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Nuclear Regulatory Commission Documents & Publications  

 

    Agency: "Nuclear Regulatory Commission."

    SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of amendments to Facility Operating License Nos. NPF-87 and NPF-89, issued to Vistra Operations Company LLC (the licensee), for operation of the Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2. The proposed amendments would revise Technical Specification (TS) 3.4.15, "RCS [Reactor Coolant System] Leakage Detection Instrumentation," to align with the Standard Technical Specifications (STS) for Westinghouse Plants and incorporate the changes made by Technical Specifications Task Force (TSTF) Traveler TSTF-513, Revision 3, "Revise PWR [Pressurized-Water Reactor] Operability Requirements and Actions for RCS Leakage Instrumentation."

    DATES: Submit comments by March 23, 2020. Comments received after this date will be considered if it is practical to do so, but the Commission is able to ensure consideration only for comments received before this date. Requests for a hearing or petition for leave to intervene must be filed by April 20, 2020.

    ADDRESSES: You may submit comments by any of the following methods:

    * Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2020-0038. Address questions about NRC docket IDs in Regulations.gov to Jennifer Borges; telephone: 301-287-9127; email: Jennifer.Borges@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document.

    * Mail comments to: Office of Administration, Mail Stop: TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, ATTN: Program Management, Announcements and Editing Staff.

    For additional direction on obtaining information and submitting comments, see "Obtaining Information and Submitting Comments" in the SUPPLEMENTARY INFORMATION section of this document.

    FOR FURTHER INFORMATION CONTACT: Dennis J. Galvin, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-6256, email: Dennis.Galvin@nrc.gov.

    SUPPLEMENTARY INFORMATION:

    I. Obtaining Information and Submitting Comments

    A. Obtaining Information Please refer to Docket ID NRC-2020-0038 when contacting the NRC about the availability of information for this action. You may obtain publicly-available information related to this action by any of the following methods:

    * Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2020-0038.

    * NRC's Agencywide Documents Access and Management System (ADAMS): You may obtain publicly-available documents online in the ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select "Begin Web-based ADAMS Search." For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document.

    * NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.

    B. Submitting Comments

    Please include Docket ID NRC-2020-0038 in your comment submission.

    The NRC cautions you not to include identifying or contact information that you do not want to be publicly disclosed in your comment submission. The NRC will post all comment submissions at https://www.regulations.gov as well as enter the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information.

    If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment into ADAMS.

    II. Introduction

    The NRC is considering issuance of amendments, as described in Vistra Operations Company LLC's (Vistra OpCo, the licensee) license amendment request dated November 7, 2019 (ADAMS Accession No. ML19325C593), to Facility Operating License Nos. NPF-87 and NPF-89, issued to Vistra OpCo, for operation of the Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2, located in Somervell County, Texas.

    The proposed amendments would revise TS 3.4.15, "RCS Leakage Detection Instrumentation" to align with the STS for Westinghouse Plants and incorporate the changes made by TSTF-513, Revision 3.

    Before any issuance of the proposed license amendments, the NRC will need to make the findings required by the Atomic Energy Act of 1954, as amended (the Act), and NRC's regulations.

    The NRC has made a proposed determination that the license amendment request involves no significant hazards consideration. Under the NRC's regulations in section 50.92 of title 10 of the Code of Federal Regulations (10 CFR), this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below with NRC edits in [brackets].

    1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

    Response: No.

    The proposed change [revises and] clarifies the Operability requirements for the Reactor Coolant System (RCS) leakage detection instrumentation and reduces the time allowed for the plant to operate when the only Operable RCS leakage instrumentation monitor is the containment atmosphere gaseous radiation monitor. The monitoring of RCS leakage is not a precursor to any accident previously evaluated. The monitoring of RCS leakage is not used to mitigate the consequences of any accident previously evaluated.

    Therefore, it is concluded that this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

    2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

    Response: No.

    The proposed change [revises and] clarifies the Operability requirements for the Reactor Coolant System (RCS) leakage detection instrumentation and reduces the time allowed for the plant to operate when the only Operable RCS leakage instrumentation monitor is the containment atmosphere gaseous radiation monitor. The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or a change in the methods governing normal plant operation.

    Therefore, it is concluded that this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

    3. Does the proposed change involve a significant reduction in a margin of safety?

    Response: No.

    The proposed change [revises and] clarifies the Operability requirements for the Reactor Coolant System (RCS) leakage detection instrumentation and reduces the time allowed for the plant to operate when the only Operable RCS leakage instrumentation monitor is the containment atmosphere gaseous radiation monitor. Reducing the amount of time, the plant is allowed to operate with only the containment atmosphere gaseous radiation monitor Operable increases the margin of safety by increasing the likelihood that an increase in RCS leakage will be detected before it potentially results in gross failure.

    Therefore, it is concluded that this change does not involve a significant reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis, with the addition of NRC staff edits, and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.

    The NRC is seeking public comments on this proposed determination that the license amendment request involves no significant hazards consideration. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination.

    Normally, the Commission will not issue the amendment until the expiration of 60 days after the date of publication of this notice. The Commission may issue the license amendments before expiration of the 60-day notice period if the Commission concludes the amendments involve no significant hazards consideration. In addition, the Commission may issue the amendments prior to the expiration of the 30-day comment period if circumstances change during the 30-day comment period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility. If the Commission takes action prior to the expiration of either the comment period or the notice period, it will publish in the Federal Register a notice of issuance. If the Commission makes a final no significant hazards consideration determination, any hearing will take place after issuance. The Commission expects that the need to take this action will occur very infrequently.

    III. Opportunity To Request a Hearing and Petition for Leave To Intervene

    --This is a summary of a Federal Register article originally published on the page number listed below--

    License amendment application; opportunity to comment, request a hearing, and petition for leave to intervene.

    Citation: "85 FR 9813"

    Document Number: "Docket Nos. 50-445 and 50-446; NRC-2020-0038"

    Federal Register Page Number: "9813"

    "Notices"

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