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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
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- A CMS Energy Company Palisades Nuclear Plant Tel: 616 764 2276 27780 Blue Star Memorial Highway Fax: 616 764 2490 Covert, Ml 49043 Nathan L. Haskell Director, Licensing January 8, 1999 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT 10 CFR 50.46 REPORT OF CHANGES AND ERRORS IN LBLOCA ECCS EVALUATION MODEL Per 10 CFR 50.46 (a)(3)(ii), a report of changes to or errors discovered in Emergency Core Cooling System (ECCS) evaluation models which are deemed to be significant is due to the NRC within 30 days of discovery. As defined in 10 CFR 50.46(a)(3)(i), a significant change or error is one which results in a calculated peak cladding temperature different by more than 50°F from the temperature calculated for the limiting transient using the last acceptable model, or is a cumulation of changes and errors such that the sum of the absolute magnitudes of the respective temperature changes is greater than 50°F. The purpose of this letter is to report a significant cumulation of changes and errors in the Palisades fuel cycle 14 Large Break Loss of Coolant Accident (LBLOCA) Eccs* evaluation performed by Siemens Powe( * - * *-
- Corporation (SPC). Further, this letter outlines the current schedule for re-analysis of .
the Palisades LBLOCA transient by SPC.
As previously reported to NRC in Reference 1, the current (fuel cycle 14) LBLOCA ECCS evaluation for Palisades resulted in a peak cladding temperature (PCT) of 1869°F. This result was based on the currently approved EXEM/PWR LBLOCA evaluation model, as modified by the interim fuel cooling testing facility (FCTF) correlation. Also as reported in Reference 1, a significant "excessive variability" error existed, which when corrected resulted in a reduction in PCT of 70°F.
ri.
2 Ten additional errors associated with the SPC EXEM/PWR LBLOCA evaluation model have been identified by SPC. The impact of each individual error on the PCT has been evaluated for Palisades fuel cycle 14 using the SPC EXEM/PWR evaluation model with the "excessive variability" error corrected. A description of each error along with its individual evaluation of the change in PCT may be found in Attachment 1. The sum of the absolute magnitudes of delta PCT introduced by these ten errors is 63°F, which is considered significant per 10 CFR 50.46. However, the licensing basis LBLOCA PCT of 1869°F continues to be conservative relative to the SPC EXEM/PWR evaluation model results corrected for "excessive variability" and the ten errors detailed in .
SPC currently plans to perform a complete re-analysis of the LBLOCA event for Palisades upon completion of the SEM/PWR-98 ECCS evaluation model review currently ongoing by NRC. The current schedule is for completion of an updated Palisades licensing basis calculation utilizing the SEM/PWR-98 ECCS evaluation model by the end of the second quarter of 1999. Until such time as this new LBLOCA evaluation is in place, SPC will continue to use the EXEM/PWR LBLOCA model, modified by the interim FCTF correlation, to perform plant analyses for Palisades.
References
- 1. Letter, NLHaskell (Consumers Energy) to Document Control Desk (NRC),
"Evaluation of 10 CFR Part 21 Report Regarding Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results", dated June 1, 1998.
- 2. Letter, JFMallay (SPC) to Document Control Desk (NRC), "Interim Report of Evaluation of a Deviation Pursuant to 10 CFR 21.21 (a)(2)", SPC Letter Number NRC:98:063, dated September 21, 1998. *
SUMMARY
OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments.
athan L. Haskell Director, Licensing Administrator, Region Ill, USNRC Project Manager, NRR, USNRC NRC Resident Inspector - Palisades Attachment
ATTACHMENT 1 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 10 CFR 50.46 REPORT OF CHANGES AND ERRORS IN LBLOCA ECCS EVALUATION MODEL 3 Pages
10 CFR 50.46 REPORT OF CHANGES AND ERRORS IN LBLOCA ECCS EVALUATION MODEL RELAP4 Decay Heat Re-normalization (SPC CR#6578)
An error was discovered in the re-normalization of the decay heat in RELAP4 at the initiation of the transient. The re-normalization incorrectly adjusted the fission product decay heat by slightly less than the required 1.2 multiplier on the RELAP4 decay heat equations. The actinides are still conservatively estimated but not by a factor as great as 1.2. The peak cladding temperature (PCT) impact of this deviation was determined to be +18°F for Palisades.
