Letter Sequence Approval |
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EPID:L-2018-LLL-0022, Extended Power Uprate Replacement Steam Dryer Core Flow Sweep Test Report (Approved, Closed) |
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Category:Letter
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[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 22, 2019 Mr. Joseph W. Shea, Vice President Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT 3 - REVIEW OF EXTENDED POWER UPRATE IMPLEMENTATION POWER ASCENSION RESULTS AND REPORTS REGARDING REPLACEMENT STEAM DRYERS (EPID L-2018-LLL-0022)
Dear Mr. Shea:
By Letter dated August 14, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17032A120), to Tennessee Valley Authority (the licensee, TVA),
the Nuclear Regulatory Commission (NRC) issued Amendment Nos. 299, 323, and 283 to Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 for Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3, respectively. These amendments authorized an increase in the maximum licensed thermal power level for Browns Ferry units, from 3458 megawatts thermal (MWt) to 3952 MWt, which is an increase of approximately 20-percent above the original licensed thermal power level of 3293 MWt. This change in power level is considered an extended power uprate (EPU).
The NRC staff approval of the EPU was based, in part, on the capability for the licensee to monitor, evaluate, and take prompt action in response to potential adverse flow effects as a result of EPU operation on plant structures, systems, and components (including verifying the continued structural integrity of the replacement steam dryer (RSD)), and meeting certain license conditions.
The Browns Ferry Unit 3 License Condition 2.C(14)(b)4.b requires performance of a core flow sweep test tp determine any compounding effect due to alignment of Vane Passing Frequency and Safety Relief Valve resonance frequencies. The core flow sweep test results are required to be provided to the NRC within 30 days after completion of the test at EPU conditions. By letter dated August 13, 2018 (ADAMS Accession No. ML18229A219), TVA submitted to the NRC the General Electric Hitachi (GEH) document: NEDC-33893P, Revision 0, "Browns Ferry Nuclear Plant, Unit 3 Replacement Steam Dryer Power Ascension Monitoring Core Flow Sweep Test Report." Based on core flow sweep tests, the licensee developed core flow factors and vane passing frequency scale factors to increase the dryer stresses at EPU conditions for the upper and lower dryer portions. In addition, by letter dated November 15, 2018 (ADAMS Accession No. ML18319A329), TVA responded to the NRC questions in a supplement related to the Browns Ferry Unit 3 core flow sweep test results. The NRC staff completed its review of
J.Shea TVA submitted reports and finds the core flow sweep test reported results acceptable.
Therefore, the staff determined that the licensee meets License Condition 2.C(14)(b)4.b.
In accordance with license conditions 2.C (14)(b)4.a, by letter dated October 24, 2018 (ADAMS Accession No. ML18298A316), as supplemented by letter dated January 2, 2019, TVA submitted the results of the Browns Ferry Unit 3 RSD EPU power ascension testing (90-Day EPU Reports) to the NRC. The specific results are contained in the GEH documents attached to TVA's letter GEH document: NEDC-33894P, Revision 0: EPU Full Re-Analysis and Benchmarking Report (PBLE01 ), and GEH document: NEDC-33895P, Revision 0, "EPU Full Re-Analysis and Benchmarking Report (PBLE02)." The NRC staff completed its review of the Unit 3 RSD power ascension testing results, final load definition as well as the results of a complete structural re-analysis Unit 3 RSD verifying its *structural integrity using the end-to-end biases / uncertainties at Browns Ferry EPU conditions. Based on the review of these reports, the licensee adequately demonstrated that the stresses in the replacement steam dryer are below the ASME Code acceptance limits, thus maintaining structural integrity at the EPU conditions. Therefore, the NRC staff determined that the 90-day EPU reports for Browns Ferry Unit 3 are acceptable and meet the requirements of License Condition 2.C(14)(b)4.a.
Browns Ferry Unit 3 License Condition 2.C(14)(b)5 requires the licensee to provide within 90 days following completion of EPU power ascension testing , a flow induced vibration (FIV) summary report for certain specified Browns Ferry Unit 3 piping and valve locations, including the vibration data and evaluation of the measured data compared to acceptance limits. In accordance with License Condition 2.C(14)(b)5, by letter dated September 13, 2018 (ADAMS Accession No. ML18257A103), TVA submitted "Browns Ferry Nuclear Plant Unit 2 Flow Induced Vibration Summary Report" that provided an evaluation of FIV data obtained at approximately 3630 MWt, 3803 MWt, and 3952 MWt for Browns Ferry Unit 3. The licensee presented the vibration measurement results along with Level-2 and Level-1 allowable limits.
Based on review of the FIV results, and licensee's evaluations, all the monitored locations meet the Level-1 and Level-2 allowable limits. Therefore, the staff concluded that the licensee meets the requirements of License condition 2C(14)(b)5.
Based on the above reviews, the NRC staff determined the licensee's submitted reports for Browns Ferry Unit 3 EPU power ascension are acceptable and meet the associated license conditions.
If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov.
Sincerely, E- ~ l '---
Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-296 cc: Listserv
ML190938198
- via email OFFICE DORL/LPLI 1-2/PM DORL/LPLI 1-2/LA DE/EMIB/BC* DORL/LPLll-2/BC DORL/LPLI 1-2/PM NAME FSaba BClayton SBailey UShoop FSaba DATE 4/11/19 4/11/19 4/11/19 4/19/19 4/22/19
