ML11173A047
| ML11173A047 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/14/2011 |
| From: | Martin R Plant Licensing Branch II |
| To: | Ajluni M Southern Nuclear Operating Co |
| Martin R, NRR/DORL/LPL2-1, 415-1493 | |
| References | |
| TAC ME5966 | |
| Download: ML11173A047 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 July 14, 2011 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION ON INSERVICE INSPECTION PLAN (TAC NO.
ME5966)
Dear Mr. Ajluni:
By letter dated March 28,2011 (Agencywide Documents Access and Management System Accession No. ML110871951), Southern Nuclear Operating Company, Inc., submitted a request for relief for Joseph M. Farley Nuclear Plant, Unit 1, that would allow the use of an alternate depth-sizing qualification for volumetric examinations of the reactor pressure vessel nozzle-to safe end dissimilar metal welds from the inside surface. The U.S. Nuclear Regulatory Commission staff has reviewed the information and has identified that additional information is needed to complete the review as stated in the enclosure.
Please provide a response within thirty (30) days of the date of this letter.
Sincerely,
/,9~4/21~
J,~E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-348
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST FNP-ISI-RR-01 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-348 By letter dated March 28, 2011, (Agencywide Documents Access and Management System Accession No. ML110871951), Southern Nuclear Operating Company, Inc. (SNC), submitted request for relief FNP-ISI-RR-01 for Joseph M. Farley Nuclear Plant, Unit 1 (Farley Unit 1), that would allow the use of an alternate depth-sizing qualification for volumetric examinations of the reactor pressure vessel nozzle-to-safe end dissimilar metal (DMW) welds from the inside surface. Specifically, the licensee proposed an alternative to the American Society of Mechanical Engineers, Boiler And Pressure Vessel Code,Section XI, Appendix VIII, Supplement 10 (DMWs), depth-sizing acceptance root mean square error (RMSE) performance demonstration requirements (PDI). To complete the review, we request the following additional information.
- 1. Some details about the welds were not included in the relief request. Provide detailed cross-sectional diagrams including sketches of the weld area. These diagrams should identify the materials (stainless steel, carbon steel, nickel alloy) of the base metal, weld, and buttering and show dimensions (Nominal inside diameter (lD), outside diameter (OD), and wall thickness) for each of the welds.
2.. Some of the ultrasonic testing (UT) techniques qualified by PDI from the ID have difficulty in detecting axial cracks, and use supplemental eddy current testing for this purpose. Will any supplemental examinations, such as eddy current testing, be performed on the ID to detect possible surface-breaking flaws and to confirm if possible indications detected by UT are surface breaking?
- 3. The cited difficulties in depth-sizing come from issues with the specific PDI mock-ups used for Appendix VIII, Supplement 10 ID depth-sizing qualifications. Specifically, these samples do not have smooth <<1/32 inch waviness) 10 surfaces. It is not clear if the limitations in the PDI specimens apply to the inspection conditions in Farley Unit 1.
3a.
Has profilometry been previously performed on any of these welds? If yes, provide a description of the surface waviness and estimate the percentage of areas with suspected probe lift-off.
3b.
If the PDI mockups have significantly different ID surface conditions than the welds in this relief request, provide a discussion on the time and effort necessary to produce mockups that match the ID conditions in the welds covered in this relief request.
- 4. All of the examinations described in this relief request are to be preformed from the inner diameter of the welds. If the vendor has qualified for depth-sizing from the OD, please provide a discussion on the difficulties that would inhibit depth sizing from the OD.
Enclosure
- 2
- 5. Some licensees have located representative mockups (with smooth 10 surfaces) containing cracks. UT vendors have used these mockups to demonstrate 10 depth-sizing RMSE capabilities. Also, vendors have independently participated in blind and non-blind round robin demonstrations on mockups containing representative cracks.
- a. Provide a discussion of SNC's efforts to provide representative mockups containing cracks (or simulated cracks with crack-like responses) with 10 surfaces similar to the surfaces used for successful 00 depth-sizing qualifications.
- b. Provide a discussion of your vendor's participation in 10 depth-sizing demonstrations that may have been independent of the POI program. If available, include a description of the specimens (10 surface waviness, configurations, and materials) and cracks, types of tests (blind or not-blind), differences between the procedures and personnel used for the demonstrations and those being proposed for examining the subject welds, a summary of results and RMSE values, and the organization sponsoring and/or proctoring the demonstrations.
July 14, 2011 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION ON INSERVICE INSPECTION PLAN (TAC NO.
ME5966)
Dear Mr. Ajluni:
By letter dated March 28, 2011 (Agencywide Documents Access and Management System Accession No. ML110871951), Southern Nuclear Operating Company, Inc., submitted a request for relief for Joseph M. Farley Nuclear Plant, Unit 1, that would allow the use of an alternate depth-sizing qualification for volumetric examinations of the reactor pressure vessel nozzle-to safe end dissimilar metal welds from the inside surface. The U.S. Nuclear Regulatory Commission staff has reviewed the information and has identified that additional information is needed to complete the review as stated in the enclosure.
Please provide a response within thirty (30) days of the date of this letter.
Sincerely, IRA!
Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-348
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1 R/F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsRgn2MailCenter Resource RidsNrrLAMOBrien Resource RidsOgcRp Resource RidsNrrDciCpnb Resource SCumblidge, RES DAiley, NRR RidsNrrPMFarley Resource Jyemal ae ADAMS A ccesslon N0.: ML11173A047
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- 1 d t d 6/17/11 OFFICE NAME DATE DORULPL2-1/PM RMartin 07/11/11 DORULPL2-1/LA MO'Brien 06/29/11 DCI/CPNB/BC(A)
DAiley
- 06117111 DORULPL2-1/BC GKulesa (PBoyle for) 07/14/11 DORULPL2-1/PM RMartin 07/14/11 OFFICIAL RECORD COPY