ML19148A532

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Acceptance Letter for LAR 19-008
ML19148A532
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 05/30/2019
From: Peter Hearn
NRC/NRO/DLSE/LB2
To: Whitley B
Southern Nuclear Operating Co
HEARN P/415-1189
References
EPID L-2019-LLA-0107
Download: ML19148A532 (2)


Text

May 30, 2019 Mr. Brian H. Whitley, Director Regulatory Affairs Southern Nuclear Operating Company, Inc.

3535 Colonnade Parkway, Bin N-226-EC Birmingham, AL 35243

SUBJECT:

ACCEPTANCE REVIEW OF SOUTHERN NUCLEAR OPERATING COMPANYS REQUEST FOR A LICENSE AMENDMENT RE: REACTOR COOLANT PUMP SPEED SENSOR CHANNEL CALIBRATION AND RESPONSE TIME TEST SURVEILLANCE REQUIREMENT CHANGES (LAR 19-008) (L2019-LLA-0107)

Dear Mr. Whitley:

By letter dated May 17, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19137A314), Southern Nuclear Operating Company (SNC) submitted a request for a license amendment to Combined License (COL) Numbers NPF-91 and NPF-92, for the Vogtle Electric Generating Plant Units 3 and 4, respectively. The requested amendment proposes a change to the Updated Final Safety Evaluation Report (UFSAR) and the COL Appendix A Technical Specifications definition for Channel Calibration to allow a qualitative check (i.e., sensor resistance and insulation resistance tests) as an acceptable means to perform channel calibration for the reactor coolant pump (RCP) speed sensors. An additional change is proposed to the UFSAR to allow the use of a conservatively allocated response time in lieu of measurement for the RCP speed sensors and preamplifiers.

The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of these requests. 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 reviews. 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 10 of the Code of Federal Regulations (10 CFR), an amendment to the license must fully describe the changes requested, and follow as far as applicable, the form prescribed for original applications. Section 52.79 of the 10 CFR addresses 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 it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and 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. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence.

B. Whitley SNC has requested NRC staff approval of this license amendment request by November 15, 2019. As we discussed the staff intends to complete this action by the date agreed to with licensee after acceptance review, unless we agree to a different date at a later time due to circumstances beyond our control. The staff estimates that it may take 400 hours16.667 days <br />2.381 weeks <br />0.548 months <br /> to complete this licensing action.

If you have any questions, please contact me at (301) 415-1189 or Peter.Hearn@NRC.gov.

Sincerely,

/RA/

Peter C. Hearn, Senior Project Manager Licensing Branch 2 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors Docket No(s): 52-025 52-026