RA-20-0179, Supplemental Information for License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core.

Supplemental Information for License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core.

ML20174A640
Person / Time
Site:	Harris
Issue date:	06/22/2020
From:	Maza K Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-20-0179
Download: ML20174A640 (5)

Text

Kim Maza Site Vice President Harris Nuclear Plant 5413 Shearon Harris Rd New Hill, NC 27562-9300 984-229-2512 10 CFR 50.90 June 22, 2020 Serial: RA-20-0179 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 / Renewed License No. NPF-63

Subject:

Supplemental Information for License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating Limits Ladies and Gentlemen:

By letter dated March 6, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20066L112), as supplemented by letter dated April 23, 2020 (ADAMS Accession No. ML20114E131), Duke Energy Progress, LLC (Duke Energy), submitted a license amendment request for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed license amendment would modify Technical Specification (TS) 3/4.2.5, DNB Parameters, and TS 6.9.1.6, Core Operating Limits Report, in support of analysis development for HNP Cycle 24. HNP TS 3/4.2.5 would be revised to reflect a lower minimum Reactor Coolant System flow rate, whereas TS 6.9.1.6.2 would reflect the incorporation of the Framatome, Inc. topical report EMF-2103(P)(A), Revision 3, Realistic Large Break LOCA

[Loss-of-Coolant Accident] Methodology for Pressurized Water Reactors, and the removal of analytical methods no longer applicable for the determination of HNP core operating limits.

The attachment to this supplemental correspondence provides an updated markup of a TS page provided in Enclosure 2 of the submittal dated March 6, 2020. Specifically, Index page iii is being resubmitted due to a discrepancy between the markup copy provided in the original submittal and the docketed authority file of the HNP TS (ADAMS Accession No. ML052860283).

The markup should have reflected the Index page associated with Amendment No. 116 (ADAMS Accession No. ML042300450), as this was the last time the NRC issued an amendment to this page.

The content of this supplemental correspondence does not change the No Significant Hazards Consideration provided in the original submittal and does not contain any regulatory commitments.

Please refer any questions regarding this submittal to Art Zaremba, Manager - Nuclear Fleet Licensing, at (980) 373-2062.

U.S. Nuclear Regulatory Commission Serial RA-20-0179 Page2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on June 22, 2020.

Sincerely, Kim E. Maza Site Vice President Harris Nuclear Plant

Attachment:

Updated Markup of Technical Specification Index Page cc: L. Dudes, NRC Regional Administrator, Region 11 J. Zeiler, NRC Sr. Resident Inspector, HNP M. Mahoney, NRC Project Manager, HNP W. L. Cox, 111, Section Chief, N.C. DHSR

U.S. Nuclear Regulatory Commission Serial RA-20-0179 Page 2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on June 22, 2020.

Sincerely, Kim E. Maza Site Vice President Harris Nuclear Plant

Attachment:

Updated Markup of Technical Specification Index Page cc: L. Dudes, NRC Regional Administrator, Region II J. Zeiler, NRC Sr. Resident Inspector, HNP M. Mahoney, NRC Project Manager, HNP W. L. Cox, III, Section Chief, N.C. DHSR

U.S. Nuclear Regulatory Commission Serial RA-20-0179 Attachment ATTACHMENT UPDATED MARKUP OF TECHNICAL SPECIFICATION INDEX PAGE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 RENEWED LICENSE NUMBER NPF-63 2 PAGES (INCLUDING COVER)

2.0 SAFETY. LIMITS AND LIMITING SAFETY SYSTEM SETTINGS

• u SECTION

• 2.1 SAFETY LIMITS 2.1.1 REACTOR CORE 2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE. 2-1 FIGURE 2.1-1 REACTOR CORE SAFETY LIMITS - THREE LOOPS IN OPERATION. 2-2 WITH MEASURED RCS FLOW> [ 293 ,540 GPM x (1.0 + C1 )]

y..___

I 290,000 GPM 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS . 2-1 TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 2-4 BASES SECTION 2.1 SAFETY LIMITS 2.1.1 REACTOR CORE B 2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE. B 2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATIQN SETPOINTS . . . . . . . . . . B 2-2 V

SHEARON HARRIS - UNIT 1 iii Amendment No. m