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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 POWERiNii
/llllCHlliAN'S PRDliRESS General Offices: 1945 West Parnall Road, Jackson,° Ml 49201 * (517) 788-0550 October 30, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT - JANUARY THROUGH JUNE 1988 *~ CORRECTION Attached is the corrected Semiannual Radioactive Effluent Release and Waste Disposal Report for the Palisades Plant covering the period from January through June 1988.
- This submitt~l is.made in accordance with 10 CFR 50.36a and Technical Specifications 6.9.3.la. This correction includes Palisades LER 88-002 which was inadvertently omitted from the original August 31, 1988 submittal.
Also included with this report is supplemental information to the July through December 1987 Semiannual Radioactive Effluent Release Report.
Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment
( 8911080515 891030 I I PDR ADOCK 05000255\
R PNU OC1089-0214-NL04 A CM5 ENERGY COMPANY
ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT JANUARY THROUGH JUNE 1988 Revised l0/5/89
. I S911080516 891030 kDR , ADOCK- 05000255 PNU IC0888-0179A-HP01 1
\,,
REVISED Palisades Nuclear *Plant Semiannual Radioactive Effluent Release Report January - June 1988 This report provides information relating to radioactive effluent releases and*
.solid radioactive waste processing at the Palisades Nuclear Plant during the period of January through June 1988. The report format is detailed in Plant Technical Spe~ification 6.9.3.la. Palisades has been on-line during this*
reporting period since being returned to service Jan~ary 27, 1988.
- 1. Supplemental Information "A. Batch Releases Information relating to batch releases of gaseous and liquid effluents is provided in Table HP 10.S-l.
B. Abnormal Releases LER-PA1.88-002
. On February 9, 1988 at 1630 an Auxiliary Operator (AO) identified
.that the in-service waste gas decay tank (WCDT) T-68C [WE;TK] had lost approximately 26 psi. The gas from the WCDT was released ini;o I
I the Auxiliary Building [NF] and ultimately to the atmosphere via. the I monitored Plan~ stack. The gaseous release from the in-service tank is contrary to Technical Specification (TS) 3.24.6.1 which states, "the WCDT system shall be used to reduce radioactive.gaseous effluents by holding gaseous waste collected by the system for a minimum of 15 days up to 60 days".
During the event, 6.032 curies of noble gas as Xe-133 were released
.over a period totaling one hour._ The-release was averaged over.a , ___
one hour period resulting in an HPC fraction of 8.0E-3 at the site boundary. Thrs value is a small portion of the one maximum P.ermiss.ible concentration fraction allowed at the site boundary.
I I
The release was monitored by Plant stack radiation monitoring equipment. No alarms or annuni::iations were received in the Control I
Room due to the highest count rate seen being a factor of I approximately five below the alert alarm setpoint. Therefore, due to the insignificant dose consequence, no adverse effects were presented to the general public.
IC0888-0179A-HP01 2
- 2. Gaseous Effluents Table HP 10.5-2 lists and surrmarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was l.13E-06% of the total release.
- 3. Liguid Effluents Table HP 10.5-3 lists and summarizes all liquid radioactive effluents released during the reporting period. There was no unidentified beta released.
- 4. Solid Waste Solid radwaste classification, sources, volume shipped, curie and nuclide content are detailed in Table HP 10.5-4. All radwaste shipments were made to either Barnwell, South Carolina or Richland, Washington for burial.
- 5. Surmiary of Radiological Impact on Man Potential doses to individuals and populations were calculated using GASPAR and LADTAP computer program codes. The first and second quarter values for curies released were input for each nuclide and summarized as_
follows:
A. The maximum offsite air dose at the site boundary due to noble gases was 3.30E-02 millirad beta and l.llE-02 millirad ganma for the first quarter; and 4.72E-02 millirad beta and l.59E-02 millirad gamma for the second quarter.
B. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluents (tritium, particulates and iodine) was the infant thyroid. Doses were 9.0lE-03 and 8.24E-03 millirem for the first and second quarters, respectively.
C. Integrated total body doses to the general population and average doses to individual~ (adults) within the population from gaseous effluent releases within a distance of 50 miles from the site boundary were: l.73E-02 manRem and l.65E-05 millirem for the first quarter; and 2.12E-02 manRem and 2.02E-05 millirem for the second quarter.
