ML041110780
| ML041110780 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/19/2004 |
| From: | Sean Peters NRC/NRR/DLPM/LPD2 |
| To: | Jamil D Duke Energy Corp |
| Peters, S, NRR/DLPM/301-415-1842 | |
| References | |
| TAC MC1703 | |
| Download: ML041110780 (6) | |
Text
April 19, 2004 Mr. D. M. Jamil Vice President Catawba Nuclear Station Duke Energy Corporation 4800 Concord Road York, South Carolina 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNIT 1 RE: REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC1703)
Dear Mr. Jamil:
By letter dated December 23, 2003, Duke Energy Corporation submitted information concerning the steam generator tube inspection report for End of Core 14 at Catawba Nuclear Station, Unit 1. The Nuclear Regulatory Commission technical staff has reviewed your submittal and has determined that additional information is required for the staff to complete its review, as identified in the Enclosure.
We discussed these issues with your staff on April 1, 2004. Your staff indicated that you would attempt to provide your response by June 1, 2004.
Please contact me at (301) 415-1842, if you have any questions on these issues.
Sincerely,
/RA/
Sean E. Peters, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-413
Enclosure:
Request for Additional Information cc w/encl: See next page
April 19, 2004 Mr. D. M. Jamil Vice President Catawba Nuclear Station Duke Energy Corporation 4800 Concord Road York, South Carolina 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNIT 1 RE: REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC1703)
Dear Mr. Jamil:
By letter dated December 23, 2003, Duke Energy Corporation submitted information concerning the steam generator tube inspection report for End of Core 14 at Catawba Nuclear Station, Unit 1. The Nuclear Regulatory Commission technical staff has reviewed your submittal and has determined that additional information is required for the staff to complete its review, as identified in the Enclosure.
We discussed these issues with your staff on April 1, 2004. Your staff indicated that you would attempt to provide your response by June 1, 2004.
Please contact me at (301) 415-1842, if you have any questions on these issues.
Sincerely,
/RA/
Sean E. Peters, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-413
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
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Enclosure REQUEST FOR ADDITIONAL INFORMATION DUKE POWER COMPANY CATAWBA NUCLEAR STATION, UNIT 1 DOCKET NO. 50-413 The Nuclear Regulatory Commission (NRC) staff has reviewed the licensees submittal dated December 23, 2003, forwarding the End of Core (EOC) 14 Steam Generator Tube Inspection Report for Catawba Nuclear Station (Catawba), Unit 1. The NRC staff has identified the following information that is needed to enable the continuation of its review.
1.
The steam generators at Catawba, Unit 1, were replaced in 1996 with Babcock and Wilcox International CFR 80 steam generators. In several locations in your reports, you reference tube support structures (e.g., fan bar 4) and tube locations (e.g., Row 14 Column 55). In order for the NRC staff to better understand the location of the indications, please provide (1) a sketch of the Unit 1 steam generators which depicts the tube support naming conventions and (2) a tubesheet map which depict the rows and columns of the tubes. In addition, please provide the following general design information: tube manufacturer, tube material, tube outside diameter, tube wall thickness, tube support (including fan bar/anti-vibration bar) material and configuration, tube support (including fan bar) thickness, tube pitch and orientation (e.g., 1.1-inch triangular pitch), expansion method, and any other noteworthy design characteristics from a steam generator tube integrity standpoint (e.g., full length stress relief of the row 1 through row 10 tubes). Furthermore, discuss whether measurements from a tube support are from the middle of the support or the edge of the support. For example, does fan bar 5 minus 0.9 inches specify an indication 0.9 inches from the bottom edge of the fan bar?
2.
For the EOC 14 inspections, please clarify the scope and extent of the inspections. For example, please discuss what probes were used during the inspection, how many tubes were inspected, and what portions of the tubes were inspected with these probes (e.g., 100 percent full-length inspection with a bobbin probe, rotating-probe inspection of the hot-leg expansion transition region (+/- 3 inches) for 100 percent of the inservice tubes, etc.).
3.
Please clarify the results of your inspection. For example:
a.
For the volumetric indications reported, please discuss the source and significance of these indications.
b.
Please clarify the difference between an NQI and an NQS indication.
c.
Please clarify the potential and actual degradation mechanisms observed in your steam generators. For example, several wear indications have been reported.
Please briefly discuss the cause of these indications and the population of tubes susceptible to these mechanisms. In addition, several tubes were inspected/classified as proximity tubes in a previous inspection. Please describe this categorization and the tubes potentially affected by this issue.
4.
Seven tubes were plugged and stabilized in steam generator C as a result of a loose part that could not be removed. Please clarify the source and nature of this part. In addition, briefly summarize the corrective actions taken and your basis for the corrective actions (e.g., all steam generators were inspected, the part was surrounded by plugged and stabilized tubes and is not expected to move based on analysis, etc).
5.
Several indications were reported as CHG indications. Please clarify the meaning of this acronym. Assuming this acronym implies the indication has changed, please discuss what signal characteristic changed and the cause of the change (or provide a description of actions that you may be planning to take to investigate the reason for the change). For the criteria used to determine if a signal exhibits little or no change, discuss how the criteria was determined. For example, was test repeatability evaluated for these types of indications such that the criteria would identify a signal change when the change was greater than normal test repeatability?
Catawba Nuclear Station cc:
Lee Keller, Manager Regulatory Compliance Duke Energy Corporation 4800 Concord Road York, South Carolina 29745 Ms. Lisa F. Vaughn Duke Energy Corporation Mail Code - PB05E 422 South Church Street Post Office Box 1244 Charlotte, North Carolina 28201-1244 Anne Cottingham, Esquire Winston and Strawn 1400 L Street, NW Washington, DC 20005 North Carolina Municipal Power Agency Number 1 1427 Meadowwood Boulevard Post Office Box 29513 Raleigh, North Carolina 27626 County Manager of York County York County Courthouse York, South Carolina 29745 Piedmont Municipal Power Agency 121 Village Drive Greer, South Carolina 29651 Ms. Karen E. Long Assistant Attorney General North Carolina Department of Justice Post Office Box 629 Raleigh, North Carolina 27602 NCEM REP Program Manager 4713 Mail Service Center Raleigh, North Carolina 27699-4713 North Carolina Electric Membership Corp.
Post Office Box 27306 Raleigh, North Carolina 27611 Senior Resident Inspector U. S. Nuclear Regulatory Commission 4830 Concord Road York, South Carolina 29745 Henry Porter, Assistant Director Division of Waste Management Bureau of Land and Waste Management Dept. of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201-1708 Mr. R. L. Gill, Jr., Manager Nuclear Regulatory Issues and Industry Affairs Duke Energy Corporation 526 South Church Street, Mail Stop EC05P Charlotte, North Carolina 28202 Saluda River Electric Post Office Box 929 Laurens, South Carolina 29360 Mr. Peter R. Harden, IV, Vice President Customer Relations and Sales Westinghouse Electric Company 6000 Fairview Road, 12th Floor Charlotte, North Carolina 28210 Mary Olson Director of the Southeast Office Nuclear Information and Resource Service 729 Haywood Road, 1-A Post Office Box 7586 Asheville, North Carolina 28802
Catawba Nuclear Station cc:
Mr. T. Richard Puryear Owners Group (NCEMC)
Duke Energy Corporation 4800 Concord Road York, South Carolina 29745 Richard M. Fry, Director Division of Radiation Protection N. C. Dept. of Environment, Health, and Natural Resources 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Diane Curran Harmon, Curran, Spielberg &
Eisenberg, LLP 1726 M Street, N.W., Suite 600 Washington, DC 20036