ML023470483
| ML023470483 | |
| Person / Time | |
|---|---|
| Site: | Nuclear Energy Institute |
| Issue date: | 12/13/2002 |
| From: | Barrett R Division of Engineering |
| To: | Marion A Nuclear Energy Institute |
| References | |
| Download: ML023470483 (2) | |
Text
December 13, 2002 Mr. Alexander Marion, Director - Engineering Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708
SUBJECT:
REQUEST FOR REACTOR PRESSURE VESSEL HEAD PENETRATION MATERIAL HEAT INFORMATION As a result of recent operating experience with Alloy 600 and reactor pressure vessel (RPV) head penetration cracking, the NRC staff has begun the development of a RPV head inspection results database to facilitate a more systematic assessment of cracking and degradation in RPV heads and vessel head penetration (VHP) nozzles. The NRC staff intends to include material heat information for each pressurized water reactor in the database, because material heat may be an important factor when evaluating the inspection results.
As part of their integrated response to Generic Letter 1997-01, in July 1997, the B&W Owners Group identified the heat and material supplier for each Babcock and Wilcox (B&W) PWR vessel head. It is our understanding that the Nuclear Energy Institute (NEI) and/or Electric Power Research Institutes Material Reliability Program (MRP) has assembled similar heat information for Westinghouse and Combustion Engineering PWRs. If this information has been compiled, the staff would like to receive a copy of any report(s) or data file(s) documenting this information.
I appreciate your assistance. If you have any questions about this request, please, contact Dr.
Allen Hiser at 301-415-1034 or Mr. Michael Marshall at 301-415-2734.
Sincerely,
/RA/
Richard Barrett, Director Division of Engineering Office of Nuclear Reactor Regulation Project No. 689 cc:
Larry Mathews, Southern Company Kurt Cozens, NEI Christine King, EPRI
Mr. Alexander Marion, Director - Engineering Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708
SUBJECT:
REQUEST FOR REACTOR PRESSURE VESSEL HEAD PENETRATION MATERIAL HEAT INFORMATION As a result of recent operating experience with Alloy 600 and reactor pressure vessel (RPV) head penetration cracking, the NRC staff has begun the development of a RPV head inspection results database to facilitate a more systematic assessment of cracking and degradation in RPV heads and vessel head penetration (VHP) nozzles. The NRC staff intends to include material heat information for each pressurized water reactor in the database, because material heat may be an important factor when evaluating the inspection results.
As part of their integrated response to Generic Letter 1997-01, in July 1997, the B&W Owners Group identified the heat and material supplier for each Babcock and Wilcox (B&W) PWR vessel head. It is our understanding that the Nuclear Energy Institute (NEI) and/or Electric Power Research Institutes Material Reliability Program (MRP) has assembled similar heat information for Westinghouse and Combustion Engineering PWRs. If this information has been compiled, the staff would like to receive a copy of any report(s) or data file(s) documenting this information.
I appreciate your assistance. If you have any questions about this request, please, contact Dr.
Allen Hiser at 301-415-1034 or Mr. Michael Marshall at 301-415-2734.
Sincerely, Richard Barrett, Director Division of Engineering Office of Nuclear Reactor Regulation Project No. 689 cc:
Larry Mathews, Southern Company Kurt Cozens, NEI Christine King, EPRI Distribution:
M. Marshall A. Hiser T. Chan S. Coffin J. Birmingham P. Wen T. Tate W. Reckley B. Sheron B. Cullen N. Chokshi M. Mayfield W. Bateman Accession No.: ML023470483 OFFICE NRR:DE:EMCB NRR:DE:EMCB NRR:DE D:DE NAME M Marshall T Chan W Bateman R Barrett DATE 12 / 4 / 02 12 / 9 / 02 12 / 9 / 02 12 / 13 /02 OFFICIAL RECORD COPY