D. The maximum total body dose to an individual (adult) in unrestricted water - related exposure pathways was 4.54E-03 and 2.67E-03 millirems for the first and second quarters, respectively. The maximum organ doses were 7.90E-03 millirem (teenage bone) for the first quarter and 4.42E-03 millirem (teenage liver) for the second quarter~_
IC0888-0179A-HP01 3
E. Integrated total body doses to the general population and average doses. to individuals (adults) within the population from liquid effluent releases within a distance of 50 miles from the site boundary were: l.63E-02 manRem and l.55E-05 millirem for the first quarter; and 1.02E-02 manRem and 9.71E-06 millirem for the second quarter.
F'. Both the Selenium-75 present in the gaseous effluent releases and the entrained noble gases present in the liquid releases (first and second quarters) were not significant in either wholebody*or organ doses.
- 6. Process Control Program (PCP).
There were no chang.es to the PCP during the reporting period.
- 7. Offsite Dose Calculation Manual (ODCM)
There were no changes to the ODCM during the reporting period.
- 8. Supplemental Information for the July-December 1987 Semiannual Radioactive Effluent Release Report The Palisades Nuclear Plant Semiannual Radioactive Effluent Release .
Report; July - December 1987, Tables HP 10.5-2 Gaseous Effluents and Tables HP 10 *. 5-3 Liquid Effluents are being submitted .as an attachment with the following revisions:
A. Table.HP 10.5-2,. Gaseous Effluents - Su1J111ation of Releases, items C.l. and_C.2., 4th Quarter only:
Change the Particulates with half-life > 8 days from 4.45E~04 Ci to 4.44E-04 Ci.
Change the average release rate for period from 5.60E-05 uCi/s~~ to 5.58E~05 uCi/sec.
B. Table HP 10.5-2, Gaseou~ Effluents (isotopic Ci li~tings),_it~m 3,
- Particulates~ 4th Quarter only:
Change Sr-89 from 4.SE-06 Ci to 2.6E-06 Ci Change Sr-90 from l.6E~06 Ci to 9.2E~07 Ci Change Net Unidentified Beta from 2.88E-04 Ci to 2.90E-04 Change particulate isotope total from 4.45E-04 Ci to 4.44E-04
- c. Table HP 10.5-3, Liquid Effluents - Swnma~ion of All Releases, items A.3. and D., 4th Quarter only:
Change the Percent.of MPC from 6.17E-02 to 5.86E-02 *.
Change the Gross Alpha ~adioactivity (Total Release) from 2.7E-05 to 8.2E-06.
IC0888-0179A-HP01 4
Change the gross alpha average diluted concentration during period from 8.9E-13 to 2.7E-13.
D. Table HP 10.5-3, Liquid Effluents (isotopic Ci listings), item 1.,
Nuclides Released, 4th Q~arter only:
Change Sr-89 from S.6E-06 Ci to 3.3E-P4 Ci Change Sr-90 from 6.lE-04 Ci to 4.3E-04 Ci Change Net Unidentified Beta fro~ 3.73E-03 Ci to 3.59E-03 ti E. In the Palisades July - December 1987 Semi-Annual Radioactive Effluent Release Repo~t Narrative, the following changes are also noted:
Item 2 - Gaseous Effluents: change from "the unidentified beta was 4.09E-OS%*of the total release" to "the unidentified beta was 4.lOE-05%" of the total release'~.
Item 3 - Liquid Effluents: change from "the unidentified beta ~as 4.60E-03% of the total release" to "the unidentified beta was 4.46E-03% of the total release".
Reasons fbr the above data revisions to the, Palisades Semi-Annual RaJio-acti ve Effluent Release Report, July - December* 1987 was that the calcu-lated Sr-89 and S~-90 reJease quantities (gaseous and liquid ~ffluents, 4th Quarter only) were based on estimated values for the months of .
November and December. Teledyne Isotopes Midwest Laboratory had not yet completed the actual sample analyses prior to the Technical Specification Semi-Annual Report due date. All data changes are indicated by "#" in the right-hand margins. There were no significant dose change~ to the public.
