ML20149K439

NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate RAI Sfnb RAI No. 2

ML20149K439
Person / Time
Site:	Farley
Issue date:	05/21/2020
From:	Shawn Williams NRC/NRR/DORL/LPL2-1
To:	Coleman J Southern Nuclear Operating Co
References
L-2019-LLS-0002
Download: ML20149K439 (4)

Text

From: Williams, Shawn Sent: Thursday, May 21, 2020 10:21 AM To: Coleman, Jamie Marquess Cc: Sparkman, Wesley A.

Subject:

Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate RE: RAI SFNB RAI No. 2 (EPID L-2019-LLS-0002)

Attachments: Farley MUR SFNB RAI No. 2.docx

Dear Ms. Coleman,

By letter dated October 30, 2019 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML19308A761), as supplemented on November 25, 2019 (ADAMS Accession No. ML19331A099), April 22, 2020 (ADAMS Accession No. ML20113E970), and May 8, 2020 (ADAMS Accession No. ML20129J876) the Southern Nuclear Operating Company, Inc., submitted a license amendment request for the Joseph M. Farley Nuclear Plant, Units 1 and 2. The proposed amendment would revise the Renewed Operating Licenses and Technical Specifications to allow for a measurement uncertainty recovery power uprate (MUR-PU) from 2775 megawatts thermal (MWt) to 2821 MWt.

The U.S. Nuclear Regulatory Commission staff has determined that additional information is needed as provided in the attached and discussed during a clarification call on May 21, 2020.

Please respond within 30 days of the date of this correspondence. If you have any questions, please contact me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov.

Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch, II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc w/encl: Listserv

Hearing Identifier: NRR_DRMA Email Number: 607 Mail Envelope Properties (SN6PR09MB32325A8655AC10A31FFC828590B70)

Subject:

Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate RE: RAI SFNB RAI No. 2 (EPID L-2019-LLS-0002)

Sent Date: 5/21/2020 10:21:22 AM Received Date: 5/21/2020 10:21:24 AM From: Williams, Shawn Created By: Shawn.Williams@nrc.gov Recipients:

"Sparkman, Wesley A." <WASPARKM@southernco.com>

Tracking Status: None "Coleman, Jamie Marquess" <JAMIEMCO@SOUTHERNCO.COM>

Tracking Status: None Post Office: SN6PR09MB3232.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1395 5/21/2020 10:21:24 AM Farley MUR SFNB RAI No. 2.docx 30642 Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING PROPOSED LICENSE AMENDMENT MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE FARLEY NUCLEAR PLANT UNITS 1 AND 2 SOUTHERN NUCLEAR OPERATING COMPANY DOCKET NOS. 50-348 AND 50-364 SFNB RAI No. 2 Generic Letter (GL) 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits, in part, describes the requirements related to the contents of the technical specifications (TSs) when referencing a pressure temperature limits report (PTLR), or similar document. GL 96-03 states:

Relocation of the curves and setpoints to a licensee-controlled document requires three separate licensee actions. The licensee must (1) have a methodology approved by the NRC to reference in its TS; (2) develop a report such as a PTLR or a similar document to contain the figures, values, parameters, and any explanation necessary; and (3) modify the applicable sections of the TS accordingly.

The guidance provided in GL 96-03 identifies six provisions that licensees must address to relocate pressure-temperature limits to an administratively controlled document. The first of these is that the methodology shall describe how the neutron fluence is calculated. While WCAP-14040-A, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves, (Agency-wide Documents Access and Management System (ADAMS) Accession No. ML050120209) addresses this requirement by describing neutron transport calculations in Chapter 2, alternative methods are described in WCAP-18124-NP-A, Fluence Determination with RAPTOR-M3G and FERRET (ADAMS Accession No. ML18204A010). While the use of WCAP-18124-NP-A is generally acceptable as described in the associated NRC staff safety evaluation, its use may preclude adherence to Chapter 2 of WCAP-14040-A.

TS 5.6.6.b is stated below, with the proposed changes in bold.

The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in WCAP-14040-A, Revision 4, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves, May 2004 and WCAP-18124-NP-A, Revision 0, Fluence Determination with RAPTOR-M3G and FERRET, July 2018.

For Farley Nuclear Plant, Units 1 and 2, the NRC staff understands that the approved methodology used to determine pressure-temperature limits would continue to be WCAP-14040-A. However, in cases where WCAP-18124-NP-A is used, the transport methods described in Chapter 2 of WCAP-14010-A may not be used.

Please modify the proposed TS revision to clarify that WCAP-18124-NP-A may be used as an alternative to Chapter 2 of WCAP-14040-A. As presently proposed, the revision suggests that both methodologies would be used.