ML18059A542: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(One intermediate revision by the same user not shown)
Line 18: Line 18:
=Text=
=Text=
{{#Wiki_filter:.,
{{#Wiki_filter:.,
* 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
consumers Power                                                         David W. Rogers Plant Safety and Licen5ing Director
* David W. Rogers Plant Safety and Licen5ing Director
* POWERiNii
* 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.
          /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 DOCKET 50-255 - LICENSE DPR 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.
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
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.
: 1. David W Rogers Plant Safety and Licensing Director CC Administrator, Region III, USNRC NRC Resident Inspector  
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.
-Palisades Attachments 9312080 lfrB\\1931130 PDR S . "" PDR "(\ A CMS" ENERGY COMPANY}}
Attachments 2 and 3 contain ABB Combustion Engineering calculations supporting the results reported in Attachment 1.
                                                                                      ~--*
David WRogers Plant Safety and Licensing Director CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachments 9312080 lfrB\\1931130 PDR ADOCK~05000255 S     .     ""   ~-    PDR
                  "(\                             A CMS" ENERGY COMPANY}}

Latest revision as of 11:59, 3 February 2020

Forwards Responses to NRC 931008 RAI Re Engineering Analysis & Root Cause Evaluation Rept of Recent Pressurizer Safe End Crack,Including Results of Util PORV Margin to Failure Analysis & Critical Flaw Size Analysis
ML18059A542
Person / Time
Site: Palisades Entergy icon.png
Issue date: 11/30/1993
From: Rogers D
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

.,

consumers Power David W. Rogers Plant Safety and Licen5ing Director

  • POWERiNii

/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 DOCKET 50-255 - LICENSE DPR 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 WRogers Plant Safety and Licensing Director CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachments 9312080 lfrB\\1931130 PDR ADOCK~05000255 S . "" ~- PDR

"(\ A CMS" ENERGY COMPANY