ML16351A150

Correction Letter Closeout of Request for Information Questions That Are No Longer Applicable Associated with the Resolution of Generic Safety Issue 191 (CAC Nos. MF2400 - MF2409)

ML16351A150
Person / Time
Site:	South Texas
Issue date:	12/16/2016
From:	Lisa Regner Plant Licensing Branch IV
To:	Gerry Powell South Texas
Regner L, NRC/NRR/DORL/LPLIV, 415-1906
References
CAC MF2400, CAC MF2401, CAC MF2402, CAC MF2403, CAC MF2404, CAC MF2405, CAC MF2406, CAC MF2407, CAC MF2408, CAC MF2409
Download: ML16351A150 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 16, 2016 Mr. G. T. Powell Executive Vice President and CNO STP Nuclear Operating Company South Texas Project P.O. Box 289 VVadsworth, TX 77483

SUBJECT:

SOUTH TEXAS PROJECT, UNITS 1 AND 2 - CORRECTION LETTER RE:

CLOSEOUT OF REQUEST FOR INFORMATION QUESTIONS THAT ARE NO LONGER APPLICABLE ASSOCIATED VVITH THE RESOLUTION OF GENERIC SAFETY ISSUE 191 (CAC NOS. MF2400, MF2401, MF2402, MF2403, MF2404, MF2405, MF2406, MF2407, MF2408, AND MF2409)

Dear Mr. Powell:

On December 12, 2016, the U.S. Nuclear Regulatory Commission (NRC) issued a letter concerning the South Texas Project, Units 1 and 2, "Closeout of Request for Information Questions that are no Longer Applicable Associated with the Resolution of Generic Safety Issue 191" (Agencywide Documents Access and Management System Accession No. ML16302A453). Due to an administrative error, the wrong version of the Enclosure to the letter was issued.

The correct version of the Enclosure to the letter dated December 12, 2016, is enclosed. VVe apologize for any inconvenience this may have caused. / .

Sincerelf, I

/ J bt~*~

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

Enclosure:

As stated cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION QUESTIONS THAT ARE NO LONGER APPLICABLE TO THE RESOLUTION OF GENERIC SAFETY ISSUE 191 FOR STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT, UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499 The U.S. Nuclear Regulatory Commission (NRC) staff determined that the following questions and licensee responses to the following questions in a request for additional information (RAI) letter dated April 15, 2014 (ADAMS Accession No. ML14087A075), are no longer applicable due to STP Nuclear Operating Company's methodology change from risk-based only to a risk and deterministic methodology:

• CASA Grande, General - 1.a, 1.b, and 1.c.

• CASA Grande, Plant Configuration - 1.a, 1.b, 2.a, 2.b, 3.a, 3.b, and 3.c.

• CASA Grande, LOCA [Loss-Of-Coolant Accident] Frequencies - 1.a, 3, and 4.

• CASA Grande to PRA [Probabilistic Risk Assessment] Interface, General - 1.a, 1.b, 2.a, 2.b, 3, 4.a, 4.b, 4.c, 5, 6.a, 6.b, and 6.c.

• STP PRA Model, Success Criteria - 1, 2.a, 2.b, 3.a, 3.b, and 3.d.

• STP PRA Model, Human Reliability Analysis - 1, 2, 3.a, 3.b, 3.c, 4.a, 4.b, 5, and 6.

• Results Interpretation, Quantification - 1.a, 1.b, and 2.

• Results Interpretation, Uncertainty Analysis - 1.a, 1.b, 1.c, 4.a, 4.b, 4.c, 4.d, 5, and 6.

• Radiation Protection and Consequence Branch - 1 and 3.

• Mechanical and Civil Engineering Branch - 1.

• Component Performance, NOE [Non-destructive Examination] and Testing Branch (EPNB) - 1, 2, 3, 4, 5, 6.a, and 6.b.

• Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB), Chemical Effects - 1.a, 1.b, 1.c, 1.d, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11.a, 11.b, 12, 13.a, 13.b, 13.c, 14.a, 14.b, 14.c, 15, 16, 17, 18.a, 18.b, 18.c, 19, 20, 21, 22.a, and 22.b.

• ESGB, Coatings - 2, 4, 5, 6.a, 6.b, and 6.c.

• Containment and Ventilation Branch (SCVB) - 1.b, 2.b, 3.b, 5, 8, and 9.b.

Enclosure

• Reactor Systems Branch (SRXB) - 2.a, 2.b, 2.c, 2.d, 2.e, 5.a, 5.b, 5.c, 6, and 8.

• Safety Issue Resolution Branch (SSIB) - 3, 5, 9, 11.a, 11.b, 11.d, 11.e, 14, 15.a, 15.b, 15.c, 15.d, 16.a, 16.b, 16.c, 16.d, 17.a, 17.b, 17.c, 17.d, 17.e, 17.f, 18, 19, 20, 21, 22, 23, 24, 25, 26.a, 26.b, 26.d, 26.e, 26.f, 28, 30, 33, 34, 35, 36, 37, 38, 40, and 41.a.

• Technical Specifications Branch (STSB) - 1 and 2.

The NRC staff determined that question SNPB-4 in the April 15, 2015, RAI is no longer applicable; however, because the plant's licensing basis analysis for boric acid precipitation (BAP) was changed, the SNPB-4 question and its response are superseded by question SNPB-3-33 in an NRC RAI dated April 11, 2016 (ADAMS Accession No. ML16082A507), which discussed the new STP BAP analysis.

The NRC staff determined that the response to question CASA Grande, LOCA Frequencies - 1.b is still applicable, and the NRC staff intends to use the information provided in the STPNOC response in letter dated May 22, 2014 (ADAMS Accession No. ML14149A434). A letter dated December 7, 2016, was submitted by the licensee to correct the June 9, 2016, letter.

The NRC staff determined that the following questions and licensee responses to the following questions in RAI dated March 3, 2015 (ADAMS Accession No. ML14357A171), are no longer applicable due to STP Nuclear Operating Company's methodology change from risk-based only to a risk and deterministic methodology:

• PRA Licensing Branch (APLA), Project Quality Assurance - 2.

• ESGB, Chemical Effects - 33 and 34.

• SSIB -45, 53, and 58.

The NRC staff determined that questions SCVB - 10 through 18 in the RAI dated March 3, 2015, are still applicable; however, the responses to these questions dated March 25, 2015 (ADAMS Accession No. ML15091A440) have been revised by the STPNOC responses provided in an August 20, 2015, supplement (ADAMS Accession No. ML15246A128).

ML16351A150 OFFICE NRR/DORULPL4/PM NRR/DORULPL4/LA NRR/DORULPL4/BC NRR/DORULPL4/PM NAME LRegner PBlechman RPascarelli LRegner DATE 12/16/16 12/16/16 12/16/16 12/16/16