PLA-7713, Submittal of Emergency Core Cooling System Evaluation Model Annual Report

Submittal of Emergency Core Cooling System Evaluation Model Annual Report

ML18165A460
Person / Time
Site:	Susquehanna
Issue date:	06/14/2018
From:	Berryman B Susquehanna, Talen Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-7713
Download: ML18165A460 (3)

Text

Brad Berryman Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 TALEN~.

Tel. 570.542.2904 Fax 570.542.1504 ENERGY JUN 1 4 2018 Brad.Berryman @TalenEnergy.com U.S. Nuclear Regulatory Commission 10 CFR 50.46 Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION 10 CFR 50.46 -ANNUAL REPORT Docket Nos. 50-387 PLA-7713 and 50-388 Reference 1: "Susquehanna Steam Electric Station 10 CFR 50.46 -Annual Report PLA-7606,"

dated June 7, 2017 (ADAMS Accession No. ML17158B382).

2: Framatome Record FS1-0037122, Revision 1.0, "10 CFR 50.46 PCT Error Reportingfor Susquehanna Units," datedApril24, 2018 Pursuant to the repmiing requirements of 10 CFR 50.46(a)(3)(ii), Susquehanna Nuclear, LLC is submitting the Emergency Core Cooling System (ECCS) evaluation model annual repmi for Susquehanna Steam Electric Station (SSES) Units 1 and 2. The attached repmi summarizes the nature of and estimated effect of any changes or errors in the ECCS model for the period April 27, 2017 through April24, 2018 for SSES Units 1 and 2.

Since the last 10 CFR 50.46 annual repmi dated June 7, 2017 (Reference 1), there have been no Peak Cladding Temperature (PCT) changes repmied toSSES and no modeling or e11'or co11'ections to the ECCS evaluation method. The cu11'ent licensing basis PCT remains in compliance with 10 CFR 50.46 requirements.

There are no new regulatory commitments contained in this submittal.

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

B. Be11'yman Attachment- 10 CFR 50.46 ECCS Evaluation Model Annual Repmi for SSES Units 1 and 2 Copy: NRC Region I Ms. T. E. Hood, NRC Project Manager Ms. L. Micewski, NRC Sr. Resident Inspector Mr. M. Shields, PA DEP/BRP

Attachment to PLA- 7713 10 CFR 50.46 ECCS Evaluation Model Annual Report for SSES Units 1 and 2

Attachment to PLA-7713 Page 1 of 1 BACKGROUND In accordance with 10 CFR 50.46(a)(3)(ii), this annual reportsurnmarizes the nature of and estimated effect of any changes or errors in the Emergency Core Cooling System (ECCS) model for the period April27, 2017 through April24, 2018 for Susquehanna Steam Electric Station (SSES) Units 1 and 2.

DISCUSSION The ECCS performance evaluation method applicable to both SSES Units 1 and 2 is the Framatome EXEM BWR-2000 LOCA Methodology.

For the reporting period of April27, 2017 to April24, 2018, there have been no repmiable changes for 10 CFR 50.46 as stated in Reference 2.

The total change listed in the last column of Table 1 does not meet the significance threshold for change (50°F) identified in 10 CFR 50.46(a)(3)(i) for which a 30-day repmi is required.

IMPACT Table 1 Non-Zero Changes and/or Enors in Calculated ECCS Performance Evaluation Model: Framatome EXEM BWR-2000 LOCA Methodology Estimated Absolute Value Description of Change/Error ilPCT (°F) of ilPCT (°F)

HUXY capability enhancement to model each fuel rod individually

-1 1 (Repmied in Reference 1)

I Total -1 1 CONCLUSION As documented in Table 1, the SSES Units 1 and 2 Loss of Coolant Accident Analysis Peak Clad Temperature (PCT) remains in compliance with 10 CFR 50.46(b)(1), which requires that the PCT not exceed 2200°F.