ML15201A602

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H. B. Robinson Electric Plant, Unit No. 2 - Staff Review of Interim Evaluation Associated with Reevaluated Seismic Hazard Implementation of Near-Term Task Force Recommendation 2.1
ML15201A602
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 10/06/2015
From: Vega F G
Japan Lessons-Learned Division
To: Glover R M
Duke Energy Corp
Wyman S M, NRR/JLD, 415-3041
References
TAC MF5265
Download: ML15201A602 (3)


Text

Mr. Richard Michael Glover Site Vice President H.B. Robinson Steam Electric Plant Duke Energy 3581 West Entrance Road, RNPA01 Hartsville, SC 29550 October 6, 2015

SUBJECT: H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 -STAFF REVIEW OF INTERIM EVALUATION ASSOCIATED WITH REEVALUATED SEISMIC HAZARD IMPLEMENTATION OF NEAR-TERM TASK FORCE RECOMMENDATION 2.1 (TAC NO. MF5265)

Dear Mr. Glover:

By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12053A340), the U.S. Nuclear Regulatory Commission (NRC) issued a request for information pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) (hereafter referred to as the 50.54(f) letter). The request was issued as part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 1 to the 50.54(f) letter requested that licensees reevaluate seismic hazards at their sites using present-day methodologies and guidance. Enclosure 1, Item 6, of the 50.54(f) letter requested that licensees identify "interim evaluation and actions taken or planned to address the higher seismic hazard relative to the design basis as appropriate, prior to completion of the [seismic] risk evaluation." In addition to the interim evaluation provided in the March 2014 Seismic Screening and Hazard report, the licensees for the Central and Eastern United States committed to providing the Expedited Seismic Evaluation Process (ESEP) report, an interim evaluation, by December 31, 2014. By letter dated December 17, 20141, Duke Energy Progress, Inc. (Duke, the licensee), provided its ESEP report in a response to Enclosure 1, Item (6) of the 50.54(f) letter, for the H. B. Robinson Steam Electric Plant, Unit No. 2 (Robinson). The NRC staff assessed the licensee's implementation of the ESEP guidance through the completion of a reviewer checklist2. Based on the NRC staff review of the ESEP report, the NRC staff concludes that the licensee's implementation of the interim evaluation meets the intent of the guidance. The staff concludes that, through the implementation of the ESEP guidance, the licensee identified and evaluated the seismic capacity of certain key installed mitigating strategies equipment that is used for core cooling and containment functions to cope with scenarios that 1 The December 17, 2014, letter can be found under ADAMS Accession No. ML 14365A105. 2 The Robinson ESEP NRC review checklist can be found under ADAMS Accession No. ML 15190A127. involve a loss of all alternating current power and loss of access to the ultimate heat sink to withstand a seismic event two times the safe shutdown earthquake for Robinson, Unit No. 2. The licensee's ESEP assessment provides additional assurance, which supports continued plant safety while the longer-term seismic evaluation is completed to support regulatory decision making. The NRC staff concludes that the licensee responded appropriately to Enclosure 1, Item (6) of the 50.54(f) letter. Application of this review is limited to the interim evaluation as part of the Recommendation 2.1 Seismic review. If you have any questions, please contact me at (301) 415-1617 or via e-mail at Frankie.Vega@nrc.gov. Docket No. 50-261 cc: Distribution via Listserv

Sincerely,Frankie G. Vega, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation involve a loss of all alternating current power and loss of access to the ultimate heat sink to withstand a seismic event two times the safe shutdown earthquake for Robinson, Unit No. 2. The licensee's ESEP assessment provides additional assurance, which supports continued plant safety while the longer-term seismic evaluation is completed to support regulatory decision making. The NRC staff concludes that the licensee responded appropriately to Enclosure 1, Item (6) of the 50.54(f) letter. Application of this review is limited to the interim evaluation as part of the Recommendation 2.1 Seismic review. If you have any questions, please contact me at (301) 415-1617 or via e-mail at Frankie.Vega@nrc.gov. Docket No. 50-261 cc: Distribution via Listserv DISTRIBUTION: PUBLIC JHMB R/F RidsOeMailCenter RidsNrrDorllpl2-2 RidsRgn2MailCenter DJackson, NRO NDiFrancesco, NRR

Sincerely,IRA/ Frankie G. Vega, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation RidsNrrPMRobinson RidsNrrLASLent RidsNrrOd MShams, NRR ADAMS Accession Number: ML 15201A602

  • via concurrence e-mail OFFICE NRR/JLD/JHMB/PM NRR/JLD/LA NRO/DSEA/RGS2 NAME SWyman Slent DJackson* DATE 7/21/2015 7/22/2015 7/8/2015 OFFICE NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME MShams FVega DATE 7/22/2015 10/6/2015 OFFICIAL RECORD COPY