IC0888-0179A-HP01 5
\
TABLE HP 10. 5-1 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES JANUARY 1988 to JUNE 1988 A. GASEOUS Units I lst Quarter 2nd Quarter Number of Releases* I 14 18 I
Total Release Time i Minutes I 2.72E+03* 7.54E+03
! I Maximum Release Time* i Minutes I 3.41E+02 l.77E+03 Avera2e Release Time Minutes l. 94E+02 4.19E+02 Minimum Release Time I1 Minutes
. l.13E+02 9.00E+Ol B. LIQUID ! Units
- lst Quarter 2nd Quarter Number of Releases 20 16 I Total Release Time Minutes 4.37E+03 6. 71E+03 I Maximum Release Time Minutes 5.67E+02 I I 6.95E+02 I
I Avera2e Release Time Minutes 2.19E+02 4.20E+02 Minimum Release Time Minutes 4.90E+Ol 6.lOE+Ol IC0888-0179A-HPOi 5
TABLE HP 10. 5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACT[VE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES JANUARY 1988 to JUNE 1988 I Est Tot al :
A. FISSION AND ACTIVATION GASES UNITS lst QUARTER 2nd QUARTER;
l
- Total r"elease Ci 6.93E+02 9.91E+02 ii
- 2. Aver"a2e release rate for period uCi/ sec 8.81E+Ol l. 26E+02 I 7. 20
- 3. Percent of annual ava MPC % 4.20E-02 I 6.0lE-02 !
I B. IODINES '
- l. Total Iodine i Ci 3.81E-03 2. 75E-03
- 2. Averaae release rate for period
- I uCi/sec 4.21E-04 3.SOE-04 4.37* '
- 3. Percent of annual avg MPC * !
I % 4.llE-04 3.63E-04
- c. PARTICULATES !
- 1. Particulates with half-life > l 8 davs Ci l.27E-04 l.78E-05 i I
- 2. Averaae release rate for oeriod uCi/ sec l.62E-05 2.26E-06
- 3. Percent of annual ava limit MPC % l .09E-05 1. 90E-06 75 .1 **
i 4. Gross alpha radioactivity ! Ci 3.86E-06 5. 36E-06
- s. Gross alpha average release rate I I for period I uCi/Sec ; 4.91E-07 6.82E-07 j
I D. TRITIUM
! L Total release Ci 9.l8E-Ol 8.98E-Ol I 2. Averaae release rate for period I uCi I sec
- l.17E-Ol l.14E-Ol I 3. Percent of annual ava MPC I %* : 8. 36E-05 8 .14E-05
! E.
- 1. Beta air dose at site boundary due* I to Noble Gases (TS 3.24.5.2a)- mRads 3. 30E-02 4.72E-02
- 2. Percent limit % 3.30E-Ol 4.72E-Ol
- 3. Ganma air dose at site boundary due to Noble Ga*es (TS 3.24.5.21) mRads i l. llE-02 ! l.59E-02 I
I 4. .Percent li11i t I % i 2.22E-Ol I 3.18E-Ol F.
- 1. Maximum organ dose to public based I based on critical receptors (TS 3.24.5.3) mRem 9.0LE:-03 ! 8.24E-03
- 2. Percent of limit % l.20E-Ol I 1. lOE-01
- Note: Data is reported for I-131 and I-133 only.
- Note: Large error factor due to very small amount of particulates present in gaseous effluents.
IC0888-0l79A-HP01 6
TABLE HP 10.5-2.
PALISADES NUCLEAR PLANT SEMIANNUAL RADLOACTIVE
. EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS*
JANUARY 1988 to JUNE 1988 l* FI SS ION GASES ' Units I 1st QUARTER I 2nd QUARTER I I i Krvoton-85 Ci 7.90E-Ol i 4.24E-Ol '
I : i
! Krvoton-85m Ci l.16E-02 I S.79E-03 I
I i
i Krypton-87 Ci l.42E-02 2. 39E-03 * ,.
I Krvoton-88 Ci l.71E-02 5.96E-03 I! I j
Xenon-13lm Ci 2.13E-Ol 7.37E-02
! Xenon-133 Ci 6.92E+02 9.91E+02 .i j i Xenon-133m Ci l.91E-02 1. 92E-02 i
! I I i I Xenon-135 I. Ci 6.JOE-02 5. 95 E-02 i
I Xenon-135m I Ci 3.84E-02 8.49E-03 i Xenon-138 ' Ci 2.62E-02 3.olE-03 Argon-41 ; Ci 9.20E*04 I None Total for Period Ci 6.93E+02 9.92E+02
- 2. IODINES Iodine-131 Ci l.9 lE-03 l.7SE-03
- *. 1- --
Iodine-132 Ci None None Iodine 133 Ci l .40E-03 9. 96E-04 Iodine-135 Ci 5.04E-04 None I. !
