ML22083A028

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Email Snsb Safety Evaluation for Harris LAR to Revise Reactor Protection System TS
ML22083A028
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 03/23/2022
From: Scott Krepel
NRC/NRR/DSS/SNSB
To: David Wrona
NRC/NRR/DORL/LPL2-2
Fred M Forsaty, NRR/DSS/SNSB 415-8523
Shared Package
ML22082A191 List:
References
EPID L-2021-LLA-0149
Download: ML22083A028 (1)


Text

From: Krepel, Scott To: Wrona, David Cc: Hon, Andy; Forsaty, Fred; DSS_AA Distribution

Subject:

SNSB Safety Evaluation for Harris LAR to Revise Reactor Protection System TS (EPID: L-2021-LLA-0149)

Date: Wednesday, March 23, 2022 1:40:41 PM Attachments: Harris Safety Evaluation -Harris Safety Evaluation -EPID L-2021-LLA-0149 - Revise TS Related to Reactor Protection System .docx

Dave, By application to the U.S. Nuclear Regulatory Commission (NRC) dated August March 6, 2021 (ADAMS Accession No. ML21218A197), Duke Energy (Licensee) proposed changes to the Technical Specifications (TSs) for Shearon Harris Nuclear Power Plant, Unit 1 (HNP), Specifically, the proposed amendment would revise TS 3.3.1, Reactor Trip System Instrumentation, to adjust the reactor trip on turbine trip interlock from P-7 (Low Power Reactor Trips Block) to P-8 (Power Range Neutron Flux). In addition, changes to TS Bases 3.3.1 are required to reflect enabling the reactor trip on turbine trip at the P-8 interlock versus the P-7 interlock. These changes will be made in accordance with the HNP Technical Specifications Bases Control Program.

The SNSB staff reviewed the proposed change and determined that it is acceptable. The safety evaluation provides the basis for the SNSB staff determination, and is attached. I have reviewed the safety evaluation and found that it contains sound regulatory and technical bases. The SNSB staff provided me concurrence on the safety evaluation and this e-mail constitutes my concurrence on the safety evaluation.

In accordance with U.S. Nuclear Regulatory Commission policy, the SNSB staff did not identify any sensitive information contained in the safety evaluation attached.

Docket No.: 50-400

Contact:

Fred M Forsaty, NRR/DSS/SNSB 301-415-8523 Scott Krepel SNSB Branch Chief OWFN 10-E06 423-331-0893 (text message)