ML20196J488
| ML20196J488 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 06/29/1999 |
| From: | Jaffe D NRC (Affiliation Not Assigned) |
| To: | Terry C TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| GL-92-01, GL-92-1, TAC-MA0536, TAC-MA0537, TAC-MA536, TAC-MA537, NUDOCS 9907070304 | |
| Download: ML20196J488 (3) | |
Text
}
[
t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20555 0001 4 y g *&
June 29, 1999 I
o i
Mr. C. Lance Terry j
Senior Vice President & Principal Nuclear Officer TU Electric Attn: Regulatory Affairs Department P. O. Box 1002 Glen Rose, TX 76043
SUBJECT:
RESPONSE TO THE REQUESTS FOR INFORMATION IN GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY," FOR COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS. MA0536 AND MA0537)
Dear Mr. Terry:
On May 19,1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter 92-01, Revision 1, Supplement 1 (GL 92 01, Rev.1, Supp.1), " Reactor Vessel Structural integrity," to holders of nuclear operating licenses. In issuing the generic letter, the staff required addressees of the generic letter to:
(1) identify, collect, and report any new data pertinent to the analysis of structural integrity of the reactor pressure vessels (RPVs) at their nuclear plants, and (2) to assess the impact of that data on their RPV integrity analyses relative to the requirements of Sections 50.80 and 50.61 to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50.60 and 10 CFR 50.61), and to the requirements of Appendices G and H to 10 CFR Part 50.
On August 17,1995, you submitted your initial response to GL 92-01, Rev.1, Supp.1, and provided the requested information relative to the structural integrity assessments for Comanche Peak Steam Electric Station, Units 1 and 2. The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on August 28, 1997; however, since the time of the staff's closure letter, the Combustion Engineering (CE)
Owners Group and the Babcock and Wilcox (B&W) Owners Group have each submitted additional data regarding the alloying chemistries of beltline we'ds in CE and B&W fabricated vessels. The additional alloying data were submitted in Topical Reports CE NPSD-1039, Revision 2, and CE NPSD-1119, Revision 1, for CE fabricated RPV welds, and BAW-2325, j
Revision 1, for B&W fabricated RPV welds.
fv J
On December 31,1997, you provided your final response to the NRC staff regarding your assessment of the information in the topical reports noted above. The NRC staff has reviewed the information that you submitted and determined that it adequately reflects the information V
contained in CE Topical Reports CE NPSD-1039, Revision 2, and CE NPSD-1119, Revision 1, for CE fabricated RPV welds.
S 957@ M E OC0046 9907070304 990629 PDR ADOCK 05000445 P
PDR l
4 C. L. Terry June 29, 1999 As a result of the staff's review of your responses to GL 92-01, Revision 1, and GL 92-01, Rev.1, Supp.1, the NRC staff has revised the information in the Reactor Vessel integrity Database (RVID) and is releasing it as RVID, Version 2. The new database diskettes are posted on the world-wide-web at a location thct is linked to the NRC home page (http://www.nrc. gov /NRR/RVID/index.html). We recommend that you review this information. If the staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for your plant. No additional information is necessary with regard to the structural integrity assessments. Future submittals on pressure and temperature limits, pressurized thermal shock, or upper shelf energy should reference the most current information.
This closes the NRC staff's efforts in regard to TAC numbers MA0536 and MA0537. The staff appreciates your efforts in regard to this matter.
Sincerely, ORIGINAL SIGNED BY David H. Jaffe, Senior Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446 cc: See next page
- DISTRIBUTION:
. Docket File A. Lee., NR
' PUBLIC PD#1V-1 r/f OGC ACRS K. Brockman, RIV To IWceive a copy of this document, indicate "C" in the box OFFICE PQPM PDIV-1/L4 q h PDIV-1/SC C h
hb LBerry ff RGramrb NAME DATE b /lf /99 b /,MJ99 '
[j /2k /99 DOCUMENT NAME: G:\\PDIVli \\Co m a nche Pe a k\\itra0536.wpd OFFICIAL RECORD COPY-b.
i Comanche Peak Steam Electne. Plant cc:
Senior Resident inspector Office of the Governor U.S. Nuclear Regulatory Commission ATTN: John Heward, Director P. O. Box 2159 Environmental and Natural Glen Rose, TX 76403-2159 Resources Policy P. O. Box 12428 Regional Admirdstrator, Region IV Austin, TX 78711 U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arthur C. Tate, Director Arlington,TX 76011 Division of Compliance & Inspection Bureau of Radiation Control Mrs. Juanita Ellis, President Texas Department of Health Citizens Association for Sound Energy 1100 West 49th Street 1426 South Polk Austin, TX 78756-3189 Dallas, TX 75224 Jim Calloway Mr. Roger D. Walker Public Utility Commission of Tcxas Regulatory Affairs Manager Electric Industry Analysis TU Electric P. O. Box 13326 P. O. Box 1002 Austin, TX 78711-3326 Glen Rose, TX 76043 George L. Edgar, Esq.
Morgan, Lewis & Bock'us 1800 M Street, N.W.
Washington, DC 20036-5869 Honorable Dale McPherson County Judge P. O. Box 851 Glen Rose, TX 76043 i
May 1999 l