Total for Period Ci I J.81E-03 I 2.75E-03 IC0888-0179A-HP01 7
TAB LE HP l 0 . 5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE
'EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS JANUARY 1988 to JUNE 1988
- 3. PARTICULATES
- Units l st QUARTER I 2nd QUARTER Chromiwn-51 i Ci None. None I
Man~anese-54 i Ci None I None Cobal t-58 Ci l.32E-05 None i
Cobalt-60 Ci 2.55E-06 4.64E-07 I Seleniwn-75 Ci 9.32E-05 1. 34E-05 I I
I I
Cesium-134 Ci ! None None !
I Cesiwn-137 ! Ci i l.08E-06 5.98E-07
! I Strontium-89 ** Ci I 6.3E-07 4. 5E-07 Stl"ontium-90 ** I Ci 3 .4E-07 2.4E-07 Net Unidentified !
Beta Ci l.64E-05 I 2.65E-06 I
I Total Ci l.27E-04 ! l.78E-05
- Note: Particulates with half-lives > 8 days.
- Note: Calculated from vendor analysis of monthly stack gas filters; 2nd quarter result includes data estimates for Hay and June due to unavailability of completed sample analyses. Reported net beta and vendor analyzed Sr~89/90 were input to GASPAR code as Sr-90 to yield conservative dose estimates.
IC0888-0l79A-HPOl 8
TABLE HP 10. 5-3 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES JANUARY 1988 to JUNE 1988 I
Est Total '
A. FISSION AND ACTIVATION PRODUCTS UNITS . 1st QUARTER 2nd QUARTER Et"ro t" %
- 1. Total l"elease (not* including tl"itium. !lases. al nha) Ci 7.JlE-03 4.23E-03 I
- 2. Average diluted concentt"ation dut"ina oeriod uCi/ml 2.56E-l0 ,* l.29E-10 14.4
- 3. Percent of MPC % 9.3SE-03 2.52E-03 B. TRITIUM
- l. Total l"elease Ci 3.49E+Ol 1. 07E+02
- 2. Average diluted concentration durimr oeriod uCi/ml l.22E-06 3. 28E-06 22.3
- 3. Percent of MPC % 4.07E-02 l. 09E-Ol
- c. DISSOLVED AND ENTRAINED CASES
- 1. Total Release Ci l.93E-03 7.SSE-02 '
I
- 2. Average diluted concentt"ation I dut"ina oeriod uC i I ml 6.75E-ll 2.31E-09 4.0*
- 3. Percent of MPC % 3.38E-OS l.16E-03 I D. CROSS ALPHA RADIOACTIVITY I (Total Release) ** Ci. 3.0E-06 2.SE-06
- l. Ct"oss alpha average diluted I concentration durina oeriod uCi/ml l.OE-13 7.6E-l4 E. VOLUME OF WASTE RELEASED (Prior to Dilu~ion) Liters 8.27E+05 F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 2.86E+l0 C. MAXIMUM DOSE COMMITMENT - WHOLEBODY mRem 4.S4E-03 2.67E-03 Percent of TS 3.24.4.la limit % 3 .03E-Ol l.78E-Ol H. MAXIMUM DOSECOHHITMENT - ORGAN mRem 7.90£-03 4.42E-03 Percent of TS 3.24.4.la limit % 1.58£-01 8.84E-02
- ~ Data is t"ep(>rted for Xe-133, Xe-l33m, Xe-135 and Kr-8Sm
- ~ Calculated from vendor analysis of monthly radwaste composite samples; 2nd quarter result includes data estimates for May and June due to unavailability of completed sample analyses.
IC0888-0179A-HP01 9
e.
TAB LE HP l 0
- PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS JANUARY 1988 to JUNE 1988
- 1. NU CL IDES RELEASED Un its l st OUARTER 2nd QUARTER I
I Cesi um-137 Ci 1. 71E-03 9.80E-04 !
Cobalt-58 Ci* 1. 30E-03 5.&0E-05 i Manaanese-54 Ci l.14E-04 2.03E-04 !
