ML20175A575

Audit Plan Supplement in Support of Review of License Amendment Request to Revise TS to Adopt TS Task Force Traveler Tstf-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF (Risk-Informed TSTF) Initiative 4

ML20175A575
Person / Time
Site:	Harris
Issue date:	06/24/2020
From:	Tanya Hood Plant Licensing Branch II
To:	Maza K Duke Energy Progress
Hood, T
References
EPID L-2019-LLA-0218, TSTF-505, Rev 2
Download: ML20175A575 (3)

Text

June 24, 2020 Ms. Kim Maza 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 - AUDIT PLAN SUPPLEMENT IN SUPPORT OF REVIEW OF LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-505, REVISION 2, PROVIDE RISK-INFORMED EXTENDED COMPLETION TIMES - RITSTF INITIATIVE 4B (EPID L-2019-LLA-0218)

Dear Ms. Maza:

By letter dated October 7, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19280C844), Duke Energy Progress, LLC (the licensee) submitted a license amendment request (LAR) for the Shearon Harris Nuclear Power Plant, Unit 1. The proposed amendment would modify Technical Specifications (TSs) requirements to permit the use of risk-informed completion times in accordance with the Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF [risk-informed TSTF] Initiative 4b (ADAMS Accession Package No. ML18269A041).

The U.S. Nuclear Regulatory Commission (NRC) staff has started our review of the LAR to revise TS requirements to permit the use of risk-informed completion times for actions to be taken when limiting conditions for operation are not met. The NRC staff is conducting a regulatory audit to support its review of the LAR in accordance with the initial audit plan that was provided to Mr. Dennis Earp of your staff by email dated May 20, 2020 (ADAMS Accession No. ML20141L623). The audit plan is being supplemented to add a specific question to the scope of the audit. The audit is being conducted using video conferencing software from June 22, 2020 to June 25, 2020 from 8:30 a.m. to 4:00 p.m. The logistics and scope of the audit supplement were discussed with your staff on June 22, 2020. The specific question is as follows:

In Table E1-1 of Enclosure 1 of the LAR, the licensee stated that the design success criteria (DSC) for TS 3.8.1.1, Action D - Two required offsite AC sources inoperable, are 1 of 2 trains from either offsite circuit or EDG [emergency diesel generator]. Explain how an offsite circuit could provide the capacity and capability to safely shut down the reactor in case of a loss-of-coolant-accident or any other design bases accidents, with both required offsite sources inoperable, and maintain it in a safe condition. Also, confirm that if any clarifications are made to the DSC, these changes will also be represented in the probabilistic risk assessment success criteria in Table E1-1 of Enclosure 1 of the LAR.

K. Maza If you have any questions regarding this matter, please contact me at 301-415-1387 or by e-mail at Tanya.Hood@nrc.gov.

Sincerely,

/RA/

Tanya E. Hood, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400 cc: Listserv

ML20175A575 *via e-mail OFFICE DORL/LPL2-2/PM DORL/LPL2-2/LA DEX/EEOB/BC NAME THood BAbeywickrama* BTitus DATE 06/22/2020 06/23/2020 06/23/2020 OFFICE DORL/LPL2-2/BC DORL/LPL2-2/PM NAME UShoop (KGreen for) THood DATE 06/24/2020 06/24/2020