ML20246N496
| ML20246N496 | |
| Person / Time | |
|---|---|
| Issue date: | 05/11/1989 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| TAC-71814, NUDOCS 8905190454 | |
| Download: ML20246N496 (4) | |
Text
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May 11, 1989 MEMORANDUM FOR:
George Knighton, Director Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects FROM:
Harry Rood, Senior Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects
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SUBJECT:
SUMMARY
OF MARCH 28, 1989 PUBLIC MEETING TO DISCUSS STRESS CORROSION CRACKING 0F HIGH-HARDNESS STEEL COMPONENTS IN SAFETY RELATED-SYSTEMS (TAC NO. 71814)
On March 28, 1989 the NRC staff met with NUMARC to discuss stress corrosion cracking (SCC) of high-hardness steel components in safety-related systems.
The attendees at the meeting are given in Enclosure 1.
The March 28, 1989 meeting was a follow-on to a meeting held on January 12, 1989 to discuss stress corrosion cracking of studs in Anchor Darling check valves observed at the D. C. Cock and Diablo Canyon plants.
At the March 28, 1989 meeting, the NRC staff stated that after the January 12, 1989 meeting, a NPRDb search was conducted, and several instances of failure of type 410 stainless steel (SS) were found. NUMARC stated that an ad hoc advisory committee hat been set up by NUMARC to study the issue of stress corrosion cracking that had been discussed at the January 12, 1989 meeting.
This advisory committee had held a meeting in early March,1989 to (1) look into the knowledge base to estimate the magnitude of the problem, and (2) determine what actis ities are already underway in the industry. The advisory group consists of six to eight individuals, including EPRI. The committee did not find a ny really significant failures involving SCC, and the failure rate was not high enough to be a challenge to the safety of nuclear power plants.
In addition, NUMARC presented a report by Babcock and Wilcox (B&W) entitled "Eveluation of 410SS and 17-4 PH for Nuclear Service," dated March 13, 1989.
The report covered the SCC susceptibility of two types of high-strength stainless steel currently in service at nuclear power plants. The report stated that " Currently installed 410S5 components should be evaluated for SCC susceptibility by reviewing manufacturing records, performing various non-destructive tests (e.g., hardness, UT), visual checks for heavy pitting, ar.d precautions against contact with Cu, S, C1, F, Doric acid, or other l
detrimental materials." NUMARC stated that this report could be made available to the industry (the 54 member-utilities of NUMARC).
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2-The NRC staff recommended that NUMAP.C distribute the B&W report on SCC of high-strength, corrosion-resistant materials to the industry, and NUMARC agreed.
In addition, the staff recommended that the transmittal letter should also state that surface examination and hardness testing of SCC-susceptible components should be considered, during maintenance of safety-related components. The NUMARC personnel at the meeting. indicated that they could not commit to this recommendation at the meeting, but would discuss it with their-management, and inform the staff of their decision.
No further meetings are planned between NUMARC and the NRC staff on this l
subject.
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Harry Rood, Senior Project Manager Project Directorate V Division of Reactor Projects - III, IV,.V and Special Projects
Enclosure:
Agenda cc: w/ enclosures - see next page l
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t May ll,1989 j
. I The NRC staff recommended that NUMARC distribute the B&W report on SCC of high-strength, corrosion-resistant materials to the industry, and NUMARC agreed.
In addition, the staff recommended that the transmittal letter should also state that surface examination and hardness testing of SCC-susceptible components should be considered, during maintenance of safety-related components. The NUMARC personnel at the meeting indicated that they could nut commit to this recommendation at the meeting, but would discuss it with their management, and inform the staff of their decision.
No further meetings are planned between NUMARC and the NRC staff on this subject.
/s/
Harry Rood, Senior Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects
Enclosure:
Agenda cc: w/ enclosures - see next page DISTRIBUTION Central File 1 NRC~&'LPDRs JSniezek PDV Files GKnighton HRood OGC EJordan BGrimes TMcLellan CDSellers RHermann CYCheng PKadambi ACRS (10)
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l B. Bradley NUMARC 1776 Eye St., NW suite 300 Washington, DC 20066 B. Brooks EPRI 3412 Hillview Avenue Palo Alto, CA 94303 D. Grace, Chairman BWR Owner's Group c/o GPU Nuclear Corp.
1 Upper Pond Road Parsippany, NJ 07054 R. Newton, Chairman Westinghouse Owrer's Group c/o Wisconsin Electric Power 231 W. Michigan Milwaukee, WI 53201 E. Sterling, Chairman CE Owner's Group c/o Arizona Nuclear Power Project 11226 N. 23rd Avenue Phoenix, Arizona 85029 J. H. Taylor c/o Nuclear Power Division Babcock and Wilcox P. O. Box 10935 Lynchburg, VA 24503-0935
t ENCLOSURE 1 ATTENDEES Public Meeting on Stress Corrosion Cracking of High-Hardness Materials in Safety-Related Systems Tuesday, March 28, 1989 NAME ORGANIZATION Biff Eradley NUMARC Michael Galler Northwest Utilities J. F. Hall Combustion Engineering Stephen Hart Duke Power Robert Hermann NRC/EMTB (participated by telephone)
Reger Huston NUMARC N. Prasad Kawanti NRC/0GCB Greg Kammerdeiner DLC/ Westinghouse Owner's Group George W. Knighton NRC/D:PDV Albert Machiels EPRI Tom K. McLellan NRC/EMTB Steve Poltorak Bechtel Harry Rood NRC/PDV C. D. Sellers NRC/EMTB Randy Van Lear Babcock and Wilcox
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