ML030220227
| ML030220227 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/22/2003 |
| From: | Cotton K NRC/NRR/DLPM/LPD2 |
| To: | Byrne S South Carolina Electric & Gas Co |
| Cotton K R, NRR/DLPM, 301-415-1438 | |
| References | |
| TAC MB6647 | |
| Download: ML030220227 (4) | |
Text
January 22, 2003 Mr. Stephen A. Byrne Senior Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, South Carolina 29065
SUBJECT:
V.C. SUMMER NUCLEAR STATION REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST NO. RR-II-08 (TAC NO. MB6647)
Dear Mr. Byrne:
By letter dated October 30, 2002, South Carolina Electric and Gas Company, the licensee for V.C. Summer Nuclear Station, submitted request for relief No. RR-II-08 regarding alternate inspections of the Steam Generator Primary Nozzle Inner Radius as required by the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 1989 Edition.
The U.S. Nuclear Regulatory Commission staff has reviewed your request and determined that it did not provide sufficient information to grant the request for relief No. RR-II-08 regarding alternate inspections of the Steam Generator Primary Nozzle Inner Radius as required by ASME Code,Section XI, 1989 Edition. The enclosed request for additional information (RAI) contains specific questions related to these issues. I have discussed this RAI with Mr. Jim Turkett, Licensing Engineer, Virgil C. Summer Nuclear Station, and he agreed to respond to this request by January 29, 2003. Please contact me if you have any questions.
Sincerely,
/RA/
Karen R. Cotton, Project Manager, Section 1 Project Directorate ll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosure:
Request for additional information cc w/encl: See next page
ML030220277 OFC PDII-1/PM PDII-2/LA PDII-1/SC NAME KCotton BClayton JNakoski DATE 1/21/03 1/21/03 1/21/03
Enclosure REQUEST FOR ADDITIONAL INFORMATION INSERVICE INSPECTION RELIEF REQUEST RR-II-08 V.C. SUMMER NUCLEAR STATION 1.
The submittal states that the relief is being requested in accordance with Title 10, Code of Federal Regulations (10 CFR), Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii). Relief such as this has been authorized using 10 CFR 50.55a(a)(3)(ii), the American Society of Mechanical Engineers Boiler and Pressure Vessel Code since (the Code) requirements reflect hardship upon the licensee. To build a case for such hardship, please provide:
- a. A comparison of worker radiation dosage between the ultrasonic and visual examination techniques.
- b. The drawings (or pictorial discussion) showing the type and location of interferences with the Code-required ultrasonic examination. The drawing number was provided in the submittal but not the drawing itself. Identify the percent coverage that is able to be achieved on these nozzles using Code-required ultrasonic examinations.
c.
A material description (cast carbon steel, cast stainless steel, cast nickel-based alloys, etc.) and dimensions (nozzle nominal inside diameter, nominal wall-thicknesses).
2.
The staff has been authorizing an enhanced VT-1 with demonstrated capabilities of resolving a 1-mil wire or equivalent flaw for the specified inner nozzle radii. This is in keeping with the current rule published in the Federal Register, 67 FR 60541, dated September 26, 2002, regarding 10 CFR 50.55a(b)(2)(xxi). The proposed alternative is relying only on the Code-requirements for VT-1 of ensuring the detection of cracks.
- a. Discuss the demonstration used for comparing the effectiveness of the enhanced VT-1 and UT.
- b. Explain the process used for selecting flaw types and sizes used for demonstrating effectiveness.
c.
Provide a description of the flaws.
- d. Discuss the variations with respect to true values.
3.
Discuss the percentage of Code-required surface coverage that will be examined with the alternate VT examination for each nozzle inner radius.
4.
Discuss the procedure for examination of the steam generator primary nozzle inner radius done during the first Inservice Inspection Interval for V.C. Summer Nuclear Station.
Mr. Stephen A. Byrne VIRGIL C. SUMMER NUCLEAR STATION South Carolina Electric & Gas Company cc:
Mr. R. J. White Ms. Kathryn M. Sutton, Esquire Nuclear Coordinator Winston & Strawn Law Firm S.C. Public Service Authority 1400 L Street, NW c/o Virgil C. Summer Nuclear Station Washington, DC 20005-3502 Post Office Box 88, Mail Code 802 Jenkinsville, South Carolina 29065 Resident Inspector/Summer NPS c/o U.S. Nuclear Regulatory Commission 576 Stairway Road Jenkinsville, South Carolina 29065 Chairman, Fairfield County Council Drawer 60 Winnsboro, South Carolina 29180 Mr. Henry Porter, Assistant Director Division of Waste Management Bureau of Land & Waste Management Department of Health & Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Mr. Gregory H. Halnon, General Manager Nuclear Plant Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station, Mail Code 303 Post Office Box 88 Jenkinsville, South Carolina 29065 Mr. Melvin N. Browne, Manager Nuclear Licensing & Operating Experience South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station, Mail Code 830 Post Office Box 88 Jenkinsville, South Carolina 29065