ML19290F980

Correction to Amendment No. 171 Revision of Technical Specifications to Support Self-Performance of Core Reload Design and Safety Analysis

ML19290F980
Person / Time
Site:	Harris
Issue date:	10/18/2019
From:	Tanya Hood Plant Licensing Branch II
To:	Hamilton T Duke Energy Progress
Hood, Tanya
References
EPID L-2017-LLA-0356
Download: ML19290F980 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 October 18, 2019 Ms. Tanya M. Hamilton Site Vice President Shearon Harris Nuclear Power Plant Mail Code NHP01 5413 Shearon Harris Road New Hill, NC 27562-9300

SUBJECT:

SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - CORRECTION TO AMENDMENT NO. 171 RE: REVISION OF TECHNICAL SPECIFICATIONS TO SUPPORT SELF-PERFORMANCE OF CORE RELOAD DESIGN AND SAFETY ANALYSIS (EPID L-2017-LLA-0356)

Dear Ms. Hamilton:

By letter dated April 29, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18288A139, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 171 to Renewed Facility Operating License No. NPF-63 for the Shearon Harris Nuclear Power Plant, Unit 1 (Shearon Harris), and Amendment No. 263 to Renewed Facility Operating License No. DPR-23 for H. B. Robinson Steam Electric Plant, Unit 2. The amendments were in response to your application dated October 19, 2017, as supplemented by letters dated June 5, October 15, and November 6, 2018. The amendments revised the Technical Specifications (TSs) to allow Duke Energy (the licensee) to self-perform core reload design and safety analysis.

Subsequent to issuance of the amendments, the NRC staff was notified by the licensee that a typographical error had been identified on Shearon Harris TS page 3/4 1-1. The words "immovable or before the words "untrippable control rod(s)" in paragraph a of Surveillance Requirement 4.1.1.1.1, was invadvertently left in due to version of that page used between the NRC staff's issuance of Amendment No. 168 dated November 19, 2018 (ADAMS Accession No. ML18262A303), and issuance of Amendment No. 171 on April 29, 2019.

The NRC staff has determined that this error was made inadvertently. The typographical error does not change any of the conclusions in the safety evaluation associated with the issuance of Amendment No. 171 and does not affect the associated notice to the public. Enclosed is replacement TS page 3/4 1-1 with a change bar added to reflect where the text "immovable or

was removed.

T. Hamilton If you have any questions, please contact me at 301-415-1387 or Tanya.Hood@nrc.gov.

/\ I Sincerely, /

J !fi1f (__ / t/;cc(

Tanya E. Hood Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400

Enclosure:

Corrected TS page 3/4 1-1 cc: Listserv

ENCLOSURE Corrected TS page 3/4 1-1

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - MODES 1 AND 2 LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to the limit specified in the COLR for 3-loop operation.

APPLICABILITY: MODES 1 and 2*.

ACTION:

With the SHUTDOWN MARGIN less than the limit specified in the COLR, immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal to the limit specified in the COLR:

a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod(s) is inoperable. If the inoperable control rod is untrippable, the above required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the untrippable control rod(s);

b. When in MODE 1 or MODE 2 with Kett greater than or equal to 1 at the frequency specified in the Surveillance Frequency Control Program by verifying that control bank withdrawal is within the limits of Specification 3.1.3.6;

c. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6; and

d. Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors below, with the control banks at the maximum insertion limit of Specification 3.1.3.6:

• See Special Test Exceptions Specification 3.10.1.

SHEARON HARRIS - UNIT 1 3/4 1-1 Amendment No. 171

ML19290F980 OFFICE NRR/D0RL/LPL2-2/PM N RR/D0RL/LPL2-2/LA NRR/D0RL/LPL2-2/BC N RR/D0RL/LPL2-2/PM NAME AHon LRonewicz UShoop (AHon for) THood DATE 10/18/2019 10/17/2019 10/18/2019 10/18/2019