ML17241A018

From kanterella
Revision as of 01:28, 2 May 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search

Shearon Harris Nuclear Power Plant, Unit 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Spent Fuel Storage Pool Criticality Analyses (TAC No. MF9996)
ML17241A018
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 08/30/2017
From: Barillas M C
Plant Licensing Branch II
To: Hamilton T M
Duke Energy Progress
Barillas M C DORL/LPL2-2 301-415-2760
References
TAC MF9996
Download: ML17241A018 (4)


Text

Ms. Tanya M. Hamilton Site Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 30, 2017 Shearon Harris Nuclear Power Plant Duke Energy 5413 Shearon Harris Road MIC HNP01 New Hill, NC 27562-0165

SUBJECT:

SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 -SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION REGARDING SPENT FUEL STORAGE POOL CRITICALITY ANALYSES (TAC NO. MF9996)

Dear Ms. Hamilton:

By letter dated June 28, 2017 (Agencywide Documents Access and Management System Accession No. ML 17193B165), Duke Energy Progress, LLC (Duke Energy) requested an amendment to the Technical Specifications (TSs) of Renewed Facility Operating License No. NPF-63 for Shearon Harris Nuclear Power Plant, Unit 1. The proposed license amendment would revise the TS for fuel storage criticality to account for the use of Metamic neutron absorbing spent fuel pool rack inserts and soluble boron for the purpose of criticality control in the Boiling Water Reactor (BWR) storage racks that currently credit Boraflex. The TS 5.6.1.3, BWR Storage Racks in Pools "A" and "B", would be modified to reflect the respective design features of the two BWR rack types utilized in these pools, including adjusted requirements for the racks that credit the use of neutron absorbing Metamic inserts and soluble boron for criticality control in place of the existing credited Boraflex. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this license 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 1 O of the Code of Federal Regulations (1 O CFR), an amendment to the license (including the TSs) must fully describe the changes re<?tuested, 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 the information delineated in the enclosure to this letter is necessary to enable the staff to 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.

T. Hamilton -2 -In order to make the application complete, the NRC staff requests that Duke Energy supplement the application to address the information requested in the enclosure by Septemqer 14, 2017. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. The information requested and the associated timeframe in this letter were discussed in a conference call with Mr. Jeffrey Roberston on August 28, 2017. If you have any questions, please contact me at (301) 415-2760 or Martha.Barillas@nrc.gov. Docket No. 50-400

Enclosure:

Supplemental Information Needed cc w/enclosure: Distribution via Listserv Martha Barillas, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation SUPPLEMENTAL INFORMATION NEEDED REGARDING SPENT FUEL STORAGE POOL CRITICALITY ANALYSES Background LICENSE AMENDMENT REQUEST DUKE ENERGY PROGRESS, LLC SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 By application dated June 28, 2017 (Agencywide Documents Access and Management System Accession Numbers ML 17193B165), Duke Energy Progress, LLC, the licensee, proposed changes to Shearon Harris Nuclear Power Plant, Unit 1 Spent Fuel Storage Pool Criticality Analyses Technical Specifications (TSs). During the Nuclear Regulatory Commission (NRC) staff's acceptance review of the requested license amendment, the NRC staff found the application contained the following insufficiency and more information is needed to accept the application for review. Regulatory Analysis Basis Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.90, "Application for amendment of license, construction permit, or early site permit." states that license amendment requests fully describe the changes desired. The license amendment request (LAR) requests changes to the Technical Specifications. Section 50.36 of 10 CFR is the governing regulation for TSs and contains the regulatory requirements for TS categories including Safety Limits, Limiting Conditions for Operation, Surveillance Requirements, Design Features and Administrative Controls. Technical Basis for the Request Section 4.0 of the LAR contains discussions regarding whether or not the regulatory requirements of 10 CFR 50.68, 10 CFR Part 50 Appendix A, General Design Criterion (GDC) 61 and GDC 62 would continue to be met. However, Section 4.0 contains no discussion of whether or not the regulatory requirements of 10 CFR 50.36 will continue to be met, given the proposed changes to TS. Insufficiency Please supplement the LAR by providing a full description of the applicable regulatory requirements for the proposed changes, including 10 CFR 50.36, and describe how these requirements will continue to be met. Enclosure T. Hamilton -3 -

SUBJECT:

SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 -SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION REGARDING SPENT FUEL STORAGE POOL CRITICALITY ANALYSES (TAC NO. MF9996) DATED: AUGUSY 31, 2017 DISTRIBUTION: PUBLIC RidsNrrLABClayton RidsNrrDorllpl2-2 RidsNrrDssStsb RidsNrrPMShearonHarris RidsRgn2MailCenter LPL2-2 R/F RidsNRRLIC109 ADAMS Accession No* ML 17241A018 .. OFFICE NRR/DORULPL2-2/PM NRR/DORULPL2-2/LA NAME MBarillas BClavton DATE 08/30/17 08/29/17 OFFICE NRR/DORULPL2-2/BC NRR/DORULPL2-2/PM NAME US hoop MBarillas DATE 08/30/17 08/30/17 OFFICIAL RECORD COPY MHamm, NRR RidsNrrDorl RidsACRS_MaUCTR *via e-mail NRR/DSS/STSB JWhitman 08/30/17 . '