RELAP4 Average Temperature (SPC CR#6581)
An error was discovered in the calculation of the fuel average temperature in RELAP4. The fuel average temperature in RELAP4 is incorrectly computed because one-half of the volume of the first gap node is used in calculating the fuel volume. The PCT impact of this deviation was determined to be -3 ° F for Palisades.
TOODEE2 Cold Gap Width (SPC CR#6574)
An error was discovered in the calculation of the gap dimensions in RODEX2.
The deviation was that the gap dimension TOODEE2 input was calculated at zero power hot standby conditions rather than at cold conditions. The PCT impact of this deviation was determined to be +2°F for Palisades.
RDX2LSE Gadolinia Conductivity (SPC CR#6419)
An error was discovered in the RDX2LSE (RODEX2) code used to provide fuel rod input for the PWR LOCA analyses. The error was that the gadolinia-bearing fuel conductivity equation described in XN-NF-85-92(P)(A), and approved by the NRC, was not incorporated in the code. The previous gadolinia-bearing fuel
. conductivity equation, described in XN-NF-79-56(P)(A), was not replaced upon the approval of the gadolinia-bearing fuel conductivity equation described in XN-NF-85-92(P)(A). The impact of incorporating the currently approved gadolinia-bearing fuel conductivity equation in the RDX2LSE code is to significantly reduce the calculated PCT for the gadolinia-bearing fuel rods during the LBLOCA.
Since the gadolinia fuel rods are not limiting, this reduction in gadolinia-bearing fuel rod PCT has no impact on the limiting PCT. Thus, the PCT impact of this deviation was determined to be 0°F for Palisades.
1
10 CFR 50.46 REPORT OF CHANGES AND ERRORS IN LBLOCA ECCS EVALUATION MODEL RDX2LSE Fuel Density (SPC CR#6655)
An error was discovered in the asymptotic fuel density (SWMDEN) used in the RDX2LSE (RODEX2) code. The SWMDEN value was not reflective of the current manufacturing process. SWMDEN is a RODEX2 input defined as the asymptotic fuel density that occurs after full densification and full accommodation of the solid swelling by the as-fabricated fuel porosity. The value of SWMDEN is determined by the processes employed during fuel manufacturing. The PCT impact of this deviation was determined to be +4 °F for Palisades.
PREFILL Negative SI Flow Rates (SPC CR#6809)
An error was discovered in the PREFILL sub-code of the RFPAC calculation.
The RFPAC code calculated negative values of LPSI and HPSI combined flow rates when there was a time gap between termination of accumulator flow and initiation of LPSI flow. The error has only been found to occur when the time gap is sufficient for the cold leg liquid to fall below 10% full. The PCT impact of this deviation was determined to be 0°F for Palisades.
TOODEE2 Axial Nodalization (SPC CR#6580)
An error was discovered regarding the calculation of an unrealistically high PCT in the region at the upper extremity of the core when 3-inch axial nodes are modeled in TOODEE2 in the upper extremity of the core (Reference 2). The current Palisades licensing analyses use greater than 3-inch nodes to model the upper extremity of the core. The unrealistically high PCT is caused by the fact that the FCTF heat transfer correlation predicts unrealistically low heat transfer coefficient above the 10.5-foot elevation. This behavior is phenomenologically unrealistic, however, the additional testing required to correct this deviation is not feasible within a reasonable time period. Therefore, to assure that a bounding PCT is calculated, an increased nodalization will be used at the top of the core .
. The PCT impact of this deviation was determined to be +25°F for Palisades.
