CNL-14-231, Notification of Intent to Use Code Case N-716-1

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Notification of Intent to Use Code Case N-716-1
ML14365A034
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 12/22/2014
From: James Shea
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-14-231
Download: ML14365A034 (2)


Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-14-231 December 22, 2014 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

Notification of Intent to Use Code Case N-716-1 10 CFR 50.55a

References:

1. TVA Letter to NRC, "Sequoyah Nuclear Plant- (SON) Risk-Informed lnservice Inspection (RI-ISI) Program And Updated lnservice Inspection (lSI)

Program For Third 1 0-Year Interval," dated April 21, 2006 (ADAMS Accession No. ML061210105)

2. NRC Letter to TVA, "Sequoyah Nuclear Plant, Units 1 And 2-Risk-Informed lnservice Inspection Program for the Third 1 0-Year Intervals (TAC NOS.

MD1452, MD1453, MD1454 AND MD1455)," dated April 30, 2007 (ADAMS Accession No. ML071070248)

By letter dated April 21, 2006 (Reference 1), the Tennessee Valley Authority (TVA) submitted Requests for Relief to use the Sequoyah Nuclear Plant (SON) Risk-Informed lnservice Inspection (RI-ISI) Program as an alternative to ASME Section XI requirements for selecting the number and locations of the elements to be examined. By letter April, 30, 2007 Reference 2), the NRC approved the application of SON RI-ISI Program for the Third 10-Year Interval for SON Units 1 and 2. For SON, the Third lnservice Inspection (lSI) Interval began on June 1, 2006.

Regulatory Guide 1.147, lnservice Inspection Code Case Acceptability, ASME Section XI,

Division 1, Revision 17 as noticed in the Federal Register (79 FR 65798) on November 5, 2014, approves the use of ASME Code Case N-716-1, "Alternative Piping Classification and Examination Requirements,Section XI, Division 1." For the third period of the third interval, TVA will apply ASME Code Case N-716-1, in lieu of the alternative approved in Reference 2.

U.S. Nuclear Regulatory Commission CNL-14-231 Page 2 December 22, 2014 There are no new regulatory commitments contained in this letter. Please address any questions regarding this submittal to Erin Henderson at (423) 843-7170.

e President, Nuclear Licensing cc :

NRC Regional Administrator-Region II NRC Senior Resident Inspector-Sequoyah Nuclear Plant