC).
The room's construction provides a massive heat sink that would absorb the heat from a fire. The ventilation would dissipate the heat quickly.
The instruments of concern are located on the east wall opposite the 480V pressurizer heater load centers. The instruments are listed above.
Equipment locations are shown in the attached drawing (E-382 detail C).
B. The instruments have steel or aluminum cases and all wiring to them is run in conduit from cable trays. The casings and conduit effectively act as a radiant energy shield. The case is a hollow steel or aluminum shell which covers, but does not directly touch, the sensing device.
FP1084-0001-NL02 4
Exemption Request
- 2 A radiant energy shield is a noncombustible material which blocks the path of radiant energy from the fire to the instrument of concern. The cases are made of steel or aluminum and conduit are made of steel and thus noncombustible. The cases and conduit surround the instruments and cable thus blocking radiant energy from reaching them. The instruments are LOCA qualified. This qualfication provides added assurance that the instruments can operate under harsh environmental conditions (e.g. high temperature, high humidity).
C. This room is in cont~inment. Access is severely limited. During operation, personnel entering containment they wear full Anti-C's and Self Contained Breathing Apparatus. They dress and undress outside of containment. There are no "step-off" pads and no discarded Anti-C's inside of containment during operation. Everything is stored or discarded outside of containment when the plant is operating.
Smoking is strictly prohibited in containment during plant operation by Administrative Procedures 7.03. In fact, it is impossible because of the self contained breathing apparatus worn by personnel. Flammable liquids are not brought into containment during operation because they are not needed for anything.
D. Combustible loading in this room is light, consisting of small amounts of cable in trays. The trays and cables are located above the instruments.
There are no combustibles at the floor level. Heat and smoke from an in-situ fire would be above the instruments. There are no transient sources of ignition.
E. Strict administrative controls dictate that all loose material be removed from containment prior to startup to prevent containment sump plugging and transient fires. Administrative Procedure Number 4.04, Revision 0, "Plant Housekeeping" states "Prior to startup following any significant mainten-ance work, the containment building shall be given a thorough inspection for any unnecessary debris which could wash into the containment sump and plug the recirculation path during post-LOCA conditions. Particular attention should be given to the 590 1 level. In addition, material which could pose a fire threat shall be removed."
Two other procedures also assure that there are no transient combustibles in containment. They are:
- 1. Operations Checklist 1.3 Revision 4, "250 Pound Heat-Up Checklist, Containment Building" states "Complete a walk through of the contain-ment building to ensure that transient combustibles and/or flammable materials have been removed."
- 2. Fire Protection Implementing Procedure Number 7 Revision 3 "Fire Prevention Activities" states "Combustible materials shall be removed as soon as possible after use to keep the amount of combustibles as low as possible." It also states "The person responsible for the work activity in a safety related area shall assure the removal of all waste, debris, scrap, rags, oil spills or other combustibles resulting FP1084-0001-NL02 4
Exemption Request
- 3 from the work activity, or at the end of each work shift, whichever is sooner." Since the containment building is a safety related area, the procedure applies to work activities in the containment building.
Thus, three procedures assure that there are no transient combustibles in the air room during operation. There are no sources of ignition in the air room. Therefore, a transient combustible fire is virtually impossible in the air room.
F. Smoke detectors are installed in the room and alarm automatically in the control room. A fire hose is readily available to the room. Portable fire extinguishers are also readily available. The fire brigade will respond immediately upon receipt of the alarm.
G. Consumers Power Company concludes, based on the reasons above that a transient fire in the air room will not occur and the present arrangement of the instruments in the containment air room is adequate that an exemption from the requirements of Appendix R, section III.G.,should be granted.
FP1084-0001-NL02