NL-19-094, 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report

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2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report
ML19360A021
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 12/16/2019
From: Vitale A
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML19360A025 List:
References
NL-19-094
Download: ML19360A021 (2)


Text

  • -==* Entergx NL-19-094 December 16, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

~Entergy Nuclear Operations. Inc.

Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, NY 10511-0249 Tel (914) 254-6700 Anthony J. Vitale Site Vice President 10 CFR 50.46

Subject:

2018 Annual 1 O CFR 50.46 Emergency Core Cooling System Evaluation Changes Report Indian Point Unit Nos. 2 and 3 NRG Docket Nos.50-247 and 50-286 Renewed Facility Operating License Nos. DPR-26 and_ DPR-64

Reference:

Entergy Nuclear Operations, Inc. (Entergy) letter to U.S. Nuclear Regulatory Commission (NRG), "2017 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report," (Letter No. NL-18-082) (ADAMS Accession No. ML18323A081 ), dated November 13, 2018.

This letter provides the annual Title 1 O of the Code of Federal Regulations (1 O CFR) 50.46 report for calendar year 2018 for Indian Point Units 2 (IP2) and 3 (IP3). The prior report for calendar year 2017 was provided in the Reference.

There are no new peak cladding temperature (PCT) adjustments required for the IP2 or the IP3 small and large break loss-of-coolant accident (LOCA) analyses of record (AORs) for calendar year 2018. Although not required by regulation, this letter reports the small break LOCA PCT for IP2 as 1028 degrees Fahrenheit (°F) and IP3 as 1543°F, and the large break LOCA PCT for IP2 as 2119°F and IP3 as 2046°F.

Two separate error corrections resulting in an estimated PCT impact of 0°F were reported by Westinghouse Electric Company, LLC (Westinghouse), concerning the IP2 and IP3 large break LOCA and small break LOCA evaluation models as follows:

1)
2)

U02 Fuel Pellet Heat Capacity (IP2 and IP3)

Vapor Temperature Resetting (IP2 and IP3)

/

NL-19-094 Page 2 of 2 The error corrections and PCT AOR assessment results are further described in the enclosed Westinghouse letter and attachment.

The limiting PCT results for the IP2 and IP3 small and large break LOCAs continue to meet the criteria of 1 O CFR 50.46, paragraph (b)(1) for calendar year 2018.

There are no new commitments being made in this submittal. If you have any questions or require additional information, please contact Ms. Mahvash Mirzai, Manager, Regulatory Assurance, at 914-254-7714.

Anthony J. Vitale AJV/mm/aye

Enclosure:

Westinghouse Letter LTR-LIS-19-14, Indian Point Units 2 and 3, 10 CFR 50.46 Annual Notification and Reporting for 2018 cc:

Regional Administrator, NRG Region I NRG Senior Project Manager, NRG NRR DORL New York State (NYS) Public Service Commission President and CEO, NYSERDA NRG Senior Resident Inspector, Indian Point Energy Center