ML14189A020

Request for Additional Information

ML14189A020
Person / Time
Site:	Farley
Issue date:	07/15/2014
From:	Shawn Williams Plant Licensing Branch II
To:	Pierce C Southern Nuclear Operating Co
Williams S
References
TAC MF4206, TAC MF4207
Download: ML14189A020 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 July 15, 2014 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Co., Inc.

P.O. Box 1295, Bin 038 Birmingham, AL 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF4206 AND MF4207)

Dear Mr. Pierce:

By letter dated May 28, 2014, the Southern Nuclear Operating Company, Inc., submitted a request for approval to use an alternative to the American Society of Mechanical Engineers (ASME)Section XI code requirement of subarticle IWC-5220 for leakage testing of the Class 2 reactor vessel flange leakoff lines.

The Nuclear Regulatory Commission staff has determined that additional information is needed as discussed in the Enclosure. We request that SNC respond within 30 days of the date of this letter. Please note that the. NRC staff's review is continuing and further requests for information may be developed.

Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor, Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION JOSEPH M. FARLEY NUCLEAR PLANT REQUEST FOR ALTERNATIVE (FNP-ISI-ALT-16)

DOCKET NOS. 50-348 AND 50-364 By letter dated May 28, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14148A492), Southern Nuclear Operating Company, submitted for staff review and approval of lSI Program Alternative Request FNP-ISI-ALT-16, which requests an alternative to the ASME Section XI code requirement of subarticle IWC-5220 for pressure testing of the Class 2 reactor vessel flange leak-off line each inspection period. To complete its review, the NRC staff requests the following additional information.

RAI1 Describe the Joseph M. Farley Nuclear Plant operating experience with regard to reactor pressure vessel flange 0-ring leakage and/or leak-off line leakage (i.e. history of any leakage, cause, corrective actions).

RAI2 ASME Code Case N-805, Reference 1 of FNP-ISI-ALT-16 states that it is the opinion of the ASME Committee that as an alternative the leakage test of the Class 1 or 2 portions of the leak detection system shall be conducted at ambient conditions after the refueling cavity has been filled to its "normal" refueling water level for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. In the first paragraph of the Proposed Alternative and Basis for Use section of FNP-ISI-ALT-16 it states the test shall be conducted at ambient conditions after the refueling cavity has been flooded to its "minimum" water level for refueling operations of 23 feet above the RPV flange for at least four hours.

Is 23 feet above the RPV flange also the "normal" refueling water level? If not, please justify performing the test at less than the "normal" refueling water level.

For the accessible portions of the Reactor Pressure Vessel Flange Leak-off Piping:

a. Discuss if the piping is insulated or not. If the piping is insulated, will the insulation be removed? If insulation will not be removed, discuss how the piping will be examined to identify potential pipe through-wall leakage.

b. If the subject piping is located in a high elevation or far away location from the examiner, describe how the pipe through-wall leakage can be identified.

• Enclosure

July 15, 2014 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Co., Inc.

P.O. Box 1295, Bin 038 .

Birmingham, AL 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF4206 AND MF4207)

Dear Mr. Pierce:

By letter dated May 28, 2014, the Southern Nuclear Operating Company, Inc., submitted a request for approval to use an alternative to the American Society of Mechanical Engineers (ASME)Section XI code requirement of subarticle IWC-5220 for leakage testing of the Class 2 reactor vessel flange leakoff lines.

The Nuclear Regulatory Commission staff has determined that additional information is needed as discussed in the Enclosure. We request that SNC respond within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed.

Sincerely,

/RAJ Shawn Williams, Senior Project Manager .

Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

Enclosure:

Request *for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPL2-1 R/F RidsAcrsAcnw_MaiiCTR Resource RidsNrrDoriDpr Resource RidsNrrDorllpl2-1 Resource RidsRgn2MaiiCenter Resource RidsNrrLASFigueroa Resource RidsNrrDe Resource RidsNrrPMFarley Resource KHoffman, NRR ADAMS Accession No.: ML14189A020 OFFICE LPL2-1/PM LPL2-1/LA LPL2-1/BC LPL2-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 07/08/14 07/15/14 07/15/14 07/15/14 OFFICIAL RECORD COPY