ML17058A434

Acceptance of Requested Licensing Action Reduce Steam Dome Pressure in Reactor Core Safety Limits

ML17058A434
Person / Time
Site:	Nine Mile Point
Issue date:	03/02/2017
From:	Marshall M Plant Licensing Branch 1
To:	Bryan Hanson Exelon Nuclear
Marshall M, NRR/DORL/LPL1
References
CAC MF8942
Download: ML17058A434 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 2, 2017 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNIT 2 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REDUCE STEAM DOME PRESSURE IN REACTOR CORE SAFETY LIMITS (CAC NO. MF8942)

Dear Mr. Hanson:

By letter dated December 13, 2016, as supplemented by letter dated February 17, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML16348A368 and ML17048A034, respectively), Exelon Generation Company, LLC submitted a license amendment request for the Nine Mile Point Nuclear Station, Unit 2 (NMP2).

The proposed amendment would revise the NMP2 technical specification (TS) safety limit (SL) to increase the low pressure isolation setpoint allowable value, which will result in earlier main steam line isolation. The revised main steam line low pressure isolation capability and the revised SL are intended to ensure that NMP2 remains within the TS SLs in the event of a pressure regulator failure maximum demand transient.

The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRG) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRG 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 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, 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 NRG staff has reviewed your letter dated December 13, 2016, as supplemented by letter dated February 17, 2017 and concluded that it does provide technical information in sufficient detail to enable the NRG 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 NRG staff's ability to complete the detailed technical review are identified, despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence.

B. Hanson Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 280 hours11.667 days <br />1.667 weeks <br />0.384 months <br /> to complete. The NRC staff expects to complete this review by February 28, 2018 (approximately 12 months). If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes in the forecasted hours, the reasons for the changes, along with the new estimates, will be communicated during the routine interactions with the assigned project manager.

These estimates are based on the NRC staff's initial review of the application, and they could change due to several factors, including requests for additional information, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. Additional delay may occur if the submittal is provided to the NRC in advance, or in parallel with, industry program initiatives or pilot applications.

If you have any questions, please contact me at (301) 415-2871 or Michael.Marshall@nrc.gov.

Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 cc: Distribution via Listserv

B. Hanson

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNIT 2 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REDUCE STEAM DOME PRESSURE IN REACTOR CORE SAFETY LIMITS (CAC NO. MF8942) DATED MARCH 2, 2017 DISTRIBUTION:

PUBLIC LPL 1 R/F RidsACRS_MailCTR Resource RidsNrrDorl Resource RidsNrrDorlLpl 1 Resource RidsNrrLALRonewicz Resource RidsNrrPMNineMilePoint Resource RidsRgn 1MailCenter Resource RidsNrrDssSrsb Resource RidsNrrDssSrxb Resource RidsNrrDeEicb Resource CTilton, NRR MRazzaque, NRR MU, NRR GSingh, NRR ADAMS Accession Number: ML17058A434 OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/LA NRR/DORL/LPL 1/BC NAME MMarshall LRonewicz SKoenick DATE 03/02/2017 03/02/2017 03/02/2017 OFFICE NRR/DORL/LPL 1/PM NAME MMarshall DATE 03/02/2017 OFFICIAL RECORD COPY