ML18059A542: Difference between revisions
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* David W. Rogers Plant Safety and Licen5ing Director | * David W. Rogers Plant Safety and Licen5ing Director | ||
* DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -REPLY TO NRC REQUEST FOR INFORMATION REGARDING THE PRESSURIZER SAFE END CRACK -CRITICAL FLAW SIZE AND MARGIN TO FAILURE ANALYSIS An NRC letter dated, October 8, 1993, requested additional information concerning the engineering analysis and root cause evaluation report of the recent pressurizer safe end crack. The letter requested that responses to the 15 information requests be docketed prior to the October 12, 1993 meeting scheduled with the NRC on this subject. The information was not available and therefore not docketed prior to the meeting. At the October 12, 1993 meeting at NRC headquarters CPCO committed to a schedule for responding to each of the 15 information requests. | * DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -REPLY TO NRC REQUEST FOR INFORMATION REGARDING THE PRESSURIZER SAFE END CRACK -CRITICAL FLAW SIZE AND MARGIN TO FAILURE ANALYSIS An NRC letter dated, October 8, 1993, requested additional information concerning the engineering analysis and root cause evaluation report of the recent pressurizer safe end crack. The letter requested that responses to the 15 information requests be docketed prior to the October 12, 1993 meeting scheduled with the NRC on this subject. The information was not available and therefore not docketed prior to the meeting. At the October 12, 1993 meeting at NRC headquarters CPCO committed to a schedule for responding to each of the 15 information requests. | ||
The schedule indicated that results of our PORV margin to failure analysis and our critical flaw size analysis (items 10 and 11 of the request) would be submitted by November 15, 1993. Our letter dated November 15, 1993 informed the NRC that the results of our PORV ma1rgin to failure analysis and *our critical flaw size analysis would not be submitted until November 30, 1993. Attachment 1 to this letter contains the information necessary to respond to information requests 10 and 11 of the NRC's October 8, 1993 letter. Attachments 2 and 3 contain ABB Combustion Engineering calculations supporting the results reported in Attachment | The schedule indicated that results of our PORV margin to failure analysis and our critical flaw size analysis (items 10 and 11 of the request) would be submitted by November 15, 1993. Our letter dated November 15, 1993 informed the NRC that the results of our PORV ma1rgin to failure analysis and *our critical flaw size analysis would not be submitted until November 30, 1993. Attachment 1 to this letter contains the information necessary to respond to information requests 10 and 11 of the NRC's October 8, 1993 letter. Attachments 2 and 3 contain ABB Combustion Engineering calculations supporting the results reported in Attachment | ||
: 1. David W Rogers Plant Safety and Licensing Director CC Administrator, Region III, USNRC NRC Resident Inspector | : 1. David W Rogers Plant Safety and Licensing Director CC Administrator, Region III, USNRC NRC Resident Inspector | ||
-Palisades Attachments 9312080 lfrB\\1931130 PDR S . "" PDR "(\ A CMS" ENERGY COMPANY}} | -Palisades Attachments 9312080 lfrB\\1931130 PDR S . "" PDR "(\ A CMS" ENERGY COMPANY}} |
Revision as of 21:08, 25 April 2019
ML18059A542 | |
Person / Time | |
---|---|
Site: | Palisades ![]() |
Issue date: | 11/30/1993 |
From: | ROGERS D W CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
Shared Package | |
ML18059A543 | List: |
References | |
NUDOCS 9312080126 | |
Download: ML18059A542 (1) | |
Text
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- consumers Power POW ERi Nii /llllCHlliAN'S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 November 30, 1993 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
- David W. Rogers Plant Safety and Licen5ing Director
- DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -REPLY TO NRC REQUEST FOR INFORMATION REGARDING THE PRESSURIZER SAFE END CRACK -CRITICAL FLAW SIZE AND MARGIN TO FAILURE ANALYSIS An NRC letter dated, October 8, 1993, requested additional information concerning the engineering analysis and root cause evaluation report of the recent pressurizer safe end crack. The letter requested that responses to the 15 information requests be docketed prior to the October 12, 1993 meeting scheduled with the NRC on this subject. The information was not available and therefore not docketed prior to the meeting. At the October 12, 1993 meeting at NRC headquarters CPCO committed to a schedule for responding to each of the 15 information requests.
The schedule indicated that results of our PORV margin to failure analysis and our critical flaw size analysis (items 10 and 11 of the request) would be submitted by November 15, 1993. Our letter dated November 15, 1993 informed the NRC that the results of our PORV ma1rgin to failure analysis and *our critical flaw size analysis would not be submitted until November 30, 1993. Attachment 1 to this letter contains the information necessary to respond to information requests 10 and 11 of the NRC's October 8, 1993 letter. Attachments 2 and 3 contain ABB Combustion Engineering calculations supporting the results reported in Attachment
- 1. David W Rogers Plant Safety and Licensing Director CC Administrator, Region III, USNRC NRC Resident Inspector
-Palisades Attachments 9312080 lfrB\\1931130 PDR S . "" PDR "(\ A CMS" ENERGY COMPANY