ML20072M592

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Sunmits Corrected Tables of PTS & Use Info as Requested by NRC Re Util Response to GL 92-01,Rev 1
ML20072M592
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 08/25/1994
From: Carns W
WOLF CREEK NUCLEAR OPERATING CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, WM-94-0108, WM-94-108, NUDOCS 9409020087
Download: ML20072M592 (3)


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' t W6) LF NUCLEAR CREEKOPERATING Ned S *Bou' Carns August 25, 1995 Chairman. President and Chml Decutwe Officer WM 94-0108 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D. C. 20555

Reference:

Letter dated May 12, 1994, from W. D. Reckley, NRC, to N. S. Carns, WCNOC

Subject:

Docket No. 50-482: Reactor Vessel Structural Integrity Gentlemen:

This letter submits corrected tables of pressurized thermal shock (PTS) and upper-shelf energy (USE) information as requested by the Reference. The Reference transmitted tables that contained PTS and USE information for Wolf Creek Generating Station and requested that an accuracy review be performed on the information contained in the tables. This information was based on data that was taken from Wolf Creek Nuclear Operating Corporation's response to Generic Letter 92-01, ' Revision 1,

  • Reactor Vessel Structural Integrity," and previously docketed information. Portions of this information were originally telecopied to Mr. W. D. Reckley on June 10, 1994, with subsequent changes made based on input from Westinghouse. Please review the attached corrected tables and update your database accordingly.

If you have any questions concerning this matter, please contact me at (316) 364-8831, extension 4000, or Mr. Richard D. Flannigan at extension 4500.

Verf truly yours,

) t* W Neil S. Carns NSC/j ra Attachment cc: L. J. Callan (NRC), w/a D. N. Graves (NRC), w/a W. D. Reckley (NRC), w/a J. F. Ringwald (NRC), w/a R G? PO Box 411/ Burhngton. KS 66839 / Phone (316) 364-8831 g P PDR An Eque Opponundy Employer u FMC.YE T  !

, o htbachment to WM 94-0108

,Page 1 of 2 .

ENCLOSURE 1 Summary File for Pressurized Thermal Shock Plant Beltline Heat No. ID Neut. IRTnot Method of Chemistry Method of %Cu %Ni Name Ident. Ident. Fluence at Determin. Factor Determin.

EOL 1RTnot CF Wolf Int. Shell 2.5E19 -20'F Plant 26 Table 0.04 0.66 Creek R2005-1 Specific Int. Shell 2.5E19 -20 F Plant 26 Table 0.04 0.64 EOL: R2005-2 Specific 3/11/2025 Int. Shell 2.5E19 -20 F Plant 31 Table 0.05 0.63 R2005-3 Specific j Lower 2.5E19 0*F Plant 58 Table 0.09 0.67 i Shell Specific R2508-1 Lower 2.5E19 10'F Plant 37 Table 0.06 0.64 Shell Specific '

R2508-2 Lower 2.5E19 40 F Plant 34.433 Calculated 0.07 0.62 Shell Specific '

R2508-3 Int. and 90146 2.5E19 -50 F Plant 27.8 Table 0.04 0.04 Lower Specific Shell Axial Welds G2.06 Int,to 90146 2.5E19 -50 F Plant 41.022 Calculated 0.05 0.05 Lower Specific Shell Circ.

Weld E3.16 BelCLCDCCS The copper and nickel contents and IRTnots of the beltline materials are from Table B-1 of WCAP-13365. Phosphorus and sulfur contents of surveillance materials are from WC AP-13365.

The fluence is from Table 6-14 of WCAP-13365.

- s Atiachment to WM 94-0108

,Page 2 of 2 j

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ENCLOSURE 2 Summary File for Upper Shelf Energy Plant Beltline Heat No. Material 3 1/4T USE 1/4T Unitrad. Method of Name Ident. Type at EOL Neutron USE Determin.

Fluence at Unirrad.

EOL USE Wolf Int. Shell A 5338-1 102 1.36E19 127 Direct Creek R2005-1 Int. Shell A 5338-1 102 1.36E19 127 Direct EOL: R2005-2 3/11/2025 Int. Shell A 5338-1 108 1.36E19 135 Direct R2005-3 Lower A 5338-1 70 1.36E19 87 Direct Shell R2508-1 Lower A 5338-1 80 1.36E19 100 Direct Shell R2508-2 Lower A 5338-1 87 1.36E19 89 Direct Shell R2508-3 Int. and B4 90146 Linde 0091 120 1.36E19 149 Direct Lower SAW Shell Axial Welds G2.06 Int.to B4 90146 Linde 124 78 1.36E19 98 Surv.

Lower SAW Weld Shell Circ. Weld E3.16 Reletences The copper and nickel contents and IRTnais of the beltline materials are from Table B-1 of WCAP-13365. Phosphorus and sulfur contents of surveillance materials are from WCAP-13365.

The fluence is from Table 6-14 of WCAP-13365.

Material type for plates and USE data are from Table A-3 of WCAP-11553; material types I for welds are from Table A-5 of WCAP-10015.

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