ML14258A729

NRR E-mail Capture - Closing Document for TAC MF3803 - Waterford Steam Electric Station 10 CFR 50.46 Report

ML14258A729
Person / Time
Site:	Waterford
Issue date:	09/05/2014
From:	Benjamin Parks NRC/NRR/DSS
To:	Michael Orenak Division of Operating Reactor Licensing
References
MF3803
Download: ML14258A729 (2)

Text

NRR-PMDAPEm Resource From: Parks, Benjamin Sent: Friday, September 05, 2014 1:34 PM To: Orenak, Michael Cc: Shoop, Undine

Subject:

Closing Document for TAC MF3803 - Waterford Steam Electric Station 10 CFR 50.46 Report Pursuant to 10 CFR 50.46(a)(3), Entergy Operations, the licensee for Waterford Steam Electric Station, Unit 3, submitted a report describing a re-analysis performed for the plant related to the installation of replacement steam generators.

The report was submitted by letter dated March 25, 2014 (Agencywide Document Access and Management System (ADAMS) Accession Number ML14085A465).

The March 24, 2014, letter stated that the notification was submitted to provide notification of a significant change to the peak cladding temperature for both the large-break (LB) and small-break (SB) loss of coolant accident (LOCA) analyses. The letter also stated that the new PCT values were determined from complete re-analyses performed in accordance with acceptable evaluation models, which had previously been approved for use at Waterford 3.

The NRC staff reviewed a summary of these analyses that was documented in the Waterford Updated Final Safety Analysis Report. The NRC staff determined, based on its review, that the re-analyses were acceptable, based on the following considerations:

• The analyses were performed using NRC-approved analytic methods, which had been specifically approved for use at Waterford.

• The Large Break LOCA analysis results indicated behavior typical of, and expected for, the nuclear steam supply system design and the evaluation model used.

• The Small Break LOCA analysis included a break spectrum that demonstrated that the licensee identified the limiting break size that caused a delay in the empty time of the safety injection accumulators, which drove a high predicted peak cladding temperature.

Since the licensee stated that the reported values were based on a re-analysis, the NRC staff considers the letter to constitute, providing a reanalysis, consistent with the regulatory requirement to include, with a report describing a significant change, a proposed schedule for doing so, or taking other action as may be needed. The significant change is considered to be the adjustments to the input of the evaluation models to reflect the installation of new steam generators.

This email concludes Reactor Systems Branch review efforts under Task Assignment Control Number MF3803.

Benjamin T. Parks Reactor Systems Branch, NRR NEW PHONE #415-0979 1

Hearing Identifier: NRR_PMDA Email Number: 1569 Mail Envelope Properties (8C658E9029C91D4D90C6960EF59FC0D60135CAD3B781)

Subject:

Closing Document for TAC MF3803 - Waterford Steam Electric Station 10 CFR 50.46 Report Sent Date: 9/5/2014 1:34:13 PM Received Date: 9/5/2014 1:34:15 PM From: Parks, Benjamin Created By: Benjamin.Parks@nrc.gov Recipients:

"Shoop, Undine" <Undine.Shoop@nrc.gov>

Tracking Status: None "Orenak, Michael" <Michael.Orenak@nrc.gov>

Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 2386 9/5/2014 1:34:15 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received: