SBK-L-13084, Revised Response to RAI B.2.1.3-5 and RAI 4.7.2-1 for License Renewal Application

Revised Response to RAI B.2.1.3-5 and RAI 4.7.2-1 for License Renewal Application

ML13135A005
Person / Time
Site:	Seabrook  (NPF-086)
Issue date:	05/08/2013
From:	Walsh K NextEra Energy Seabrook
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SBK-L-13084, TAC MF0464
Download: ML13135A005 (6)

Text

NExTera ENEROY 1,

May 8, 2013 SBK-L-13084 U.S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 Seabrook Station NextEra Energy Seabrook License Renewal Application Revised Response to RAI B.2.1.3-5 and RAI 4.7.2-1

References:

1. NextEra Energy Seabrook, LLC letter SBK-L-10077, "Seabrook Station Application for Renewed Operating License," May 25, 2010. (Accession Number ML101590099)

2. NextEra Energy Seabrook, LLC letter SBK-L-11002, "Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs-Set 4," January 13, 2011. (Accession Number MLL110140809)

3. NextEra Energy Seabrook, LLC letter SBK-L-11015, "Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Sets 6, 7, and 8," February 3, 2011. (Accession Number ML110380081)

4. Amendment 134 to facility Operating License No. NPF-86 for the Seabrook Station, Unit No. 1, "Seabrook Station, Unit No.1 - Issuance of Amendment Regarding the Extension of the Inspection of Interval for the Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process (TAC No. MF0464)," April 4, 2013.

(Accession Number ML13028A146)

In Reference 1, NextEra Energy Seabrook, LLC (NextEra) submitted an application for a renewed facility operating license for Seabrook Station Unit I in accordance with the Code of Federal Regulations, Title 10, Parts 50, 51, and 54.

In Reference 2, NextEra responded to the NRC requests for additional information related to the aging management program associated with Metal Fatigue of Reactor Coolant Pressure Boundary (RAI B.2.3.1-5). This response has been revised to remove fracture mechanics evaluation as a corrective action alternative.

In Reference 3, NextEra responded to the NRC requests for additional information related to the inspection of the Reactor Coolant Pump flywheels (RAI 4.7.2-1). This response has been revised to incorporate Amendment 134 (Reference 4) to the facility Operating License regarding flywheel inspection frequency.

NextEra Energy Seabrook, LLC.

A.

f 626 Lafayette Rd, Seabrook, NH 03874

Unifed States Nuclear Regulatory Commission SBK-L-13 084 / Page 2 Provided in this Supplement are changes to the License Renewal Application (LRA). To facilitate understanding, the changes are explained, and where appropriate, portions of the LRA are repeated with the change highlighted by strikethroughs for deleted text and bolded italics for inserted text.

There are no new or revised regulatory commitments contained in this letter.

If there are any questions or additional information is needed, please contact Mr. Richard R.

Cliche, License Renewal Project Manager, at (603) 773-7003.

If you have any questions regarding this correspondence, please contact Mr. Michael O'Keefe, Licensing Manager, at (603) 773-7745.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on Sincerely, Kevin T. Walsh Site Vice President NextEra Energy Seabrook, LLC

Unifed States Nuclear Regulatory Commission SBK-L-13 084 / Page 3 - Revised Response to RAI B.2.1.3-5 and RAI 4.7.2-1 and Associated LRA Changes cc:

W.M. Dean, J. G. Lamb, M. Jennerich R. A. Plasse Jr.,

L. M. James, NRC Region I Administrator NRC Project Manager, Project Directorate 1-2 NRC Resident Inspector NRC Project Manager, License Renewal NRC Project Manager, License Renewal Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 to SBK-L-13084 Revised Response to RAI B.2.1.3-5 and RAI 4.7.2-1 and Associated LRA Changes

Uniied States Nuclear Regulatory Commission Page 2 of 3 SBK-L-13084 / Enclosure 1

1. Revised NextEra Energy Seabrook Response to RAI B.2.3.1-5 NextEra Energy Seabrook will not be using fracture mechanics evaluation for performing fatigue assessments in the aging management program associated with the Metal Fatigue of Reactor Coolant Pressure Boundary Program. The response to RAI B.2.3.1-5 provided in SBK-L-11002, dated January 13, 2011 has been revised as follows:

GALL AMP X.DV 1 program element does not spe.ifi.ally address the use of a ffratur*.

Pressure Vessel Code,Section X!, Appendix L, provides guidancc for methods fer performfing fatigue assessments to dctermn ae tability fer continued servýice of reactor coolant system and primary pressur boundary.omponents subje..td to the.mal and mechanical fatigue leads. The AMSE Code specifies two methods for per-forming fatigue assessments; a fatigue usage faetor evaluation and a flaw toler-ance evaluation (using fraetur-e mfechanics teehniques). These two evaluation methods are the analy~ieal options provided in LRA Section B.2.3.4. Use of a fracture mechanics evaluation for performing fatigue assessments will not be utilized as a corrective action alternative. The following changes have been made to the Seabrook Station License Renewal Application:

1. On Page B-215 of Section B.2.3.1, Metal Fatigue of Reactor Coolant Pressure Boundary, the 2nd corrective action has been removed from aging management program as follows:

1.

Reanalyze affected component(s) for an increase in the number of that specific transient while accounting for other component-affecting plant transients that may be projected not to achieve their analyzed levels.

2.

Perform a fracture mechanics evaluation of a postulated flaw in affected plant components, which, when coupled with an inservice inspection program, will serve to demonstr-ate flaw~ tolerant behavior.

3.

Repair the affected component.

4.

Replace the affected component.

2. Revised NextEra Energy Seabrook Response to RAI 4.7.2-1 Amendment 134 to the Facility Operating License No. NPF-86 for Seabrook Station, Unit No. I was issued on April 4, 2013 (ML13028A146). This amendment extends the reactor coolant pump (RCP) flywheel examination frequency from 10 year inspection interval to an interval not to exceed 20 years. Based on this amendment, the response to RAI 4.7.2-1 provided in SBK-L-11015, dated February 3, 2011 has been revised as follows:

1) During the first 20 years of operation at Seabrook Station, RCP flywheel inspections including surface and volumetric examinations of all of the RCP motor flywheels have been performed in accordance with Technical Specification requirements, resulting in no unacceptable indications. The review of the flywheel surface and volumetric examinations for the RCP motor flywheels has found that all inspections to date had

United States Nuclear Regulatory Commission Page 3 of 3 SBK-L-13084 / Enclosure 1 acceptable results. There were no indications found in any of the ISI inspection reports that required a flaw evaluation to be submitted to the staff for evaluation as required by regulatory position C.4.b(5) of Regulatory Guide 1.14, Rev. 1

2) During the period of extended operation, Seabrook Station will continue the ISI of RCP flywheels consistent with the approved operating license which eifrently requires ISI of the RCP Flywheel at an interval not to exceed 20 years. every ten years.

NextEra Energy Seabro.k is evaluating a Lie.nse Amendment Request for-apprval to ehanget Trfaveler-TSTF 421, "Revisien to RCP Flywheel inspection Program (WCAP 15666)-,

which ealls for-inspection cver~y 20 year-s.