ML14195A071

Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report

ML14195A071
Person / Time
Site:	Brunswick
Issue date:	07/16/2014
From:	Michael Balazik Japan Lessons-Learned Division
To:	Hamrick G Progress Energy Carolinas
Balazik M, NRR/JLD, 415-2856
References
Download: ML14195A071 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 16, 2014 George T. Hamrick, Vice President Brunswick Steam Electric Plant P.O. Box 10429 Southport, NC 28461

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2- REQUEST FOR ADDITIONAL INFORMATION ASSOCIATED WITH NEAR-TERM TASK FORCE RECOMMENDATION 2.1, SEISMIC HAZARD AND SCREENING REPORT

Dear Mr. Hamrick:

By letter dated March 31, 2014, to the Nuclear Regulatory Commission (NRC) (Agencywide Documents and Management System (ADAMS) Accession No. ML14106A461), Duke Energy Progress, Inc., submitted for NRC review the Seismic Hazard and Screening Report, Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident for Brunswick Steam Electric Plant (BSEP), Units 1 and 2.

The NRC staff has reviewed the information provided forBSEP, Units 1 and 2, and has determined that additional information is required to complete the review. Enclosed is a request for additional information (RAI) related to the plant's Individual Plant Examination for External Events. As discussed with your staff during a recent phone call, the NRC staff requests that you respond no later than August 15,2014.

If you have any questions related to the enclosed RAisor the requested submission date, please contact me at 301-415-2856 or via e-mail at michael.ba!azik@nrc.gov.

Sincerely, Docket Nos. 50-325 and 50-324

Enclosure:

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

REQUEST FOR ADDITIONAL INFORMATION NEAR-TERM TASK FORCE RECOMMENDATION 2.1 I SEISMIC HAZARD AND SCREENING REPORT DUKE ENERGY PROGRESS. INC.

BRUNSWICK STEAM ELECTRIC PLANT. UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued a request for information pursuant to Title 10 of the Code of Federal Regulations, Part 50 (10 CFR),

Section 50.54(f) (hereafter referred to as the 50.54 (f) letter) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340). The purpose of the request was to gather information concerning, in part, the seismic hazards at operating reactor sites and to enable the NRC staff to determine whether licenses should be modified, suspended, or revoked. To respond to the 50.54(f) letter, Duke Energy Progress (Duke, the licensee) committed to follow the Electric Power Research Institute (EPRI) Report, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation2.1: Seismic," (ADAMS Accession No. ML12333A170) as supplemented by the EPRI Report, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force (NTTF) Recommendation 2.1: Seismic" (referred to as the Expedited Approach) (ADAMS Accession No. ML13102A142). Duke submitted the re-evaluated seismic hazards (ADAMS Accession No. ML14106A461) for Brunswick Steam Electric Plant (BSEP), Units 1 and 2 in March 2014. The NRC staff conducted the screening and prioritization review of the submittal by assessing the screening evaluation and hazard analysis utilizing the endorsed SPID guidance. Accordingly, during the NRC screening and prioritization process, the staff identified that a determination could not be made and interactions with Duke were needed to reach resolution. The staff identified BSEP, Units 1 and 2, as a "conditional screen-in" for the purposes of prioritizing and conducting additional evaluations. On May 9, 2014, the NRC staff issued a letter (ADAMS Accession No. ML14111A147) documenting the NRC staff's screening results.

In accordance with the SPID and Expedited Approach guidance, the re-evaluated seismic hazard determines if additional seismic risk evaluations are warranted for a plant. The SPID guidance provides criteria for a plant with ground motion response spectra (GMRS) above the safe shutdown earthquake, but bounded by the Individual Plant Examination for External Events (IPEEE) capacity spectrum. To use the IPEEE capacity spectrum to screen out of conducting a seismic risk evaluation, the licensee needed to demonstrate the adequacy of BSEP's IPEEE evaluation by meeting the criteria in the SPID. If the IPEEE capacity is greater than the GMRS in the 1-1OHz range, the plant screens out of conducting a seismic risk.

The following additional information is requested to support the NRC's final screening determination for BSEP based on IPEEE adequacy:

Enclosure

1. In Appendix B, Section 2.1.2 of the submittal, it states that soils evaluation considered relevant structures on the Safe Shutdown Equipment List which includes the intake canal. The submittal also states that slope stability screens out at BSEP. Describe the basis for screening out slope stability along the intake canal under the review level earthquake loading.

2. In Appendix B, Section 2.1.2 of the submittal, it states that considerations similar to Table 7-1A of Reference 6.4 was used for screening out liquefaction for the intake canal.

If appears that the reference should have been Reference 6.6. Clarify whether the submittal should cite Reference 6.6 instead of Reference 6.4 when referring to Table 7-1A or provide a description of the considerations used for screening.

ML14195A071 *concurrence via e-mail OFFICE NRR/JLD/JHMB/PM NRR/DORULPL2-2/PM* NRR/JLD/JHMB/LA NRR/JLD/JHMB/BC NAME

• MBalazik AHon Slent SWhaley DATE 07/14/14 07/15114 07114/14 07/16/14