CNL-16-188, Withdrawal of Browns Ferry Unit 2 Fifth Ten Year Interval Request for Relief 2-ISI-30 and Response to NRC Request for Additional Information Related to Browns Ferry Unit 3 Fourth Ten Year Interval Request for Relief 3-ISI-27 for the Use o

Withdrawal of Browns Ferry Unit 2 Fifth Ten Year Interval Request for Relief 2-ISI-30 and Response to NRC Request for Additional Information Related to Browns Ferry Unit 3 Fourth Ten Year Interval Request for Relief 3-ISI-27 for the Use of

ML16343A935
Person / Time
Site:	Browns Ferry
Issue date:	12/07/2016
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CAC MF7795, CAC MF7796, CNL-16-188
Download: ML16343A935 (3)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-16-188 December 7, 2016 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 2 and 3 Renewed Facility Operating License Nos. DPR-52 and DPR-68 NRC Docket Nos. 50-260 and 50-296

Subject:

Withdrawal of Browns Ferry Unit 2 Fifth Ten Year Interval Request For Relief 2-ISI-30 and Response to NRC Request for Additional Information Related to Browns Ferry Unit 3 Fourth Ten Year Interval Request for Relief 3-ISI-27 for the Use of Alternatives to Certain American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section XI Requirements (CAC Nos. MF7795 and MF7796)

References:

1. TVA Letter to NRC, CNL-16-072, "Browns Ferry Nuclear Plant Units 2 and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection and Augmented Programs, Unit 2 Fifth Ten Year Interval Request for Relief 2-ISI-30 and Unit 3 Fourth Ten Year Interval Request for Relief 3-ISI-27, dated June 10, 2016 (ML16165A234)

2. NRC Letter to TVA, Browns Ferry Nuclear Plant, Units 2 and 3 - Request for Additional Information Related to Relief Request for the Use of Alternatives to Certain American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section XI Requirements (CAC Nos. MF7795 and MF7796), dated October 27, 2016 (ML16288A018)

By letter dated June 10, 2016 (Reference 1), Tennessee Valley Authority (TVA) submitted requests for alternative from Inservice Inspection (ISI), 2-ISI-30 and 3-ISI-27, pertaining to Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code for Browns Ferry Nuclear Plant (BFN) Units 2 and 3, respectively. The proposed alternative would provide permanent relief from reactor vessel circumferential weld examinations currently required by the ASME B&PV Code Section XI for the periods of extended operation ending June 28, 2034, for BFN Unit 2 and July 2, 2036, for BFN Unit 3.

U.S. Nuclear Regulatory Commission CNL-16-188 Page 2 December 7, 2016 The Reference 2 letter provided two Nuclear Regulatory Commission (NRC) Requests for Additional Information (RAls) related to the requests for alternative. RAl -1 was applicable to both BFN Unit 2 (2-ISl-30) and BFN Unit 3 (3-ISl-27) . RAl-2 was applicable to only BFN Unit 2. TVA agreed to respond to the RAls by December 7, 2016.

In RAl-2 , the NRC requested an updated analysis of the failure probability for the limiting RPV axial weld at BFN Unit 2. Completion of the updated analysis is in progress and is currently scheduled to be complete at the end of 2017. As a result , TVA is not presently able to provide the requested analysis within a schedule that supports the approval date requested by TVA in Reference 1. Therefore, TVA hereby withdraws request for alternative 2-ISl-30 , applicable to BFN Unit 2. TVA plans to resubmit a request for alternative for BFN Unit 2 after the updated failure probability analysis is completed. Due to the withdrawal of 2-IS l-30 , TVA is not providing a response to RAl-1 or RAl-2 for BFN Unit 2.

The enclosure to this letter provides the TVA response to RAl-1 in support of request for alternative 3-ISl-27 , applicable to BFN Unit 3.

There are no new regulatory commitments contained in this letter. If you have any questions, please contact Ed Schrull at (423) 751 -3850.

• , e President, Nuclear Licensing

Enclosure:

Response to NRC Request for Additional Information RAl-1 for Browns Ferry Nuclear Plant, Unit 3, American Society of Mechanical EngineersSection XI, lnservice Inspection and Augmented Program , Fourth Ten Year Interval Request for Relief 3-ISl-27 cc (w/Enclosures) :

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant

ENCLOSURE Response to NRC Request for Additional Information RAI-1 for Browns Ferry Nuclear Plant, Unit 3, American Society of Mechanical EngineersSection XI, Inservice Inspection and Augmented Program, Fourth Ten Year Interval Request for Relief 3-ISI-27 NRC RAI-1 Please state whether the neutron fluence values provided in Table 2 of your submittal for Request for Alternative 2-ISI-30 (BFN 2) and 3-ISI-27 (BFN 3) are applicable for the proposed 14.3 percent extended power uprate conditions, as proposed in your license amendment request dated September 21, 2015 (ADAMS Accession No. ML15282A152)

TVA Response As stated in the cover letter, request for alternative 2-ISI-30, applicable to Browns Ferry Nuclear Plant (BFN), Unit 2, is being withdrawn.

For request for alternative 3-ISI-27, applicable to BFN Unit 3, the neutron fluence values provided in Table 2 of 3-ISI-27 are applicable for the proposed 14.3 percent extended power uprate conditions, as proposed in the TVA license amendment request dated September 21, 2015 (Reference).

Reference Letter from TVA to NRC, CNL-15-169, "Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU)," dated September 21, 2015 (ML15282A152)

CNL-16-188 Enclosure - Page 1 of 1