RDX2LSE Incorrect Gadolinia Density (SPC CR#6442)
An error was discovered in the RDX2LSE (RODEX2) code used to provide fuel rod input for the PWR LOCA analyses. The error was that the gadolinia-bearing fuel rod fuel density correlation has been incorrect. Calculations with a developmental version of RDX2LSE indicate that the initial stored energy for the gadolinia fuel rods is a few degrees lower with the corrected density correlation.
Thus, the calculated PCT for gadolinia fuel rods will be slightly lower than that previously calculated. Since the PCT for gadolinia fuel rods is significantly less 2
- !J 10 CFR 50.46 REPORT OF CHANGES AND ERRORS IN LBLOCA ECCS EVALUATION MODEL than the limiting PCT for U0 2 fuel rods, the PCT impact of this deviation was determined to be 0°F for Palisades.
RELAP4 Transient Gap (SPC CR#6805)
An error was discovered in the gap conductance being too low at the start of the transient because RELAP4 incorrectly converted the DELFI input from inches to feet a second time. It was converted correctly for the initial, steady-state calculation. Consequently, the gap conductance decreased at the start of the transient causing a slight, unexpected increase in the fuel average temperature and resulting in conservative peak cladding temperatures. This error exists only in the RELAP4 version corrected for excessive variability and does not exist in the RELAP4 versions used in prior licensing calculations. The PCT impact of this deviation on the RELAP4 code corrected for excessive variability (Reference
- 1) was determined to be -11°F for Palisades.
RELAP4 Pressure Dependent Fill Junction (SPC CR#6877)
An error was discovered when an incorrect flow rate was produced for the pressure dependent fill junction by the SIS model. The iterative solution method used a non-converged pressure to determine the fill flow rate. This error exists only in the RELAP4 version corrected for excessive variability and does not exist in the RELAP4 versions used in prior licensing calculations. The PCT impact of this deviation on the RELAP4 code corrected for excessive variability (Reference
- 1) was determined to be 0°F for Palisades.
3
LICENSING CORRESPONDENCE
SUMMARY
10 CFR 50.46 REPORT OF CHANGES AND ERRORS IN LBLOCA ECCS EVALUATION MODEL January 7, 1999 FILE NAME: h:\pdf\general\50.46err.rv0 SYS/EQUP NO: NA PRC NO.: NA NPAD NO.: NA RELATED CORRECTIVE ACTION DOCUMENTS: None DATES OF PREVIOUS NRC CORRESPONDENCE: None DATES OF PREVIOUS CONSUMERS ENERGY CORRESPONDENCE: 6/1/98 REVIEW & CONCURRENCE RECORD The attached document requires your review as described below. Your concurrence is requested by 1nl99. The Licensing contact is Phil Flenner, phone extension 2544. This letter is not required to be submitted under oath.
REVIEWER REVIEW CONCURRENCE SIGNATURE COMMENTS CODES* (.-') after signature if you want a copy of submittal.
Lead Manager, GABaustian 1 On file - Rec'd 117/99 Comments incorporated GFPratt 1 On file - Rec'd 117/99 ./ Comments incorporated Licensinq Peer Peer D"E_E~R~9-- Comments incorporated Licensing Supv (Required) Admin ~ '/1 Director, Licensing (Required) Admin Y"J~<lAA, JOY'//'/
v v tu:*(:9 11
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- 1. Reviewer is certifying the accuracy a*nd completeness of the correspondence in the reviewer's area of expertise (including consistency with FSAR, P&IDs, procedures). Each reviewer is also expected to assess the entire document for consistency. Please document any required changes on the document itself and return it to the Licensing contact. If you desire formal comment resolution, please indicate this on the document or in the comment section above.
- 2. Reviewer is familiar with the subject matter and should review the entire document, or appropriate sections of the document, to verify the information is accurate and complete.
- 3. Reviewer is assigned an NRC commitment contained within the correspondence and summarized on the attached sheet(s). The commitment wording and completion date should be verified to be proper, and concurrence provided by initials of assigned person or their supervisor.