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

Notification of Intent to Use Code Case N-716-1

ML14365A034
Person / Time
Site:	Sequoyah
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 10 CFR 50.55a 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

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 10-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 10-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