RA-18-0201, Corrected Technical Specification Page Regarding License Amendment Request to Self Perform Core Reload Design and Safety Analyses

Corrected Technical Specification Page Regarding License Amendment Request to Self Perform Core Reload Design and Safety Analyses

ML18288A276
Person / Time
Site:	Harris
Issue date:	10/15/2018
From:	Donahue J Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-18-0201
Download: ML18288A276 (5)

Text

JOSEPH DONAHUE Vice President Nuclear Engineering 526 South Church Street, EC-07H Charlotte, NC 28202 980-373-1758 Joseph.Donahue@duke-energy.com Serial: RA-18-0201 10 CFR 50.90 October 15, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63

SUBJECT:

CORRECTED TECHNICAL SPECIFICATION PAGE REGARDING LICENSE AMENDMENT REQUEST TO SELF PERFORM CORE RELOAD DESIGN AND SAFETY ANALYSES

REFERENCES:

1. Duke Energy letter, Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses, dated October 19, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17292A040)

2. Duke Energy letter, Response to Request for Additional Information (RAI) Regarding Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses, dated June 5, 2018 (ADAMS Accession No. ML18156A209)

Ladies and Gentlemen:

In Reference 1, as supplemented by Reference 2, Duke Energy Progress, LLC (Duke Energy) submitted a request for an amendment to the Technical Specifications (TS) for, in part, Shearon Harris Nuclear Power Plant, Unit 1 (HNP) to support the allowance of Duke Energy to self-perform core reload design and safety analyses. The proposed amendment would, in part, revise the HNP TS Chapter 1 definition of Shutdown Margin, consistent with Technical Specification Task Force (TSTF) TSTF-248, Revision 0, Revise Shutdown Margin Definition for Stuck Rod Exception. To support this amendment, a correction to the proposed changes to HNP TS Page 1-5 has been made and is provided in Attachment 1. This proposed TS page change supersedes the respective TS page in Attachment 4 of Reference 1. No new commitments have been made in this submittal. If you have additional questions, please contact Mr. Art Zaremba, Manager - Regulatory Affairs, at 980-373-2062.

U.S. Nuclear Regulatory Commission RA-18-0201 Page 2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on October 15, 2018.

Sincerely,

~u~

Joseph Donahue Vice President - Nuclear Engineering JD/jbd Attachments:

1. Revision of Proposed Technical Specification Page Changes cc:

C. Haney, Regional Administrator USNRC Region II J. Zeiler, USNRC Senior Resident Inspector - HNP M. C . Barillas, NRR Project Manager - HNP W . L. Cox, Ill, Section Chief, NC DHSR RA-18-0201 Attachment 1 Revision of Proposed Technical Specification Page Changes

DEFINITIONS PROCESS CONTROL PROGRAM 1.25 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 and State regulations , burial ground requirements , and other requirements governing the disposal of solid radioactive waste .

PURGE - PURGING 1.26

• PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

QUADRANT POWER TILT RATIO 1.27 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs , whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average.

RA TED THERMAL POWER 1.28 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2948 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.29 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC.

REPORTABLE EVENT 1.30 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

SHUTDOWN MARGIN 1.31 RGIN shall be the instantaneous amount of reactivit e reactor is subcritical or w *tical fro

• ondition assuming all rod cluster assemblies (shutd ro are xcept for the single rod clust o ighest reactivity worth which is assumed to be SITE BOUNDARY 1.32 For these Specifications, the SITE BOUNDARY shall be identical to the EXCLUSION AREA BOUNDARY defined above.

Replace with Insert #1 SHEARON HARRIS - UNIT 1 1-5 Amendment No. 439--

SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a. All rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

However, with all rod cluster assemblies verified as fully inserted by two independent means, it is not necessary to account for a stuck rod cluster assembly in the SHUTDOWN MARGIN calculation. With any rod cluster assembly not capable of being fully inserted, the reactivity worth of the rod cluster assembly must be accounted for in the determination of SHUTDOWN MARGIN, and

b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the nominal zero power design level.