ML103260116

From kanterella
Jump to navigation Jump to search
Core Operating Limits Report Cycle 9 Operation
ML103260116
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 11/17/2010
From: Krich R
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML103260116 (40)
v • d • e


Text

Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing November 17, 2010 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Facility Operating License No. DPR-33 NRC Docket No. 50-259

Subject:

Browns Ferry Nuclear Plant, Unit 1, Core Operating Limits Report for Cycle 9 Operation In accordance with the requirements of Technical Specification 5.6.5.d, the Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant, Unit 1, Cycle 9, Core Operating Limits Report (COLR). The Unit 1, Cycle 9, COLR includes all modes of operation (Modes 1 through 5).

There are no new commitments contained in this letter. If you have any questions, please contact Tom Matthews at (423) 751-2687.

Respectfully, R. M. Krich

Enclosure:

Core Operating Limits Report, (105% OLTP), for Cycle 9 Operation TVA-COLR-BF1 C9, Revision 0, dated October 2010 cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant printed on recycled paper (U-

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit I Core Operating Limits Report, (105% OLTP), for Cycle 9 Operation TVA-COLR-BF1C9, Revision 0, dated October 2010

j ENO;' L-52 16016t 801 QA oument Pagm Affmcf§d; All h*flt--*30(1, Ivi*lfn 0 LINPG Nuclear Fuel Engineering - BWRFE 1101 Mrtker tret SUM attanooga, TN 37402 Browns Ferry Unit I Cycle 9 Core Operating Limits Report, (105% OLTP)

TVA-COLR-BFIC9 Revision o(Finai)

(OVtobe 010, P§00 V October 2010 Prepared:, ;W.-, 9r ý _i- Date:

Date: 0,,*-ii Verified, 'ý ýohefl, E~ngineer Approved: 6,(. /.Date,

.....it G. C, Storey, Mai BWR Fuel Engineering Date; / Aozo/O_

36ek, Manager, Reator Engineering Approved:

U

Nuclear Fuel Engineering - BWRFE NPG Date: October 15, 2010 1101 Market Street Chattanooga, TN 37402 EDMS: L32 101015 801 Table of Contents Total Number of Pages = 38 (including review cover sheet)

List of T a b le s ................................................................................................................................................. iii List of F ig u re s ................................................................................................................................................ iv Re v is ion Log ................................................................................................................................... v No m e nc la tu re ................................................................................................................................................ vi References .................................................................................................... ................... ...... ....... viii 1 Intro d u c tio n ........................................................................................................................... 1 1 .1 P u rp o s e ......................................................................................................................... 1 1 .2 S c o p e ............................................................................................................................ 1 1.3 Fuel Loading .................................................................................................................. 1 1.4 Acceptability .................................................................................................................. 1 2 APLHG R Lim its .................................................................................................................... 3 2.1 Rated Power and Flow Lim it: APLHG RRATED ........................................................... 3 2.2 Off-Rated Power Dependent Lim it: APLHG Rp ......................................................... 3 2.3 Off-Rated Flow Dependent Lim it: APLHGRF ........................................................... 3 2.4 Single Loop O peration Lim it: APLHG RSLO ............................................................... 3 2.5 Equipment Out-Of-Service Corrections .................................. 5 3 LHG R Lim its ......................................................................................................................... 6 3.1 Rated Power and Flow Lim it: LHGRRATED ................................................................ 6 3.2 Off-Rated Power Dependent Lim it: LHG Rp ............................................................. 6 3.3 Off-Rated Flow Dependent Lim it: LHG RF ................................................................ 6 3.4 Single Loop O peration Lim it: LHG RSLO ........................................................................ 6 3.5 Equipm ent O ut-Of-Service Corrections .................................................................... 6 4 O LM CPR Lim its ................................................................................................................. 14 4.1 Rated Power and Flow Lim it: MCPRRATED ............................................................. 14 4.1.1 Scram Tim ing Dependence ............................................................................ 14 4.1.2 Equipment O ut-Of-Service (EOOS) Options .................................................. 15 4.1.3 Exposure Dependent Lim its ............................................................................ 15 4.2 Flow Dependent MCPR Lim it: MCPRF .................................................................. 16 4.3 Single Loop O peration Lim it: MCPRSLO .................................................................. 16 4.4 Power Dependent MCPR Lim it: MCPRp ............................................................... 16 5 APRM Flow Biased Rod Block Trip Settings .................................................................. 24 6 Rod Block Monitor (RBM ) Trip Setpoints and Operability ........................ ......................... 25 7 Shutdown Margin Lim it.................................................................................................. 27 Appendix A: Therm al-Hydraulic Stability ............................................................................. 28 Browns Feny Unit I Cycle 9 Page ii Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street Chattanooga, TN 37402 EDM&S L32 101015 801 List of Tables Nuclear Fuel Types ............................................................... I....................................................... 2 Analytical RBM Trip Setpoints .............................................................................................. 25 RBM Setpoint Applicability .................................................................................................... 25 Control Rod W ithdrawal Error Results ................................................................................... 26 O PRM Setpoints ........................................................................................................................ 30 Browns Ferry Unit 1 Cyde 9 Page iii Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 List of Figures APLHGRRATED ............................................................................................................................... 4 LHGRRATED for GE14 U0 2 Fuel ............................................................................................... 8 LHGRFACp for All EIS or RPTOOS Conditions ........................................................................ 9 LHGRFACp for TBVOOS Conditions ..................................................................................... 10 LHGRFACp for PLUOOS Conditions ..................................................................................... 11 LHGRFACP for RPTOOS, TBVOOS, and PLUOOS Conditions ............................................ 12 LHGR FAC F................................................................................................................................. 13 MCP RF........................................................................................................................................ 17 MCPRRaed: BOC to MOC Exposure ..................................................................................... 18 MCPRRated: BOC to EOC Exposure ....................................................................................... 19 Kp Multiplier and MCPRp for All Equipment In Service or RPTOOS ...................................... 20 Kp Multiplier and MCPRp for TBVOOS .................................................................................. 21 Kp Multiplier and MCPRp for PLUOOS .................................................................................. 22 Kp Multiplier and MCPRp for RPTOOS, TBVOOS, and PLUOOS ......................................... 23 Browns Ferry Unit 1 Cycle 9 Page iv Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE

[ NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 Revision Log Number I Page Description 1-RO All New document, per NFTP-1 11, Section 3.3, Item Q.

Page v Browns Feny Browns R 9 Cyde Unit 1 Cycle Ferry Unit 9 Page v Core Operating Limits Report, (105% OLTP)

TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801

<Nomenclature 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 EOC End of Cycle EOOS Equipment OOS FFTR Final Feedwater Temperature Reduction FFWTR Final Feedwater Temperature Reduction FHOOS Feedwater Heaters OOS ft Foot: english unit of measure for length 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)

MCPR Minimum CPR Browns Ferry Unit 1 Cyde 9 Page vi Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE I NPG Date: October 15,2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 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 OOS Out-Of-Service OPRM Oscillation Power Range Monitor 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 RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS RPT OOS SDM Shutdown Margin SLMCPR MCPR Safety Limit SLO Single Loop Operation TBV Turbine Bypass Valve TBVIS Turbine Bypass Valve IS TBVOOS Turbine Bypass Valves OOS TIP Transversing In-core Probe TIPOOS Transversing In-core Probe OOS TLO Two Loop Operation TSP Trip Setpoint TSSS Technical Specification Scram Speed TVA Tennessee Valley Authority Browns Ferry Unit 1 Cycle 9 Page vii Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE i NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 References

1. 0000-01 13-6833-SRLR, Revision 0, Supplemental Reload Licensing Report Browns Ferry 1 Reload 8 Cycle 9, Global Nuclear Fuels, Inc., September 2010.
2. 0000-0077-8380-SRLR, Revision 0, Supplemental Reload Licensing Report Browns Ferry 1 Reload 7 Cycle 8, Global Nuclear Fuels, Inc., August 2008.
3. 0000-0044-1520-SRLR, Revision 0, Supplemental Reload Licensing Report Browns Ferry 1 Reload 6 Cycle 7, Global Nuclear Fuels, Inc., January 2007.
4. 0000-0113-6833-FBIR, Revision 0, Fuel Bundle Information Report Browns Ferry I Reload 8 Cycle 9, Global Nuclear Fuels, Inc., September 2010.

Methodoloqy References

5. NEDE-24011-P-A-16, General Electric Standard Application for Reactor Fuel, October 2007.
6. NEDE 724011-P-A-16-US, General Electric Standard Application for Reactor Fuel (Supplement for United States), October 2007.

PRNM Setpoint References

7. Filtered Setpoints - EDE-28-0990 Rev. 3 Supplement E, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL (NUMAC) - Power-Uprate Condition] for Tennessee Valley Authority Browns Ferry Nuclear Plant", October 1997.
8. Unfiltered Setpoints - EDE-28-0990 Rev. 2 Supplement E, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL (NUMAC) - Power-Uprate Condition] for Tennessee Valley Authority Browns Ferry Nuclear Plant", October 1997.
9. GE Letter LB#: 262-97-133, Browns FerryNuclear PlantRod Block Monitor Setpoint Clarification- GE Proprietary Information, September 12, 1997.
10. NEDC-32433P, Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Unit 1, 2, and 3, GE Nuclear Energy, April 1995.

