ML23067A092
| ML23067A092 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 03/08/2023 |
| From: | Sivaraman M Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| ECM: L94 230124 800 | |
| Download: ML23067A092 (1) | |
Text
Post Office Box 2000, Decatur, Alabama 35609-2000 March 0, 2023 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 2 Facility Operating License No. DPR-52 NRC Docket No. 50-260
Subject:
Browns Ferry Nuclear Plant, Unit 2 Core Operating Limits Report for Cycle 23 Operation, Revision 0 In accordance with the requirements of Technical Specification (TS) 5.6.5.d, the Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN), Unit 2, Cycle 23, Core Operating Limits Report (COLR). Revision 0 of the Unit 2 COLR includes Modes 3 through 5.
There are no new regulatory commitments in this letter. If you have any questions, please contact C. L. Vaughn, Nuclear Site Licensing Manager, at (256) 729-2636.
Respectfully, Manu Sivaraman Site Vice President
Enclosure:
Core Operating Limits Report, (120% OLTP, MELLLA+), for Cycle 23 Operation, TVA-COLR-BF2C23, Revision 0 cc: (w/ Enclosure)
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 2 Core Operating Limits Report, (120% OLTP, MELLLA+), for Unit 2 Cycle 23 Operation, TVA-COLR-BF2C23, Revision 0 (See Attached)
ECM: L94 230124 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: January 30, 2023 Browns Ferry Unit 2Cycle 23 Page ii Core Operating Limits Report, (120% OLTP, MELLLA+)
TVA-COLR-BF2C23, Revision 0(Final)
Operating Modes 3, 4, &5 Only Table of Contents Total Number of Pages = 11 (including review cover sheet)
List of Tables.......................................................................................................................... iii List of Figures......................................................................................................................... iv Revision Log............................................................................................................................v Nomenclature.......................................................................................................................... vi References............................................................................................................................viii 1
Introduction......................................................................................................................1 1.1 Purpose....................................................................................................................1 1.2 Scope.......................................................................................................................1 1.3 Fuel Loading.............................................................................................................1 1.4 Acceptability..............................................................................................................2 2
Shutdown Margin Limit....................................................................................................3
ECM: L94 230124 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: January 30, 2023 Browns Ferry Unit 2Cycle 23 Page iii Core Operating Limits Report, (120% OLTP, MELLLA+)
TVA-COLR-BF2C23, Revision 0(Final)
Operating Modes 3, 4, &5 Only List of Tables Nuclear Fuel Types
...........................................................................................................2
ECM: L94 230124 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: January 30, 2023 Browns Ferry Unit 2Cycle 23 Page iv Core Operating Limits Report, (120% OLTP, MELLLA+)
TVA-COLR-BF2C23, Revision 0(Final)
Operating Modes 3, 4, &5 Only List of Figures No table of figures entries found.
ECM: L94 230124 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: January 30, 2023 Browns Ferry Unit 2Cycle 23 Page v Core Operating Limits Report, (120% OLTP, MELLLA+)
TVA-COLR-BF2C23, Revision 0(Final)
Operating Modes 3, 4, &5 Only Revision Log Number Page Description 0-R0 All New document.
ECM: L94 230124 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: January 30, 2023 Browns Ferry Unit 2Cycle 23 Page vi Core Operating Limits Report, (120% OLTP, MELLLA+)
TVA-COLR-BF2C23, Revision 0(Final)
Operating Modes 3, 4, &5 Only Nomenclature ABSP Automatic Backup Stability Protection APLHGR Average Planar LHGR APRM Average Power Range Monitor AREVA NP Vendor (Framatome, Siemens)
BOC Beginning of Cycle BSP Backup Stability Protection BWR Boiling Water Reactor CAVEX Core Average Exposure CD Coast Down CMSS Core Monitoring System Software COLR Core Operating Limits Report CPR Critical Power Ratio CRWE Control Rod Withdrawal Error CSDM Cold SDM DIVOM Delta CPR over Initial CPR vs. Oscillation Magnitude DSS-CD Detect and Suppress Solution - Confirmation Density EOC End of Cycle EOCLB End-of-Cycle Licensing Basis EOOS Equipment OOS EPU Extended Power Uprate (120% OLTP)
FFTR Final Feedwater Temperature Reduction FFWTR Final Feedwater Temperature Reduction FHOOS Feedwater Heaters OOS ft Foot: English unit of measure for length GNF Vendor (General Electric, Global Nuclear Fuels)
GWd Giga Watt Day HTSP High TSP ICA Interim Corrective Action ICF Increased Core Flow (beyond rated)
IS In-Service kW kilo watt: SI unit of measure for power.
