PLA-7475, Submittal of 10 CFR 50.46 - Annual Report

Submittal of 10 CFR 50.46 - Annual Report

ML16159A005
Person / Time
Site:	Susquehanna
Issue date:	06/07/2016
From:	Franke J Susquehanna, Talen Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-7475
Download: ML16159A005 (2)

Text

.Jon A. Franke Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 TALEN ~

Tel. 570.542.2904 Fax 570.542.1504 ENERGY Jon.Franke@TalenEnergy.com JUN 0 7 201 6 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-7475 and 50-388

Reference:

I. PLA-7339, J. A. Franke (Susquehanna Nuclear, LLC) to Document Control Desk (USNRC), "Susquehanna Steam Electric Station, 10 CFR 50.46 -Annual Report,"

dated June 18, 2015.

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

10 CPR 50.46(a)(3)(ii) requires (in part) annual repmiing of changes to or enors 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 CPR 50.46 requirements.

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

Since April28, 2015 (as reported by Reference 1) until April28, 2016, there have been no non-zero Peak Cladding Temperature (PCT) changes reported to Susquehanna Nuclear, LLC for Units 1 and 2. Thus, the cunent licensing basis PCT remains valid.

There have been no modeling or e1Tor conections to the ECCS evaluation method since the last report (Reference 1).

This letter meets the annual repmiing requirements.

Susquehanna Nuclear, 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 CPR 50.46limit, and to ensure that the 10 CPR 50.46 reporting requirements are met.

Document Control Desk PLA-7475 There are no new regulatory commitments contained in this submittal.

If you have any questions regarding this letter, please contact Mr. Jason R. Jennings, Manager- Nuclear Regulatory Affairs, at (570) 542-3155.

Sincerely, J. A. Franke Copy: NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Ms. T. E. Hood, NRC Project Manager Mr. M. Shields, PA DEP/BRP

.Jon A. Franke Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 TALEN ~

Tel. 570.542.2904 Fax 570.542.1504 ENERGY Jon.Franke@TalenEnergy.com JUN 0 7 201 6 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-7475 and 50-388

Reference:

I. PLA-7339, J. A. Franke (Susquehanna Nuclear, LLC) to Document Control Desk (USNRC), "Susquehanna Steam Electric Station, 10 CFR 50.46 -Annual Report,"

dated June 18, 2015.

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

10 CPR 50.46(a)(3)(ii) requires (in part) annual repmiing of changes to or enors 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 CPR 50.46 requirements.

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

Since April28, 2015 (as reported by Reference 1) until April28, 2016, there have been no non-zero Peak Cladding Temperature (PCT) changes reported to Susquehanna Nuclear, LLC for Units 1 and 2. Thus, the cunent licensing basis PCT remains valid.

There have been no modeling or e1Tor conections to the ECCS evaluation method since the last report (Reference 1).

This letter meets the annual repmiing requirements.

Susquehanna Nuclear, 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 CPR 50.46limit, and to ensure that the 10 CPR 50.46 reporting requirements are met.

Document Control Desk PLA-7475 There are no new regulatory commitments contained in this submittal.

If you have any questions regarding this letter, please contact Mr. Jason R. Jennings, Manager- Nuclear Regulatory Affairs, at (570) 542-3155.

Sincerely, J. A. Franke Copy: NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Ms. T. E. Hood, NRC Project Manager Mr. M. Shields, PA DEP/BRP