ML13172A041: Difference between revisions

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#REDIRECT [[PLA-7029, Susquehanna Steam Electric Station (SSES) - 10 CFR 50.46 - Annual Report (PLA-7029)]]
{{Adams
| number = ML13172A041
| issue date = 06/20/2013
| title = Susquehanna Steam Electric Station (SSES) - 10 CFR 50.46 - Annual Report (PLA-7029)
| author name = Franke J A
| author affiliation = PPL Susquehanna, LLC
| addressee name =
| addressee affiliation = NRC/NRR, NRC/Document Control Desk
| docket = 05000387, 05000388
| license number =
| contact person =
| case reference number = PLA-7029
| document type = Letter, Annual Report
| page count = 2
}}
 
=Text=
{{#Wiki_filter:JUN 2 0 2013 Jon A. Franke Site Vice President U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 jfranke@ pplweb.com SUSQUEHANNA STEAM ELECTRIC STATION (SSES) 10 CFR 50.46 -ANNUAL REPORT Docket Nos. 50-387 and 50-388 PLA-7029  
 
==Reference:==
: 1. PLA-6870, T. S. Rausch (PPL) to Document Control Desk (USNRC), "Susquehanna Steam Electric Station , 10 CFR 50.46 -Annual Report," dated June 21, 2012. 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 June 14, 2012 (Reference
: 1) until April18, 2013, 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-7029 If you have any questions, please contact Mr. John L. Tripoli, Manager-Nuclear Regulatory Affairs at (570) 542-3100. J . Franke Copy: NRC Region I Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. L. J. Winker, PA DEP/BRP}}

Revision as of 20:32, 17 March 2019

Susquehanna Steam Electric Station (SSES) - 10 CFR 50.46 - Annual Report (PLA-7029)
ML13172A041
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 06/20/2013
From: Franke J A
Susquehanna
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
PLA-7029
Download: ML13172A041 (2)
v • d • e


Text

JUN 2 0 2013 Jon A. Franke Site Vice President U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 jfranke@ pplweb.com SUSQUEHANNA STEAM ELECTRIC STATION (SSES) 10 CFR 50.46 -ANNUAL REPORT Docket Nos. 50-387 and 50-388 PLA-7029

Reference:

1. PLA-6870, T. S. Rausch (PPL) to Document Control Desk (USNRC), "Susquehanna Steam Electric Station , 10 CFR 50.46 -Annual Report," dated June 21, 2012. 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 June 14, 2012 (Reference

1) until April18, 2013, 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-7029 If you have any questions, please contact Mr. John L. Tripoli, Manager-Nuclear Regulatory Affairs at (570) 542-3100. J . Franke Copy: NRC Region I Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. L. J. Winker, PA DEP/BRP

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