PLA-7770, CFR 50.46 Annual Report

CFR 50.46 Annual Report

ML19161A131
Person / Time
Site:	Susquehanna
Issue date:	06/10/2019
From:	Cimorelli K Susquehanna, Talen Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-7770
Download: ML19161A131 (4)

Text

Kevin Cimorelli Susquehanna Nuclear, LLC JUN 1 0 2019 Site Vice President 769 Salem Boulevard Berwick, PA 18603 TALEN~

Tel. 570.542.3795 Fax 570.542.1504 Kevin.Cimorelli@TalenEnergy.com ENERGY 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-7770 and 50-388 References 1. "Susquehanna Steam Electric Station (SSES) 10 CFR 50.46 -Annual Report PLA-7606, "dated June 07, 2017 (ADAMS Accession No. ML17158B382)

2. "Susquehanna Steam Electric Station 10 CFR 50.46 -Annual Report PLA-7713, "dated June 14, 2018 (ADAMS Accession No. ML18165A460)

3. Framatome Record FS1-0039922, Revision 1.0, "10 CFR 50.46 PCT Error Reportingjor the Susquehanna Units," dated September 17, 2018

4. Framatome Record FS1-0043512, Revision 1.0, "10 CFR 50.46 PCT Error Reporting/or the Susquehanna Units, "dated April 22, 2019 Pursuant to the reporting requirements of 10 CFR 50.46(a)(3)(ii), Susquehanna Nuclear, LLC is submitting the Emergency Core Cooling System (ECCS) evaluation model annual report for Susquehanna Steam Electric Station (SSES) Units 1 and 2. The attached report summarizes the nature of and estimated effect of any modeling changes or error corrections in the ECCS model for the period April25, 2018 through April22, 2019 for SSES Units 1 and 2.

Since the last 10 CFR 50.46 annual report dated June 14, 2018 (Reference 2), there has been a Peak Cladding Temperature (PCT) change reported toSSES resulting from a modeling change or error correction to the ECCS evaluation method. The current 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 Ms. Melisa Krick, Manager-Nuclear Regulatory Affairs, at (570) 542-1818.

K. Cimorelli 0 CFR 50.46 ECCS Evaluation Model Annual Report

Document Control Desk PLA-7770 Copy: NRC Region I Ms. T. E. Hood, NRC Project Manager Ms. J. Tobin, NRC Project Manager Ms. L. Micewski, NRC Sr. Resident Inspector Mr. M. Shields, PA DEP/BRP

Attachment to PLA- 7770 10 CFR 50.46 ECCS Evaluation Model Annual Report

Attachment to PLA-7770 Page 1 of 1 BACKGROUND In accordance with 10 CFR 50.46(a)(3)(ii), this annual report summarizes the nature of and estimated effect of any modeling changes or errors corrections in the ECCS model for the period April 25, 2018 through April 22, 2019 for 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 April 25, 2018 to April 22, 2019, there has been one reportable 10 CFR 50.46 modeling change or error correction to the ECCS evaluation method since the previous 10 CFR 50.46 report (Reference 2). A review of the Susquehanna RELAX steam dryer related inputs identified a need to update the volume input of the steam dryer assembly as well as the free volume input for the dryer region (Reference 3). The impact of this change is summarized in Table 1.

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 report is required.

IMPACT Table 1 Non-Zero PCT Changes Resulting from Modeling Changes / Error Corrections in Calculated ECCS Performance Evaluation Model: Framatome EXEM BWR-2000 LOCA Methodology Estimated Absolute PCT (°F) Value of Description of Change/Error PCT (°F)

HUXY capability enhancement to model each fuel rod individually -1 1 (Reference 1)

Updated steam dryer information +5 5 (Reference 3)

Total Since Initial PCT +4 6 (Reference 4)

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