ML14245A363

Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 5.7.2.10, Reactor Coolant Pump Flywheel Inspection Program

ML14245A363
Person / Time
Site:	Watts Bar
Issue date:	09/08/2014
From:	Dion J Watts Bar Special Projects Branch
To:	James Shea Tennessee Valley Authority
Minarik A
References
TAC MF4525
Download: ML14245A363 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 8, 2014 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801

SUBJECT:

WATTS BAR NUCLEAR PLANT, UNIT NO. 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 5.7.2.10, REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM {TAG NO. MF4525)

Dear Mr. Shea:

By letter dated July 24, 2014, Tennessee Valley Authority submitted a license amendment request for Watts Bar Nuclear Plant, Unit 1. The proposed amendment request would revise the inspection interval of the Reactor Coolant Pump flywheel from the currently approved interval as described in Regulatory Guide 1.14, Revision 1, August 1975 (FACT CHECK) to 20 years using the Consolidated Line Item Improvement Process (CLIIP) using Technical Specifications Task Force Traveler (TSTF)-421 as a reference. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (1 0 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.

J. Shea While the staff has accepted the submittal for review, the staff believes that this amendment made use of both TSTF-421 and TSTF-237, Revision 1, "Relaxation of Reactor Coolant Pump Flywheel Examinations." Therefore, the staff cannot commit to the metrics and timelines associated with a review that implements the CLIIP. That being said, some of the conclusions are directly applicable to this application, including the No Significant Hazards Consideration provided in the model Safety Evaluation for TSTF-421 that was noticed on October 22, 2003 (68 FR 60422).

If you have any questions, please contact Anthony Minarik at (301) 415-6185 or you may contact me at (301} 415-1564.

Sincerely,

~ (f* ~v~'-

Siva P. Lingam, Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390 cc: Distribution via Listserv

J.Shea While the staff has accepted the submittal for review, the staff believes that this amendment made use of both TSTF-421 and TSTF-237, Revision 1, "Relaxation of Reactor Coolant Pump Flywheel Examinations." Therefore, the staff cannot commit to the metrics and timelines associated with a review that implements the CLIIP. That being said, some of the conclusions are directly applicable to this application, including the No Significant Hazards Consideration provided in the model Safety Evaluation for TSTF-421 that was noticed on October 22, 2003 (68 FR 60422).

If you have any questions, please contact Anthony Minarik at (301) 415-6185 or you may contact me at (301) 415-1564.

Sincerely, IRA/

Siva P. Lingam, Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390 cc: Distribution via Listserv DISTRIBUTION:

PUBLIC LPWB Reading File RidsAcrsAcnw_MaiiCTR Resource RidsNrrDorl Resource RidsNrrDoriDpr Resource RidsNrrDorllpwb Resource RidsNrrLABCiayton Resource RidsNrrPMWattsBar1 Resource RidsRgn2MaiiCenter Resource ADAMS Accession No.: ML14245A363 OFFICE LPWB/PMiT LPWB/PM LPWB/LA LPWB/BC LPWB/PM NAME AMinarik Slingam BCiayton JQuichocho Slingam DATE 08/28/2014 09/04/2014 09/04/2014 09/08/2014 09/08/2014 OFFICIAL RECORD COPY