Cobal t-60 Ci 1. 38E-03 2.13E-03 I I
I Cesi um-134 Ci 1. 62E-04 l.21E-04 i Iodine-131 Ci 2.37E-05 None !
Strontium-89*** Ci 2.lE-03 5.9E-04 !
i Strontium-90**~ ' Ci 5.2E-04 1. 5 E-04*
Net Unidentified Beta ;
Ci None None Fission & Activation.
Product Total
- Ci 7.llE-03 4.23E-03 Noble Gases ' Ci l 1. 93E-03 7.55E-02 I
I I 3.49E+Ol L07E+02 Tritium Ci I Grand Total ' Ci .. i 3.49E+Ol l.07E+02
- NOTE: Calculated from vendor analysu of mont*hly radwaste composite samples; 2nd quarter result includes estimates for May and June due to unavailability of completed sample *analyses. Reported net beta and vendor analyzed Sr-89/90 were input to LADTAP code as Sr~90 to yield conservative dose estimates.
IC0888-0l79A-HPOl 10
TAB LE HP l 0 . S-4 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SOLID RADIOACTIVE WASTE JANUARY 1988 to JUNE 1988 Waste Source of Solidification Container Volume Total Principal Class Waste Agent Type (Cu.ft. ) Curies Radionuclides..:.-
A DAW N/A B-25 Box-LSA 1174 .o 3.1 H3 ,Mn-S4,Fe-55,Co-57, Co-58,Co-60,Ni-63 Cs-134,Cs-137,Sr-90, Tc-99, C-14,* I-129 A Evaporator Asphalt Metal drum 661.S 7.9 H3 ,Mn-54,Fe-55,Co-57, Bottoms co~58,co-60,Ni-63 Cs-134,Cs-137,Sr-90, Tc-99, C-14, I-129 Sb-125 B Irradiated N/A Steel liner l4.6 149.0 Mn-54,Fe-55,Sb-125, Hardware Co-58,Co-60,Ni-63 c Irradiated N/A Steel liner 14.6 1097.7 Mn-54,Fe-55,Sb-125 Hardware Co-58,Co-60,Ni-63 Total Shipped 1864. 7 1257.7
- NOTE: Ganma isotopes are measured quantities; all other isotopes are estimated.
IC0888-0l79A-HP01 11
Palisades Nuclear Plant Semiannual Radioactive Effluent Release R~port (Revised)
JULY - DECEMBER 1987 This report provides information relating to radioactive effluent releases and solid radioactive waste disposal operations of the Palisades Nuclear Plant during the period of July through December 1987~ The report format is detailed in Plant Technical Specification 6.9.3.la. During this reporting period, Palisades was off-line from October l - November 12, 1987 and December 4, 1987 - January 26, 1988 due to maintenance outages.
- 1. Supplemental Information A. Batch Releases Information relating to batch releases of gaseous and_ liquid effluents is provided in Table HP 10.5-1.
B. Abnormal Releases There were two (2) reportable incidents of abnormal gaseous r~leases from the Palisades Plant during the July - December 1987 reporting period. A brief description of each is provided:
- 1. *0n July 8, 1987, at approximately 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, the gaseous contents of Waste Gas Decay Tank. (WCDT) T-68A were accidentally released to the atmosphere without being held for a minimum of fifteen (15) days.* This was contrary to Palisades Technical Specification 3.24.6.l and resulted in an Event Report (E-PAL-87-029) to the NRC. Cause of the WCDT release was determined to be theperformance*of maintenance activity on the (then in-service) T-68A WGDT relief valve. Approximately 5.78 m3 of noble gas escaped from the WCDT into the Auxiliary Building. The noble gas was vented from the Auxiliary Building via the ventilation system and out the plant stack.. The release wa1 monitored by the stack. noble gas monitor (RIA 2326)
- and occurred over an approximate thirty (30) minute time period. The release totaled 0.224 curies and is included in the third quarter gaseous effluent totals. No release limits were exceeded. *
- 2. On October 19, 1987, at approximately 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />, the gaseous*
contents of Waste Gas Decay Tank. (WGDT) T-1018 were released to the atmosphere without being held for a minimum of fifteen (15) days. This was contrary to Palisades Technical Specification 3.24.6.1 and resulted in an Event Report (E-PAL-87-047) to the NRC. Cause of the unauthorized WCDT release was inattention to detail and procedure non-compliance. The activity of WCDT-1018 was known as it had been isolated and sampled prior to the release. No release limits were exceeded. A total of 7.20 IC0288-0022A-HP01 12
- ~6Rl 1080'519 891030 R ADOCK 05000255 PNU .
curies was released and is included in the fourth (~th) quarter gaseous effluent totals.
