ML16053A187

Request for Additional Information, Request to Revise Technical Specification 6.8.3.j, Containment Leakage Rate Testing Program, to Extend Integrated Leak Rate Test Interval from 10 to 15 Years (CAC MF6176-MF6177)

ML16053A187
Person / Time
Site:	South Texas
Issue date:	03/01/2016
From:	Lisa Regner Plant Licensing Branch IV
To:	Koehl D South Texas
Regner L, NRR/DORL/LPLIV-1
References
CAC MF6176, CAC MF6177
Download: ML16053A187 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 1, 2016 Mr. Dennis L. Koehl President and CEO/CNO STP Nuclear Operating Company South Texas Project P.O. Box 289 VVadsworth, TX 77483

SUBJECT:

SOUTH TEXAS PROJECT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO A LICENSE AMENDMENT REQUEST TO EXTEND THE CONTAINMENT INTEGRATED LEAK RATE TEST FREQUENCY (CAC NOS. MF6176 AND MF6177)

Dear Mr. Koehl:

By letter dated April 29, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15128A352), as supplemented by letters dated June 29, October 8, and November 11, 2015 (ADAMS Accession Nos. ML15198A147, ML15293A509, and ML15329A304, respectively), STP Nuclear Operating Company (the licensee) requested changes to the Technical Specifications for South Texas Project, Units 1 and 2. The proposed change would permit the existing Containment Integrated Leak Rate Testing frequency to be extended from 10 years to 15 years on a permanent basis.

The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your application and determined that additional information, as described in the enclosure to this letter, is required to complete the review.

A draft version of the request for additional information (RAI) was provided to Mr. Lance Sterling of your staff via e-mail on February 18, 2016 (ADAMS Accession No. ML16050A026). The questions were discussed with your staff during a conference call the same day. The RAI was revised and a draft copy of the enclosed request for additional information (RAI) was provided to Mr. Lance Sterling of your staff via e-mail on February 24, 2016 (ADAMS Accession No. ML16057A032). The questions were discussed with your staff during a conference call on February 25, 2016. Your response is requested by March 21, 2016, to allow the NRC staff enough time to make a regulatory decision on your license amendment request by your requested date of April 30, 2016. If you are unable to provide a satisfactory RAI response by March 21, 2016, the staff is unlikely to meet your requested completion date.

D. Koehl If you have any questions, please contact me at 301-415-1906 or vis e-mail at Lisa. Reg ner@nrc.gov.

Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO EXTEND THE CONTAINMENT INTEGRATED LEAK RATE TEST FREQUENCY STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT. UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499 By letter dated April 29, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15128A352), as supplemented by letters dated June 29, October 8, and November 11, 2015 (ADAMS Accession Nos. ML15198A147, ML15293A509, and ML15329A304, respectively), STP Nuclear Operating Company (the licensee) requested changes to the Technical Specifications for South Texas Project (STP), Units 1 and 2. The proposed change would permit the existing Containment Integrated Leak Rate Testing frequency to be extended from 10 years to 15 years on a permanent basis.

The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that the following additional information is required to complete the review.

SCVB RAI:

The STP Updated Final Safety Analysis Report (UFSAR) Section 6.2.1.3, "Mass and Energy Release Analyses for Postulated Loss of Coolant Accidents," states the use of the Westinghouse WCAP-10325-P-A methodology for loss-of-coolant accident (LOCA) mass and energy release analysis. Westinghouse Electric Company LLC (Westinghouse) has issued Nuclear Safety Advisory Letters (NSALs)-06-6, 5, and 2, and lnfoGram (IG)-14-1 to report errors in this methodology. Also, a new methodology (GOTHIC) is used for the LOCA containment analysis for which the mass and energy input needs to be corrected based on the above NSALs and the lnfoGram.

The licensee indicated that the three Westinghouse NSALs were corrected and incorporated into the new LOCA containment analysis and the analysis results have been incorporated into the UFSAR.

1. Please describe any changes in inputs and assumptions in the reanalysis that could potentially reduce the conservatism in the previous analysis. Please describe which UFSAR sections and figures contain the revised results of the LOCA mass and energy releases, containment pressure response, and Equipment Qualification pressure/temperature response analyses. Provide a brief description of the changes from the previous analysis results.

Enclosure

2. The information provided in the IG-14-1 is generic. Please describe STP plant-specific analysis/evaluations performed to determine the applicability of the errors reported in the lnfoGram to STP and its impact on the current analysis of record.

ML16053A187 *via email OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DSS/SCVB/BC NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1/PM NAME LRegner (MWatford for) JBurkhardt* RDennig* RPascarelli LRegner DATE 2/25/16 2/25/16 2/25/16 03/01 /16 03/01/16