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MONTHYEARML18054A7611989-05-11011 May 1989
Documents Five Commitments Made at 890502 Meeting Re Short Term Plans for Continued Operation & Steam Generator Maint. Plant Will Be Shutdown on or Before 891010 to Implement Repair to Westinghouse Tube Plugs from Defective Heat Lot
Project stage: Meeting
ML18054A7711989-05-22022 May 1989
Forwards Rev 1 to MPR-1124, Palisades Steam Generators Tube Crack Growth During Steam Line Break, for NRC Review.Max Crack Size Expected Following Steam Line Break Event Is 117 Degrees of Circumference
Project stage: Other
ML18054A8841989-07-31031 July 1989
Submits Oct 1989 Outage Eddy Current Insp Plans & MIZ-18 Qualification Status,Per 890511 & 0224 Ltrs.Results of Tube Flaw Size/Vibration Analysis Conducted by MPR Assoc,Indicate That Continued Operation Does Not Present Significant Risk
Project stage: Other
ML18054A9471989-08-30030 August 1989
Forwards Palisades Nuclear Plant 1989 MIZ-18 Eddy Current Sys Qualification, Per 890731 Commitment
Project stage: Other
ML18054A9501989-08-30030 August 1989
Provides 2 Wk Notice & Requests NRC Approval Re Increase in Power to Nominal 90% in 5% Increments.Increase in Power Will Provide More Data to Evaluate Power Level Dependency of Steam Generator Tube Leakage
Project stage: Other
ML18054A9721989-09-0808 September 1989
Reviews Util 890830 Request to Raise Power at Facility Above Current Operating Level of 80% to Provide 2-wk Period at Elevated Power Levels Prior to Shutdown for Maint Outage.Nrc Has No Objections to Planned Power Increase
Project stage: Other
ML18054B0241989-09-26026 September 1989
Summary of 890912 Meeting W/Util Re Proposed Steam Generator Tube Insp Program for Plant.List of Attendees & Proposed Plan Details Encl
Project stage: Meeting
ML18054B0211989-09-28028 September 1989
Discusses Scope of Fall 1989 Outage Steam Generator Tube Insp,Per Util 890830 Commitment.Results of Insps Will Be Used to Determine If Any Expansion Necessary Subsequent to Insps
Project stage: Other
ML18054B0851989-11-0303 November 1989
Forwards Detailed 1989 Maint Outage Steam Generator Insp Results.Licensee Concludes That Probability or Consequences of Accident or Malfunction of Equipment Important to Safety Will Not Be Increased by Continued Operation W/Generators
Project stage: Other
IR 05000255/19890011989-11-0303 November 1989
SALP Board Rept 50-255/89-01 for June 1988 - Aug 1989
Project stage: Request
ML18054B0841989-11-0606 November 1989
Confirms 891103 Telcon Re Past Quantification of primary-to- Secondary Sys Leakage within Steam Generators & Recent Training of Operations Personnel for Mitigating Steam Generator Tube Rupture Incident
Project stage: Other
ML18054B3081989-12-12012 December 1989
Advises That Util Intends to Proceed W/Administrative primary-to-secondary Sys Leakage Operating Criteria of 80% Rated Thermal Power Until Replacement of Both Steam Generators in Fall 1990.Insp Plans Under Evaluation
Project stage: Other
ML18054B3531990-01-0404 January 1990
Provides Justification to Support Exemption from Tube Wastage Insps & Insp Plans in Event of Steam Generator Tube Leak Outage.Listed Insp Plan Will Be Implemented When Leakage Identified
Project stage: Other
ML18054B5621990-04-17017 April 1990
Advises That NRR Plans No Further Review of Re Completion of MIZ-18 Eddy Current Sys Qualification Program,Based on Successful Application of MIZ-18 During Fall 1989 Steam Generator Insps
Project stage: Approval
1989-07-31
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- .. 'W' consumers Power POWERINli MICHlliAN'S PRDliRESS General Offi"ces: 1945 West Parnall Road, Jackson,' Ml 49201 * (517) 788-0550 May 22, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
STEAM GENERATOR OPERATING COMMITMENTS -
FLAW SIZE/VIBRATION ANALYSIS (TAC NO 69344)
Consumers Power Company committed to provide a steam generator tube flaw size/vibration analysis for NRC review.
Attached is the analysis, entitled "Palisades Steam Generator Tube Crack Growth During a Steam Line Break".
This analysis evaluates the potential for an existing tube crack to grow to critical crack size as a result of a steam line break.
As summarized in the attached report, the maximum throughwall crack size which can exist in a steam generator tube without bursting due to the internal pressure is 187° of the circumference.
The maximum crack size expected following a steam line break event, assuming existing circumferential throughwall cracks of 90° or less, is 117° of the circumference.
The maximum expected crack size is much smaller than the critical crack size and, therefore, a steam line break event is not expected to cause a fluid-elastic vibration induced tube failure.
R~k{(/J_
Ralph R Frisch Senior Licensing Analyst CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment 8905310041 890522 PDR ADOCK 05000255 p
PNU OC0589-0134-NL04 A CMS ENERGY COMPANY