- 2.
- Gaseous Effluents Table HP 10.5-2 lists and su!Tlllarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was 4.lOE-05% of the total release. 4
- 3. Liquid Effluents Table HP 10.5-3 lists and surm1arizes all liquid radioactive.effluents released during the reporting peri9d. The unidentified beta was ii 4~46E-03% of the total release.
- 4. Solid Waste Solid radwaste classification, sources, volume shipped,. curie and *nuclide*,
content are detailed in Table HP 10. 5-4. AU radwaste *shipments were made to either Barnwell, South Carolina*or Richland, Washington for burial.
- 5. Sunmary of Radiological Impact on Han
- Potential doses to individua(~ and populations were calculated using GASPAR and LADTAP computer program codes. The third and fourth quarter values for curies released were input for each nuclide and summarized as follo.ws:
A. The maximum offsite air dose at the site boundary due. to noble gases was 2.62E-02 millirad beta and 8.SOE-03 millirad ganma for the third quarter; and 2.73E-02 millirads beta and 9.21E-03 millirads gamma for the fourth quarter.
B. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluents
{tritium, particulate and iodine) was the child bone. Doses were 6.63!-02 and 1.14E-Ol millirem for the third and fourth quarters, re1pectively.
C. The mazimum total body dose to individuals (adult) in unrestricted water-related exposure pathways was 4.38E-03 millirem for the third quarter and 5.86E-02 millirem for the fourth quarter. The maximum organ dose (teenage liver) was 7.83E-03 and 9.72E-02 millirem for the third and fourth quarters, respectively.
D. Integrated total body doses to the general population and average doses to individuals within the population from liquid effluent releases within a distance of 50 miles from the site boundary were:
l.48E-02 manRem and l.41E-05 millirem for the third quarter; and l.91E-Ol manRem and l.82E-04 mi 11 ;rem for the fourth quarter.
IC0288-0022A-HP01 13
E. Integrated total body doses to the general population and average doses to individuals (adults) within the population from gaseous effluent releases within a distance of 50 miles from the site boundary were: 3.34E-02 manRem and 3.18E-OS millirem for the third quarter; and 4.94E-02 manRem and 4.70E-OS millirem for the fourth quarter.
F. The.Selenium-75 in gaseous effluent releases (fourth quarter only) and* the entr~ined noble gases presen~ in both the third and fourth quarter liquid releases were not significant in either wholebody or organ doses.
- 6. Process Conti6l Program (PCP)
There are no changes to the PCP during this reporting period.
- 7. Offsite Dose Calculation Manual (ODCH)
There are no changes to the ODCH during this reporting period.
- 8. Supplemental Information for the January-June 1987 Semiannual Radioactive Effluent Release Report The Palisades Nuclear Plant Semiannual Radioactive Effluent Release Report; January - June 1987, Table HP 10.5-2 Gaseous Effluents and HP 10.5-3 Liquid Effluents are being submitted as an attachment for the following revisions:
A. Table HP 10.5-2, Gaseous Effluents - Su1J111ation of Releases, item C.3., 2nd Quarter only:
Change the Particulate P~rcent of Annuai Average Limit HPC from 2.62E-06 to 2.64E-O!.
B. Table HP 10.5-2, Gaseous Effluents (isotopic Ci listings), item 3, Particulates, 2nd Quart~r ~nly:
Change Sr-89 from J.2E-07 Ci to 5-.9E-07 ci-.---
Change Sr-90 from 2.8E-07 Ci *to 5.5E-07 Ci.
Chana* Net Unidentified Beta from 4.31E-05 Ci to 4.26E-05 Ci.
C. Table HP 10.5-3, Liquid Effluents
- Summation of Releases, item A.3., 2nd Qaurter only:
Change the Fission and Activation Cases Percent of HPC from 2.31E-02 to 2.19E-02.
