ML010950534
| ML010950534 | |
| Person / Time | |
|---|---|
| Site: | Nuclear Energy Institute |
| Issue date: | 04/05/2001 |
| From: | Sheron B NRC/NRR/ADPT |
| To: | Marion A Nuclear Energy Institute |
| Carpenter C, NRR/DRIP/RGEB, 4415-1282 | |
| References | |
| Download: ML010950534 (4) | |
Text
April 05, 2001 Mr. Alex Marion, Director Engineering Nuclear Energy Institute 1776 I Street, N.W., Suite 400 Washington, D.C. 20006-3708
SUBJECT:
MRP MEETING ON CRDM CRACKING DISCUSSION TOPICS
Dear Mr. Marion:
The staff will be meeting with the Electric Power Research Institutes Materials Reliability Program (MRP) on Thursday, April 12, 2001, to discuss the generic implications and proposed industry actions of the circumferential cracking found on pressurized water reactor (PWR) control rod drive mechanism (CRDM) upper head penetrations at Oconee Unit 3.
In addition to a discussion of the Oconee circumferential CRDM cracking, the NRC staff requests that the MRPs presentation on their proposed actions to address the generic aspects of the CRDM cracking issue include, but not be limited to, the following items:
A discussion of how the results of the CRDM cracking found at Oconee is being utilized by the MRP to address this issue on a generic basis. In order to provide sufficient background, the staff requests that an overview of the Oconee CRDM cracking be given, and include, as a minimum, the results of non-destructive examinations (NDE) and any destructive examinations performed to date, a discussion of the repairs performed or planned, the licensees plans for resolving this issue, the implications of this experience on the reliability of ongoing inspections, and the potential for circumferential failure of a PWR CRDM penetration.
Discussion of the inspection plans, schedule, scope and method to be utilized in performing NDE of the CRDMs. This discussion is requested to include a listing of all PWRs that are either in, or will be coming down for, an outage during the current outage season, any inspections that have been or will be performed by these licensees, and whether licensees will expand the scope of inspections beyond that presently required by Generic Letter (GL) 88-05, "Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants, dated March 17, 1988 (e.g., removal of insulation, etc.).
The schedule for and scope of a generic safety assessment of PWR CRDMs, supported by deterministic and/or risk-informed assessments, that establishes a technical justification for continued operation with potentially degraded penetrations until such time as comprehensive inspections can be performed of the PWR CRDMs.
Mr. Alex Marion "
A discussion of the implications of this recent service experience on the commitments made in response to GL 97-01, "Degradation of Control Rod Drive Mechanism Nozzle And Other Vessel Closure Head Penetrations," dated April 1, 1997.
If you have any question regarding this request, please contact Jack Strosnider of my staff at (301) 415-3298.
Sincerely,
/RA/Signed by B. Sheron Brian Sheron, Associate Director Project Licensing & Technical Analysis Office of Nuclear Reactor Regulation Project No. 689 cc:
See next page
Mr. Alex Marion "
A discussion of the implications of this recent service experience on the commitments made in response to GL 97-01, "Degradation of Control Rod Drive Mechanism Nozzle And Other Vessel Closure Head Penetrations," dated April 1, 1997.
If you have any question regarding this request, please contact Jack Strosnider of my staff at (301) 415-3298.
Sincerely,
/RA/Signed by B. Sheron Brian Sheron, Associate Director Project Licensing & Technical Analysis Office of Nuclear Reactor Regulation Project No. 689 cc:
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ADPT:NRR NAME CECarpenter PWen KWichman WBateman JRStrosnider BWSheron DATE 04/03/2001 04/04/2001 04/04/2001 04/04/2001 04/04 /2001 04/05/2001 OFFICIAL RECORD COPY
Nuclear Energy Institute Project No. 689 cc:
Mr. Ralph Beedle Senior Vice President and Chief Nuclear Officer Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708 Ms. Lynnette Hendricks, Director Plant Support Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708 Mr. Jim Davis, Director Operations Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708 Mr. Charles B. Brinkman, Director Washington Operations ABB-Combustion Engineering, Inc.
12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. David Modeen, Director Engineering Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708 Mr. H. A. Sepp, Manager Regulatory and Licensing Engineering Westinghouse Electric Company P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 Mr. Anthony Pietrangelo, Director Risk & Performance Based Regulation Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708 Larry Mathews, MRP Southern Nuclear Operating Company Manager, Inspection and Testing Services P. O. Box 1295 Birmingham, AL 35201 Vaughn Wagoner, Technical Chair Assessment Committee Carolina Power & Light Company One Hannover Square 9C1 P.O. Box 1551 Raleigh, NC 27612 Avtar Singh, EPRI MRP Manager Electric Power Research Institute P. O. Box 10412 3412 Hillview Ave.
Palo Alto, CA 94303 C. Thomas Alley, Jr., Technical Chair Inspection Task Duke Power Company Nuclear General Office 526 South Church Street Mail Code EC09O PO Box 1006 Charlotte NC 28201 Mr. Allan McIlree, EPRI Assessment Manager Electric Power Research Institute P. O. Box 10412 3412 Hillview Ave Palo Alto, CA 94304 Gary D. Moffatt, Technical Chair Repair/Mitigation Task V. C. Summer Nuclear Station P. O. Box 88 Jenkinsville, SC 29065 Frank Ammirato, EPRI Inspection Manager EPRI NDE Center P. O. Box 217097 1300 W. T. Harris Blvd.
Charlotte, NC 28221