LCO License Condition of Operation LFWH Loss of Feedwater Heating LHGRFAC LHGR Multiplier (Power or Flow dependent)
LPRM Low Power Range Monitor LRNB Generator Load Reject, No Bypass MAPFAC MAPLHGR multiplier (Power or Flow dependent)
ECM: L94 230124 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: January 30, 2023 Browns Ferry Unit 2Cycle 23 Page vii Core Operating Limits Report, (120% OLTP, MELLLA+)
TVA-COLR-BF2C23, Revision 0(Final)
Operating Modes 3, 4, &5 Only MBSP Manual Backup Stability Protection MCPR Minimum CPR MELLLA Maximum Extended Load Line Limit Analysis MELLLA+
Maximum Extended Load Line Limit Analysis Plus MSRV Moisture Separator Reheater Valve MSRVOOS MSRV OOS MTU Metric Ton Uranium MWd/MTU Mega Watt Day per Metric Ton Uranium NEOC Near EOC NRC United States Nuclear Regulatory Commission NSS Nominal Scram Speed NTSP Nominal TSP OLMCPR MCPR Operating Limit OLTP Original Licensed Thermal Power OOS Out-Of-Service OPRM Oscillation Power Range Monitor OSS Optimum Scram Speed PBDA Period Based Detection Algorithm Pbypass Power, below which TSV Position and TCV Fast Closure Scrams are Bypassed PLU Power Load Unbalance PLUOOS PLU OOS PRNM Power Range Neutron Monitor RBM Rod Block Monitor RCPOOS Recirculation Pump OOS (SLO)
RDF Rated Drive Flow RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS RPT OOS RTP Rated Thermal Power SDM Shutdown Margin SLMCPR MCPR Safety Limit SLO Single Loop Operation TBV Turbine Bypass Valve TBVIS TBV IS TBVOOS Turbine Bypass Valves OOS TIP Transversing In-core Probe TIPOOS TIP OOS TLO Two Loop Operation TSP Trip Setpoint TSSS Technical Specification Scram Speed TVA Tennessee Valley Authority
ECM: L94 230124 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: January 30, 2023 Browns Ferry Unit 2Cycle 23 Page viii Core Operating Limits Report, (120% OLTP, MELLLA+)
TVA-COLR-BF2C23, Revision 0(Final)
Operating Modes 3, 4, &5 Only References 1.
BFE-4774, Revision 0, Browns Ferry Unit 2 Cycle 23 In-Core Shuffle, Tennessee Valley Authority, January 2023.
2.
ANP-3996P, Revision 0, Browns Ferry Unit 2 Cycle 23 Fuel Cycle Design Report, Framatome Inc., April 2022.
Methodology References 3.
ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
4.
EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, Siemens Power Corporation, October 1999.
ECM: L94 230124 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: January 30, 2023 Browns Ferry Unit 2Cycle 23 Page 1 Core Operating Limits Report, (120% OLTP, MELLLA+)
TVA-COLR-BF2C23, Revision 0(Final)
Operating Modes 3, 4, &5 Only 1
Introduction In anticipation of cycle startup, it is necessary to describe the expected limits of operation.
1.1 Purpose The primary purpose of this document is to satisfy requirements identified by unit technical specification section 5.6.5. This document is applicable for outage Mode 3, 4, & 5 operation.
This document may be provided, upon final approval, to the NRC.
1.2 Scope This document will discuss the following areas:
3/4 Shutdown Margin (SDM) Limit (Technical Specification 3.1.1)
Applicability: All Modes 1.3 Fuel Loading The core will contain fresh ATRIUM 11, and previously exposed ATRIUM 10XM. Nuclear fuel types used in the core loading are shown in Table 1.1. The core shuffle and final loading were explicitly evaluated for BOC cold shutdown margin performance as documented per Reference
- 1. The planned Core loading analyzed is based on Reference 2.
ECM: L94 230124 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: January 30, 2023 Browns Ferry Unit 2Cycle 23 Page 2 Core Operating Limits Report, (120% OLTP, MELLLA+)
TVA-COLR-BF2C23, Revision 0(Final)
Operating Modes 3, 4, &5 Only Table 1.1 Nuclear Fuel Types
- Fuel Description Original Cycle Number of Assemblies Nuclear Fuel Type (NFT)
Fuel Names (Range)
ATRIUM-10XM XMLC-4087B-15GV80-FBH 21 37 21 FBH001-FBH176 ATRIUM-10XM XMLC-4036B-15GV80-FBH 21 31 22 FBH177-FBH264 ATRIUM-10XM XMLC-4093B-10GV80-FBH 21 56 23 FBH265-FBH320 ATRIUM-10XM XMLC-4058B-15GV80-FBJ 22 216 24 FBJ331-FBJ546 ATRIUM-10XM XMLC-4015B-15GV80-FBJ 22 92 25 FBJ547-FBJ638 ATRIUM 11 AT11-3974B-14GV100-FBK 23 84 26 FBK649-FBK732 ATRIUM 11 AT11-3971B-14GV100-FBK 23 160 27 FBK733-FBK892 ATRIUM 11 AT11-4175B-13GV80-FBK 23 88 28 FBK893-FBK980 1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 3 and 4.
- The table identifies the expected fuel type breakdown in anticipation of final core loading. The final composition of the core depends upon uncertainties during the outage such as discovering a failed fuel bundle, or other bundle damage. Minor core loading changes, due to unforeseen events, will conform to the safety and monitoring requirements identified in this document.
ECM: L94 230124 800 Reactor Engineering and Fuels - BWRFE 1101 Market Street, Chattanooga TN 37402 Date: January 30, 2023 Browns Ferry Unit 2Cycle 23 Page 3 Core Operating Limits Report, (120% OLTP, MELLLA+)
TVA-COLR-BF2C23, Revision 0(Final)
Operating Modes 3, 4, &5 Only 2
Shutdown Margin Limit (Technical Specification 3.1.1)
Assuming the strongest OPERABLE control blade is fully withdrawn, and all other OPERABLE control blades are fully inserted, the core shall be sub-critical and meet the following minimum shutdown margin:
SDM 0.38% dk/k