PLA-7175, (SSES)- 10 CFR 50.46 - Annual Report

(SSES)- 10 CFR 50.46 - Annual Report

ML14171A089
Person / Time
Site:	Susquehanna
Issue date:	06/20/2014
From:	Franke J Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-7175
Download: ML14171A089 (2)

Text

Jon A. Franke PPL Susquehanna, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 JUN 2 0 2014 jfranke@ pplweb.com U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION (SSES) 10 CFR 50.46 - ANNUAL REPORT Docket Nos. 50-387 PLA-7175 and 50-388

Reference:

1. PLA-7029, J. A. Franke (PPL) to Document Control Desk (USNRC),

"Susquehanna Steam Electric Station, 10 CPR 50.46 -Annual Report,"

dated June 20, 2013.

This report is being sent in accordance with 10 CFR 50.46(a)(3)(ii).

10 CFR 50.46(a)(3)(ii) requires (in part) annual reporting of changes to or errors in evaluation models used for calculating Emergency Core Cooling System (ECCS) performance, and an estimate of their effect on the limiting ECCS analysis.

Additionally, a proposed schedule is required for re-analysis or identification of other actions necessary to show compliance with 10 CFR 50.46 requirements.

The ECCS performance evaluation method applicable to both SSES Unit 1 and Unit 2 is the AREV A NP EXEM BWR-2000 LOCA Methodology.

Since April18, 2013 (as reported by Reference 1) until May 6, 2014, there have been no non-zero Peak Cladding Temperature (PCT) changes reported to PPL Susquehanna, LLC for Units 1 and 2. Thus, the current licensing basis PCT remains valid and no further actions are required.

There have been no modeling changes or error corrections to the ECCS evaluation method since the last report (Reference 1).

This letter meets the annual reporting requirements.

PPL Susquehanna, LLC will continue to track future changes to the evaluation models used in the applicable loss of coolant accident (LOCA) analysis methods to ensure that the PCT values remain below the 10 CFR 50.46limit, and to ensure that the 10 CFR 50.46 reporting requirements are met.

There are no new regulatory commitments contained in this submittal.

Document Control Desk PLA-7175 If you have any questions, please contact Mr. John L. Tripoli, Manager - Nuclear Regulatory Affairs at (570) 542-3100.

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/ .A.Franke Copy: NRC Region I Mr. J. Greives, NRC Sr. Resident Inspector Mr. J. Whited, NRC Project Manager Mr. L. Winker, P A DEP/BRP