ML17292A081

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Supplemental Information Needed for Acceptance of Requested Licensing Action Application to Adopt 10CFR 50.69, Risk-Informed Categorization and Treatment of Sscs for Nuclear Power Plants
ML17292A081
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 10/23/2017
From: Mahesh Chawla
Plant Licensing Branch III
To: Coffey R
Point Beach
References
CAC MG0196, CAC MG0197, L-2017-LLA-0284
Download: ML17292A081 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION Mr. Robert Coffey Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241 WASHINGTON, D.C. 20555-0001 October 23, 2017

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNITS 1AND2-SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: APPLICATION TO ADOPT 10 CFR 50.69, "RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEM, AND COMPONENTS (SSCS) FOR NUCLEAR POWER PLANTS (CAC NOS.

MG0196 AND MG0197) (L-2017-LLA-0284)

Dear Mr. Coffey:

By letter dated August 31, 2017, NextEra Energy Point Beach, LLC, (NextEra, the licensee) submitted a license amendment request (LAA) for Point Beach Nuclear Plant (PBNP), Units 1 and 2. The proposed LAA would modify the licensing basis, by addition of a License Condition, to allow for the implementation of the provisions of Title 1 O of the Code of Federal Regulations (10 CFR), Part 50.69, "Risk-Informed Categorization and Treatment of Structures, System, and Components (SSCs) for Nuclear Power Plants."

The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC or Commission) staff's acceptance review of this LAA. 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 1 O CFR, whenever a holder of a license, including a construction permit and operating license under this part, and an early site permit, combined license, and manufacturing license under part 52 of this chapter, desires to amend the license or permit, application for an amendment must be filed with the Commission, as specified in Sections 50.4 or 52.3 of this chapter, as applicable, fully describing the changes desired, 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/relief request in terms of regulatory requirements and the protection of public health and safety and the environment.

In order to make the application complete, the NRC staff requests the licensee supplement the application to address the information requested in the enclosure by October 26, 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 time frame in this letter were discussed with your representative, Mr. Scott Manthei, Senior Licensing Engineer, during a teleconference held on October 6, 2017.

If you have any questions, please contact me, at (301) 415-8371 or Mahesh.chawla@nrc.gov.

Docket Nos. 50-266 and 50-301 cc: Distribution via Listserv

Enclosure:

As stated Sincerely,

~~IYl/___

Mahesh Chawla, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST APPLICATION TO ADOPT 10 CFR 50.69, RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEM, AND COMPONENTS (SSCS)

FOR NUCLEAR POWER PLANTS - POINT BEACH NUCLEAR PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-266 AND 50-301 Additional requested information:

a. Clarify whether a high winds hazard screening evaluation or the high winds probabilistic risk assessment (PRA) will be used during the safety significance categorization process consistent with Section 5.4 of Nuclear Energy Institute 00-04, as endorsed by Regulatory Guide (RG) 1.201, Revision 1.
b. If the high winds PRA will be used during the safety significance categorization process, describe the peer review process applied to the high winds PRA, indicate whether it was a full-scope peer review and identify the guidance used to perform this peer review (e.g.,

American Society of Mechanical Engineers/American Nuclear Society (ASME/ANS) RA-Sa 2009, RG 1.200, Revision 2). Include any necessary gap-or self-assessments if current guidance/standards were not used in the peer review. In addition, provide all facts and observations (F&Os) characterized as findings from the peer review of the high winds PRA. For each F&O, include details of its disposition or why not meeting the corresponding Capability Category II requirements has no impact on the application.

c.

If a high winds hazard screening evaluation will be used during the safety significance categorization process, describe this screening evaluation. Also, discuss how this evaluation is consistent with the screening criteria in Section 6-2 of ASME/ANS RA-Sa 2009, as qualified by RG 1.200, Revision 2, and reflects the current as-built, as-operated plant.

Enclosure

ML17292A081 OFFICE NRR/DORL/LPL3/PM NAME MChawla DATE 10/19/17 OFFICE NRR/DORL/LPL3/BC NAME DWrona DATE 10/23/17 NRR/DORL/LPL3/LA NSIR/DRA/APLA/BC SRohrer SRosenburg 10/19/17 10/20/17 NRR/DORL/LPL3/PM MChawla 10/23/17