RA-19-0417, Supplement to License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications

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Supplement to License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications
ML19312C572
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 11/08/2019
From: Hamilton T
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-19-0417
Download: ML19312C572 (7)


Text

Tanya M. Hamilton Vice President Harris Nuclear Plant 5413 Shearon Harris Road New Hill, NC 27562-9300 919-362-2502 10 CFR 50.90 November 8, 2019 Serial: RA-19-0417 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:

Supplement to License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications Ladies and Gentlemen:

By letter dated July 25, 2019 (ADAMS Accession No. ML19206A599), Duke Energy Progress, LLC (Duke Energy), submitted a license amendment request (LAR) proposing changes to the Technical Specifications (TS) for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed amendment would revise TS 3/4.10.3, Special Test Exceptions, Physics Tests, and TS 3/4.10.4, Special Test Exceptions, Reactor Coolant Loops, to eliminate the within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> restriction from Surveillance Requirement (SR) 4.10.3.2 for performing an Analog Channel Operational Test (ACOT) on the intermediate and power range neutron monitors prior to initiating physics tests and to eliminate the within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> restriction from SR 4.10.4.2 for performing an ACOT on the intermediate range monitors, power range monitors, and P-7 interlock prior to initiating startup or physics tests, respectively. The proposed amendment would also delete certain reporting requirements from TS, provide clarification to required actions of TS 3/4.4.4, Relief Valves, eliminate a second Completion Time associated with TS 3/4.8.1.1, A.C. Sources - Operating, and reflect the title changes of the Plant Nuclear Safety Committee (PNSC) to the On-Site Review Committee (ORC) and the Plant General Manager to the plant manager. of this supplemental correspondence provides updated markups of impacted pages to address editorial items identified in the TS markups provided in Enclosure 2 of the original submittal. Specifically, it addresses the relocation of the word and from the end of Action a.2 to Action a.1 of TS 3.1.1.3, Moderator Temperature Coefficient, and defines ORC in TS 6.6.1.b, TS 6.13.b, and TS 6.14.b. 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.

In accordance with 10 CFR 50.91, HNP is providing the state of North Carolina with a copy of this supplemental correspondence.

U.S. Nuclear Regulatory Commission Serial: RA-19-0417 Page 2 Please refer any questions regarding this submittal to Art Zaremba, Manager - Nuclear Fleet Licensing, at (980) 373-2062.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on November~. 2019.

Sincerely, Tanya M. Hamilton

Attachment:

1. Updated Proposed Technical Specification Changes cc: J. Zeiler, NRC Sr. Resident Inspector, HNP W. L. Cox, Ill, Section Chief, N.C. DHSR T. Hood, NRC Project Manager, HNP NRC Regional Administrator, Region II

U.S. Nuclear Regulatory Commission Serial: RA-19-0417 ATTACHMENT 1 UPDATED PROPOSED TECHNICAL SPECIFICATION CHANGES SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 RENEWED LICENSE NUMBER NPF-63 5 PAGES (INCLUDING COVER)

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ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION On-Site Review 6.6.1 The following actions shall be taken for REPORTABLE EVENTS: Committee (ORC)

a. The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and
b. Each REPORTABLE EVENT shall be reviewed by the PNSC, and the results of this review shall be submitted to the Manager - Nuclear Assessment Section and the Vice President - Harris Nuclear Plant.

6.7 SAFETY LIMIT VIOLATION 6.7.1 Deleted.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978;
b. The emergency operating procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Generic Letter No.

82-33;

c. Security Plan implementation;
d. Emergency Plan implementation;
e. PROCESS CONTROL PROGRAM implementation;
f. OFFSITE DOSE CALCULATION MANUAL implementation; SHEARON HARRIS - UNIT 1 6-16 Amendment No. 161

On-Site Review Committee (ORC) plant manager

On-Site Review Committee (ORC) plant manager