ML20070A014: Difference between revisions

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| number = ML20070A014
| number = ML20070A014
| issue date = 06/20/1994
| issue date = 06/20/1994
| title = Submits Results of Review of Data to Be Used in Reactor Vessel Integrity Database,In Response to NRC 940525 Ltr, Requesting Verification of Database Entries W/Regard to GL 92-01,Rev 1
| title = Submits Results of Review of Data to Be Used in Reactor Vessel Integrity Database,In Response to NRC , Requesting Verification of Database Entries W/Regard to GL 92-01,Rev 1
| author name = Tuckman M
| author name = Tuckman M
| author affiliation = DUKE POWER CO.
| author affiliation = DUKE POWER CO.
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = GL-92-01, GL-92-1, TAC-M83448, TAC-M83449, NUDOCS 9406280128
| document report number = GL-92-01, GL-92-1, TAC-M83448, TAC-M83449, NUDOCS 9406280128
| title reference date = 05-25-1994
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 2
| page count = 2
| project = TAC:M83448, TAC:M83449
| stage = Other
}}
}}


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Catawba Nuclear Station, Units 1 and 2 i
Catawba Nuclear Station, Units 1 and 2 i
Docket Numbers 50-413 and -414                                              ;
Docket Numbers 50-413 and -414                                              ;
Generic Letter 92-01, Revision 1; Verification of Data                      l Base Entries (TAC Nos. M83448 and M83449)                                  l By letter dated May 25, 1994, the NRC forwarded a set of data to be used in the Reactor Vessel Integrity Database, and requested that Duke review the data for accuracy.                    In reviewing the data for                !
Generic Letter 92-01, Revision 1; Verification of Data                      l Base Entries (TAC Nos. M83448 and M83449)                                  l By {{letter dated|date=May 25, 1994|text=letter dated May 25, 1994}}, the NRC forwarded a set of data to be used in the Reactor Vessel Integrity Database, and requested that Duke review the data for accuracy.                    In reviewing the data for                !
Catawba, some erroneous data were discovered.
Catawba, some erroneous data were discovered.
1 For Catawba Unit 1, Lower Shell Forging 04, Heat No. Ident. 527708,                            I the %Cu value should be 0.05. For Circ. Weld WOS, Heat No. Ident.
1 For Catawba Unit 1, Lower Shell Forging 04, Heat No. Ident. 527708,                            I the %Cu value should be 0.05. For Circ. Weld WOS, Heat No. Ident.

Revision as of 09:22, 31 May 2023

Submits Results of Review of Data to Be Used in Reactor Vessel Integrity Database,In Response to NRC , Requesting Verification of Database Entries W/Regard to GL 92-01,Rev 1
ML20070A014
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 06/20/1994
From: Tuckman M
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, TAC-M83448, TAC-M83449, NUDOCS 9406280128
Download: ML20070A014 (2)


Text

ll l c .

r DukeIbwer Company M S TLcxw P0 Bax l'/4 Senior Mce President Charlotte, NC28201-1006 Nuclear Generation (704)382-22000ffice

. (704)382-4360 Fax DUKEPOWER June 20, 1994 l

U. S. Nuclear Regulatory Commission l

Washington, D. C. 20555 Attention: Document Control Desk i

Subject:

Catawba Nuclear Station, Units 1 and 2 i

Docket Numbers 50-413 and -414  ;

Generic Letter 92-01, Revision 1; Verification of Data l Base Entries (TAC Nos. M83448 and M83449) l By letter dated May 25, 1994, the NRC forwarded a set of data to be used in the Reactor Vessel Integrity Database, and requested that Duke review the data for accuracy. In reviewing the data for  !

Catawba, some erroneous data were discovered.

1 For Catawba Unit 1, Lower Shell Forging 04, Heat No. Ident. 527708, I the %Cu value should be 0.05. For Circ. Weld WOS, Heat No. Ident.

895075, the %Ni valun should be 0.72. The reference for both I values is WCAP-13763 (Table 1), August 1993, which was transmitted i to the NRC by letter from D. L. Rehn to Document Control Desk, dated August 12, 1993.

For Catawba Unit 2, ID Neut. Fluence at EOL value should be 2.46E19. (Reference WCAP-13875, Table 6-15, February, 1994, transmitted by letter, D. L. Rehn to Document Control Desk, March 2, 1994.) This will change the value of 1/4T fluence for upper shelf energy.

If you have any questions about these data, please call Scott Gewehr at (704) 382-7581.

Very tru yours,

% s. ) w6vw.

M. S. Tuckman nt

(, c .U 4 4 PDR I ww:<mvn m

e  :.

I U. S.. Nuclear Regulatory Commision J,une 20, 1994 Page 2 cc: Mr. R. E. Martin, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission l Mail Stop 14H25, OWFN l Washington, D. C. 20555 )

Mr. S. D. Ebneter, Regional Administrator U.S. Nuclear Regulatory Commission - Region II 101 Marietta Street, NW - Suite 2900 Atlanta, Georgia 30323

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