L-22-194, Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events

From kanterella
(Redirected from L-22-194)
Jump to navigation Jump to search
Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events
ML22262A151
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 09/19/2022
From: Tony Brown
Energy Harbor Nuclear Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML22262A150 List:
References
L-22-194
Download: ML22262A151 (2)


Text

Withhold from Public Disclosure Under 10 CFR 2.390(a)(4) 11Ja energy Energy Harbor Nuclear Corp.

Davis-Besse Nuclear Power Station

~ harbor 550 1 N. State Route 2 Oak Harbor, Ohio 43449 Terry J. Brown 419-32 1-7676 Site Vice President, Davis-Besse Nuclear September 19, 2022 L-22-194 ATTN : Document Control Desk U.S. Nuclear Regulatory Commission Washington , DC 20555-0001

SUBJECT:

Davis-Besse Nuclear Power Station , Unit No. 1 Docket No. 50-346, License No. NPF-3 Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events On July 21 , 2022, Energy Harbor Nuclear Corp. (EHNC) submitted the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events (ADAMS Accession No. ML22202A430) for the Davis-Besse Nuclear Power Station, Unit No. 1. In an email on July 28, 2022, the NRG notified EHNC that information was missing from several enclosures to the EHNC submittal. The document in Enclosure C is missing page 4-2. Also, the affidavit in Enclosure D requests that information in Enclosure E be withheld pursuant to 10 CFR 2.390. However, neither the affidavit nor the document in Enclosure E indicate what information is considered proprietary. EHNC hereby submits four enclosures in response to these issues.

Enclosure A (replacement for Enclosure C of the previous submittal) contains Framatome Inc. document ANP-2718NP-007, which is the non-proprietary version of "Appendix G Pressure-Temperature Limits for 52 EFPY for Davis-Besse Nuclear Power Station." This submittal provides the document in its entirety.

Enclosure B (replacement for Enclosure D of the previous submittal) contains affidavit 32-9271138-003 pursuant to 10 CFR 2.390 requesting that the confidential commercial information provided in Enclosure D be withheld from public disclosure.

Enclosure D contains information to be withheld from public disclosure under 10 CFR 2.390(a)(4). Upon removal of Enclosure D, this letter is uncontrolled.

Withhold from Public Disclosure Under 10 CFR 2.390(a)(4)

Davis-Besse Nuclear Power Station, Unit No. 1 L-22-194 Page 2 Enclosure C (replacement for Enclosure F of the previous submittal) contains Framatome Inc. document 32-9344638-001 "Updated inputs to 52 EFPY P-T Operating Curves." This document is the nonproprietary version of Enclosure D and was updated to reflect the new revision number of that document.

Enclosure D (replacement for Enclosure E of the previous submittal) contains Framatome Inc. document 32-9271138-003 "Updated inputs to 52 EFPY P-T Operating Curves" with the proprietary information identified in brackets.

There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required , please contact Mr. Phil H. Lashley, Manager - Fleet Licensing, at (330) 696-7208.

Enclosures:

A. Framatome Inc. document ANP-2718NP-007 "Appendix G Pressure-Temperature Limits for 52 EFPY for Davis-Besse Nuclear Power Station." Nonproprietary B. Affidavit Pursuant to 10 CFR 2.390 for 32-9271138-003 C. Framatome Inc. document 32-9344638-001 "Updated inputs to 52 EFPY P-T Operating Curves." Nonproprietary D. Framatome Inc. document 32-9271138-003 "Updated inputs to 52 EFPY P-T Operating Curves." Proprietary cc: NRC Region Ill Administrator NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board Enclosure D contains information to be withheld from public disclosure under 10 CFR 2.390(a)(4). Upon removal of Enclosure D, this letter is uncontrolled.