PLA-7606, Submittal of 10 CFR 50.46 - Annual Report

Submittal of 10 CFR 50.46 - Annual Report

ML17158B382
Person / Time
Site:	Susquehanna
Issue date:	06/07/2017
From:	Berryman B Susquehanna, Talen Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-7606
Download: ML17158B382 (3)

Text

Brad Berryman Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 TALEN~

Brad.Berryman @TalenEnergy.com ENERGY U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 10 CFR 50.46 SUSQUEHANNA STEAM ELECTRIC STATION (SSES) 10 CFR 50.46 -ANNUAL REPORT Docket Nos. 50-387 PLA-7606 and 50-388 Reference 1: PLA-7475, J A. Franke (Susquehanna Nuclear, LLC) to Document Control Desk (USNRC), "Susquehanna Steam Electric Station, 10 CFR 50.46 -Annual Report,"

dated June 7, 2016.

Reference 2: AREVA Record FS1-0031872, Revision 1.0, "10 CFR 50.46 PCT Error Reporting for the Susquehanna Units, "dated April 26, 2017.

Pursuant to the reporting requirements of 10 CFR 50.46(a)(3)(ii) Susquehanna Steam Electric Station (SSES) is submitting the Emergency Core Cooling System (ECCS) evaluation model annual repmt for SSES Units 1 and 2. to this letter summarizes the nature of and estimated effect of any changes or errors in the ECCS models for SSES Units 1 and 2 for the repmting period of April28, 2016 through April 26, 2017.

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. - SSES Units 1 & 2- 10 CFR 50.46 ECCS Evaluation Model Annual Report 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 1 to PLA- 7606 SSES Units 1 & 2 -

10 CFR 50.46 ECCS Evaluation Model Annual Report

Attachment 1 to PLA-7606 Page 1 of 1 BACKGROUND In accordance with 10 CFR 50.46(a)(3)(ii), this annual repmt summarizes the nature of and estimated effect of any changes or enors in the Emergency Core Cooling System (ECCS) model for the period April28, 2016 through April26, 2017 for Susquehanna Steam Electric Station (SSES) Units 1 and 2.

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

For the repmting period of April28, 2016 to April26, 2017, there have been two repmtable changes for 10 CFR 50.46 as stated in Reference 2:

1) Previous analyses have been perfmmed on a DEC ALPHA computer platfmm. New analyses have been qualified on a LINUX based computer platfmm. The impact of the change in platfmms was estimated to have an insignificant impact on Peak Clad Temperature (PCT). Therefore, the 10 CFR 50.46 repmtable impact is estimated as 0°F.

2) Previous versions of the heatup code HUXY allowed a limited number of different rod types to be modeled. The method grouped rods that had similar local peaking histories.

HUXY has been revised to no longer have a limited number of rod groupings. This change in rod grouping resulted in a 1°F decrease in PCT. Therefore, the 10 CFR 50.46 repmtable impact is estimated as -1 °F.

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 Changes and/or Errors in Calculated ECCS Perfmmance Evaluation Model: AREV A NP EXEM BWR-2000 Methodology Estimated Absolute Value Description of Change/Error t.PCT (°F) of t.PCT (°F)

HUXY capability enhancement to model each fuel rod individually -1 1 I Total -1 1 CONCLUSION As documented in Table 1, the SSES Unit 1 and Unit 2 Loss of Coolant Accident analysis Peak Clad Temperature (PCT) remains in compliance with 10 CFR 50.46(b)(l), which requires that the PCT shall not exceed 2200°F.