CNL-18-099, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 2, Operator Training Results

Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 2, Operator Training Results

ML18205A498
Person / Time
Site:	Browns Ferry
Issue date:	07/23/2018
From:	Henderson E Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-18-099
Download: ML18205A498 (4)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-18-099 July 23, 2018 10 CFR 50.90 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 2, Operator Training Results

Reference:

Letter from TVA to NRC, CNL-18-002, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, dated February 23, 2018 (ML18057B276)

By the reference letter, Tennessee Valley Authority (TVA) submitted a request for a Technical Specification (TS) amendment (TS-510) to Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 for Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3, respectively. The proposed amendment allows operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) operating domain and use of the Detect and Suppress Solution - Confirmation Density (DSS-CD) stability solution.

The purpose of this letter is to provide the BFN-related response to a specific Peach Bottom Atomic Power Station (PBAPS) NRC request for additional information that was sent to Exelon Generation regarding operator actions associated with the MELLLA+ analysis. The Enclosure to this letter provides the BFN operator response times for operator actions to mitigate an Anticipated Transient Without Scram (ATWS) event based on operator training completed to support the MELLLA+ analysis.

TVA has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in the reference letter. The supplemental information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. In addition, the supplemental information in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed license amendment.

Additionally, in accordance with 10 CFR 50.91(b)(1), TVA is sending a copy of this letter and the enclosure to the Alabama State Department of Public Health.

U.S. Nuclear Regulatory Commission CNL-18-099 Page 2 July 23, 2018 There are no new regulatory commitments associated with this submittal. If there are any questions or if additional information is needed, please contact Edward D. Schrull at (423) 751-3850.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 23rd day of July 2018.

Respectfully,

~cf/,~

E. K. Henderson Director, Nuclear Regulatory Affairs Enclosure':

Browns Ferry Nuclear Plant Units 1, 2, and 3 Maximum Extended Load Line Limit Analysis Plus Operator Training Results cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant State Health Officer, Alabama State Department of Public Health

Enclosure Browns Ferry Nuclear Plant Units 1, 2, and 3 NRC Docket Nos. 50-259, 50-260, and 50-296 Maximum Extended Load Line Limit Analysis Plus Operator Training Results

ENCLOSURE Training on operator immediate actions supporting the MELLLA+ analysis was completed from April 2, 2018 to May 10, 2018, for all 16 BFN Operating Shift Crews. All 16 Operating Shift Crews were evaluated to ensure that they can meet the operator action times consistent with the assumptions in the MELLLA+ analysis. The response times assumed in the MELLLA+

analysis are Standby Liquid Control (SLC) pump initiation within 120 seconds and reduction of reactor water level by reducing feedwater flow within 120 seconds. Results of the operating crews evaluation regarding the operator actions are provided below.

Average Operator Crew Action Required Time Action Time SLC pump initiation 44 seconds 120 seconds Commence reactor water level 41 seconds 120 seconds reduction by reducing feedwater flow Note: SLC pump initiation time is from the failure-to-scram until the SLC pump is started.

Reactor water level reduction time is from the failure-to-scram until the injection rate of an in-service injection system is lowered.

E-1