ML062210436
| ML062210436 | |
| Person / Time | |
|---|---|
| Site: | Vogtle, Farley  |
| Issue date: | 08/15/2006 |
| From: | Martin R NRC/NRR/ADRO/DORL/LPLII-1 |
| To: | Grissette D Southern Nuclear Operating Co |
| Martin R, NRR/DORL, 415-1493 | |
| References | |
| TAC MD2482, TAC MD2483, TAC MD2484 | |
| Download: ML062210436 (5) | |
Text
August 15, 2006 Mr. D. E. Grissette Vice President Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 1 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2, REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST NO. ISI-GEN-ALT-06-02 (TAC NOS. MD2482, MD2483 and MD2484)
Dear Mr. Grissette:
By letter dated June 29, 2006, Southern Nuclear Company (SNC) submitted Relief Request No. ISI-GEN-ALT-06-02 proposing an alternative to certain requirements of the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code) at Joseph M.
Farley Nuclear Plant, Unit 1 and Vogtle Electric Generating Plant, Units 1 and 2. Specifically, SNC proposed using ASME Code Case N-696, Qualification Requirements for Appendix VIII Piping Examinations Conducted From the Inside Surface.
The Nuclear Regulatory Commission staff has reviewed that response and has identified a need for additional information as stated in the enclosure. We request your most expeditious response to these issues to support continuation of our review.
Sincerely,
/RA/
Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-424, and 50-425
Enclosure:
Request for Additional Information cc w/encl: See next page
Mr. D. E. Grissette August 15, 2006 Vice President Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 1 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2, REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST NO. ISI-GEN-ALT-06-02 (TAC NOS. MD2482, MD2483 and MD2484)
Dear Mr. Grissette:
By letter dated June 29, 2006, Southern Nuclear Company (SNC) submitted Relief Request No. ISI-GEN-ALT-06-02 proposing an alternative to certain requirements of the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code) at Joseph M.
Farley Nuclear Plant, Unit 1 and Vogtle Electric Generating Plant, Units 1 and 2. Specifically, SNC proposed using ASME Code Case N-696, Qualification Requirements for Appendix VIII Piping Examinations Conducted From the Inside Surface.
The Nuclear Regulatory Commission staff has reviewed that response and has identified a need for additional information as stated in the enclosure. We request your most expeditious response to these issues to support continuation of our review.
Sincerely,
/RA/
Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-424, and 50-425
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
Public RidsNrrPMRJervey RidsNrrDorlLpl2-1 RidsNrrDNaujock LPL2-1 R/F RidsAcrsAcnwMailCenter RidsNrrPMRMartin(hard copy)
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RidsNrrLAMObrien Accession No.: ML062210436 NRR-88 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/CPNB/BC NRR/LPL2-1/BC NAME RMartin RSola TChan by memo ML062230060 EMarinos DATE 08/11/06 08/11/06 08/10/06 08/10/06 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST NO. ISI-GEN-ALT-06-02 FOR RENEWED FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 AND FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 AND FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 The licensee requested to use ASME Code Case N-696 (N-696) for the examination of selected dissimilar metal welds. N-696, Paragraph 3.3(d) states that Supplement 2 or Supplement 3 procedures, equipment, and personnel are qualified for depth-sizing when the flaw depths estimated by ultrasonics, as compared with the true depths, do not exceed 0.125 in. (3mm)
RMS [root mean square], when they are combined with a successful Supplement 10 qualification. The proposed alternative is specifically for the use of N-696. In the section identified as the "Basis for Use," there is an implied alternative for handling performance demonstrated depth-sizing values that are greater than 0.125 in. RMS.
In the submittal section "Basis for Use," a discussion on depth sizing values greater than 0.125 in. RMS was presented. The purpose of the discussion is not clear because it is suggesting another alternative separate from the submittal section "Proposed Alternative." If a depth sizing value greater than 0.125 in. is part of the proposed alternative, provide the alternative depth-sizing value. The basis for the acceptability of an RMS value greater than the ASME Code required value is that any required flaw evaluation adds to the measured flaw size, the difference between the ASME Code 0.125" RMS performance demonstration acceptance criterion and the larger RMS value from the vendor's procedure performance demonstration.
The staff considers the licensee's approach to address the current inability to meet the ASME Code-required UT depth-sizing RMS requirement as a short-term solution. Vendors continue to make improvements to their UT sizing capabilities. These improvements may reduce the difference between the depth-sizing RMS Code-requirement and currently achievable RMS values. Discuss options Farley and Vogtle have considered for the examination of the subject welds. Explain why the ASME Code RMS value is not achievable for the selected vendor.
Joseph M. Farley Nuclear Plant, Unit 1 cc:
Mr. J. R. Johnson General Manager Southern Nuclear Operating Company, Inc.
P.O. Box 470 Ashford, AL 36312 Mr. B. D. McKinney, Licensing Manager Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201-1295 Mr. M. Stanford Blanton Balch and Bingham Law Firm P.O. Box 306 1710 Sixth Avenue North Birmingham, AL 35201 Mr. J. Gasser Executive Vice President Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201 State Health Officer Alabama Department of Public Health 434 Monroe St.
Montgomery, AL 36130-1701 Chairman Houston County Commission P.O. Box 6406 Dothan, AL 36302 Resident Inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, AL 36319
Vogtle Electric Generating Plant, Units 1 & 2 cc:
Mr. N. J. Stringfellow Manager, Licensing Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201-1295 Mr. T. E. Tynan, General Manager Vogtle Electric Generating Plant Southern Nuclear Operating Company, Inc.
7821 River Road Waynesboro, GA 30830 Mr. Jeffrey T. Gasser Executive Vice President Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201-1295 Mr. Steven M. Jackson Senior Engineer - Power Supply Municipal Electric Authority of Georgia 1470 Riveredge Parkway, NW Atlanta, GA 30328-4684 Mr. Reece McAlister Executive Secretary Georgia Public Service Commission 244 Washington St., SW Atlanta, GA 30334 Mr. Harold Reheis, Director Department of Natural Resources 205 Butler Street, SE, Suite 1252 Atlanta, GA 30334 Attorney General Law Department 132 Judicial Building Atlanta, GA 30334 Mr. Laurence Bergen Oglethorpe Power Corporation 2100 East Exchange Place P.O. Box 1349 Tucker, GA 30085-1349 Arthur H. Domby, Esquire Troutman Sanders Nations Bank Plaza 600 Peachtree Street, NE Suite 5200 Atlanta, GA 30308-2216 Resident Inspector Vogtle Plant 8805 River Road Waynesboro, GA 30830 Office of the County Commissioner Burke County Commission Waynesboro, GA 30830 Mr. D. E. Grissette, Vice President Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201