IC0288-0022A-HP01 14
]1
- D. Table HP 10.5-3, Liquid Effluents (isotopic Ci Listings)i icem L, Nuc1ides Released, 2nd Quarter only:
Change Sr-89 from 5.4E-05 Ci to 2.6E-05 Ci.
Change Sr-90 from 9.lE-05 Ci to 5.5E-05 Ci.
Change Net Unidentified Beta from l.93E-03 Ci to l.99E-03 Ci.
Reasons for the above data revisions to the Palisades Nuclear Plant Semiannual Radioactive Effluent Release Report, January - June 1987 ~as that the calculated Sr-89 and Sr-90 release quantities (for both gaseous and liquid effluents) were based on estimated values for the mon~h of June. Teledyne Isotopes Midwest* Laboratory had not yet completed the actual sample analyses prior to the Techniql Specific.ation Semiannual report due date. All data changes are indicated by "#" in the right-hand margins. There were no reportable changes in doses to the pubiic.
IC0288-0022A-HP01 15
TABLE HP 10.5-2 e
(~evised)
PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES JULY 1987 to DECEMBER 1987
' Est Total i A. F'ISSION AND ACTIVATION GASES UNITS 3t'd QUARTER 4th QUARTER! En"OC' % i
- 1. total C"elease Ci 5.49E+02 5.70E+02 i I
- 2. Avet"aae release t'ate for period uCi/sec 6.89E+Ol 7.17E+Ol 24.0
- 3. Percent of annual av2 MPG % 3.29E-02 3.43E-02 i I I B. IODINES
- 1. Total Iodine Ci ! 5.49E-03 l .49E-02 I i
i
- 2. Averaae release rate for' Pet'iod
- uCi/ sec I 6. 90E-04 l .88E-03 4. 66* i
- 3. Percent of annual av2 MPG * % I 7.71E-04 2.59E-03 I
- c. PAR TI CLTT .ATES
- 1. Particulates with half-life >
8 davs Ci l.80E-04 4.44E-04
- 2. Averaae release rate for Period uCi/sec 2.26E-05 5.58E-05
- 3. Percent of annual av2 1 imit MPC % l.OJE-04 l. 76E-04 20.8**
. 4. Gross alpha radioactivity . Ci 6.lSE-06 6.40E-06
- 5. Gross alpha average release rate for period I uCi/Sec 7. 74E-07 8.0SE-07 :
iI D. TRITIUM l
- Total C"elease Ci 8.25E-Ol 7.56E-Ol I
- 2. Averaae release rate for period uCi/sec l.04E-Ol 9.SlE-02 I
- 3. Percent of annual ava MPC % 7.41E-05 6.79E-05 I i
E.
- l. Beta *ai.r dose at site boundary due to Noble Gases (TS 3.24.5.2a) mRads 2.62E-02 2. 73E-02 .
- 2. -Percent limit % 2.62E-Ol 2. 73E-Ol-
- 3. Gamma air doae at site boundary due to Noble Ga*** (TS 3.24.5.21) - mRads 8.SOE-03 9.21E-03 l.84E-Ol
- 4. Percent li*it I % l.76E-Ol F.
- 1. Maximum organ dose to public based :
based on critical receptors (TS 3.24.5.3) mRem 6.63E-02 l.14E-O 1-
- 2. Percent of limit % 8.84E-Ol l.52EOO Data is reported for I~l31 and I-133 only.
Large error factor due to very small amount of particulates present in gaseous effluents.
IC0288-0022A-HP01 16
TABLE HP 10.5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Revised)
GASEOUS EFFLUENTS JULY 1987 to DECEMBER 1987
- 3. PARTICULATES**
- I Units * : 3rd QUARTER 4th QUARTER I
I Ch r-omi um-5 1 Ci I None None Han2anese-54 Ci I None None Cobalt-SB Ci None 6. 77E-OS Cabal t-60 Ci 7.44E-06 6.48E-06 Selenium-75 Ci None 6.56E-OS i
Niobium-95 Ci None 1. iOE-06 Cesium-134 Ci None None '
Cesium-137 Ci None 9.35E-06 I
Strontium-89**** ! Ci 1. 7E-06 2.6E-06 #
II i
St ront ium-90***'*
- Ci 4. lE-07 ! 9.2E-07 Net unidentified I I
beta Ci 1. 70E-04 2. 90E-04 Total Ci I l.BOE-04 ! 4.44E-04 I
- NOTE: Particulates with half-lives >8 days.
- NOTE: Calculated from vendor analysis of monthly stack gas filters.
Reported net beta and vendor analyzed Sr89/90 results were input to CASPAR code as Sr~90 to yield conservative dose estimates.
IC0288-0022A-HP01 17
TABLE riP l0.5-J PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Revised)
LIQUID EFFLUENTS - SUHHAT ION OF ALL RELEASES JULY 1987 to DECEMBER 1987
! Est Total
. A. FISSION AND ACTIVATION PRODUCTS I UNITS 3rd QUARTER 4th QUARTER: Error %
- l. Total release (not including i tritium. aases. aloha) :
Ci 8.80E-03 6.88E-02
- 2. Average diluted concentration i durina oeriod uCi /ml 2.62E-10 I 2.27E-09 ; 15
- 3. Percent of MPC % 1. 06E-02 5.86E-02 I
- 8. TRITIUM i
- l. Total release i Ci S.73E+Ol 4.47E+Ol
- 2. Average.diluted concentration durinll oeriod uCi/ml 1. 71E-06 l .4 7E-06 . 16
- 3. Percent of MPC % 5.68E-02 4.92E-02
- c. DISSOLVED AND ENTRAINED CASES !
- 1. Total Release Ci 7.97E-02 3.76E-02
- 2. Average diluted concentration durina oeriod uCi/ml 2.37E-09 l.24E-09 5.6*
- 3. Percent of MPC % l.19E*03 6.20E-04 D. CROSS ALPHA RADIOACTIVITY I (Total Release) ** Ci 2.6E-05 8.2E-06 I 1
- Gross alpha average diluted concentration durina oeriod uCi/ml 7.7E-13 2.7E-l3 I
. E. VOLUME OF WASTE RELEASED ..
(Prior to Dilution) Liters 9.55E+05 l.40E+06 F. VOLUME OF DILtrrION WAT!I USED DURING
. PERIOD Liters 3.36E+l0 3.03E+l0 G. MAXIMUM DOS! COtltITMIHT - WHOLEBODY mRem 4.38E-03 5 .86E-02
- Percent of TS 3.24.4.la limit % 2. 92E-Ol 3.91EOO H. MAXIMUM DOSE COMMITMENT - ORGAN miem 7 .83!-03 9.72E-02 Percent of TS 3.24.4.la limit % l.57E-Ol l.94EOO
- ~ Data is reported for Xe-133
- ~ Calculated from vendor analysis of monthly radvaate composite samples.
IC0288-0022A-HP01 18
\
v, *
.PALISADES NUC~EAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Revised)
LIQUID EFFLUENTS JULY 1987 to DECEMBER 1987 I l. NUCLIDES RELEASED I Units ! 3rd QUARTER 4th QUARTER
- I Ces ium-13 7 ;
Ci I l.6SE-03 I 2.20E-02 Cobalt-58 Ci I 9.85E-05 l. 77E-03
\
Manaanese-54 Ci I 5.62E-04 9. 70E-03 Cobalt-60 Ci 4<39E:..03 2.42E-02 Cesium-134 Ci 2.46E-04
Rubidium-88 Ci 8.58E-04 None i Molvbdenum-99 Ci None* !
2.95E-05
~
Stronti um-89*** Ci 7 .2E-06 3.JE-04 :
I i
Strontium-90*** Ci I!
8 .SE-06
I Cobalt 57 Ci I None l. l3E-05 I
Antimonv-125 Ci
!i None 1. 90E-04 Iodine-131 Ci I
I od ine-133 Ci 2.49E-06 None Chromium-51 Ci None 1. 04E-04 I1
Beta Ci 9.72E-04 3.59E-o3*
I Fission & Activa.tion Product Total (Above) Ci 8.80!-03 6.88E-.02 ...
I I Noble Gases Ci 7.97!-02 3.76E-02 I
I Tritium Ci 5.73E+Ol 4.47E+Ol Grand Total Ci
- NOTE: Calculated from vendor analysis of mon~hly radwaste composite samples:
Reported net beta and vendor analyzed Sr89/90 results were input to
~TAP dose as Sr-90 to yield conservative dose estimates.
IC0288-0022A-HP0l 19