Browns Ferry Unit 1 Cycle 9 Page viii Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 I 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 may be provided, upon final approval, to the NRC.

1.2 Scope This document will discuss the following areas:

> Average Planar Linear Heat Generation Rate (APLHGR) Limit (Technical Specifications 3.2.1 and 3.7.5)

> Linear Heat Generation Rate (LHGR) Limit (Technical Specification 3.2.3, 3.3.4.1, and 3.7.5)

> Minimum Critical Power Ratio Operating Limit (OLMCPR)

(Technical Specifications 3.2.2, 3.3.4.1, and 3.7.5)

> Average Power Range Monitor (APRM) Flow Biased Rod Block Trip Setting (Technical Requirements Manual Section 5.3.1 and Table 3.3.4-1)

> Rod Block Monitor (RBM) Trip Setpoints and Operability (Technical Specification Table 3.3.2.1-1)

> Shutdown Margin (SDM) Limit (Technical Specification 3.1.1) 1.3 Fuel Loading The core will contain all Global Nuclear Fuels, Inc., GE14 fuel. Nuclear fuel types used in the core loading are shown in Table 1.1. The core shuffle and final loading were assessed to determine Reference 1 applicability relative to minor loading changes.

1.4 Acceptability Limits discussed in this document were generated based on NRC approved methodologies per References 5 through 6.

Browns Ferry Unit 1 Cycle 9 Page 1 Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE

[ NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 Table 1.1 Nuclear Fuel Types Nuclear Original Number of Fuel Type Fuel Names Fuel Description Cycle Assemblies (NFT) (Range)

GE 14-P1 ODNAB1 57-NOG-1 OOT-1 50-T6-2889 7 1 4 JLX209-JLX432 GE14-P1ODNAB377-16GZ-1OOT-150-T6-2890 7 37 5 JLX433-JLX528 GE 14-P1 ODNAB402-16GZ-1 OOT-1 50-T6-2891 7 31 6 JLX529-JLX560 GE 14-PI ODNAB350-16GZ-1 00T-1 50-T6-2892 7 20 7 JLX561-JLX592 GE1 4-P1 ODNAB419-16GZ-1 OOT-1 50-T6-2894 7 32 9 JLX613-JLX644 GE1 4-PI ODNAB368-15GZ-1 OOT-1 50-T6-2895 7 32 10 JLX645-JLX716 GE14-P1ODNAB402-19GZ-100T-150-T6-2896 7 24 11 JLX717-JLX740 GE 14-P1 ODNAB377-17GZ-1 OOT-1 50-T6-2897 7 8 13 JLX741-JLX772 GE14-PI ODNAB406-16GZ-1 OOT-1 50-T6-3078 8 48 14 JYE101-JYE148 GE 14-P1 ODNAB406-15GZ-1 OT-1 50-T6-3079 8 63 16 JYE245-JYE308 GE1 4-P1 ODNAB418-16GZ-1 OOT-1 50-T6-3080 8 72 18 JYE357-JYE428 GE 14-P1 ODNAB400-17GZ-1 OOT-1 50-T6-3081 8 96 15 JYE149-JYE244 GE 14-P1 ODNAB417-16GZ-1 OOT-1 50-T6-3082 8 48 17 JYE309-JYE356 GE 14-P1 ODNAB408-16GZ-1 OOT-1 50-T6-3363 9 180 1 JYP101-JYP280 GE1 4-P1 ODNAB412-16GZ-1 OOT-1 50-T6-3364 9 40 2 JYP281-JYP320 GE1 4-P1 ODNAB404-15GZ-1 OOT-1 50-T6-3365 9 16 8 JYP321 -JYP336 GE 14-P1 ODNAB408-17GZ-1 OOT-1 50-T6-3366 9 16 19 JYP337-JYP352 The table identifies the expected fuel type breakdown inanticipation 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 inthis document.

Browns Ferry Unit 1 Cycle 9 Page 2 Core Operating Umits Report, (105% OLTP) TVA-COLR-BFIC9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15,2010 1101 Market Street Chattanooga, TN 37402 EDMS: L32 101015 801 2 APLHGR Limits (Technical Specifications 3.2.1 & 3.7.5)

The APLHGR limit is determined by adjusting the rated power APLHGR limit for off-rated power, off-rated flow, and SLO conditions. The most limiting of these is then used as follows:

APLHGR limit = MIN (APLHGRp, APLHGRF, APLHGRSLO) where:

APLHGRp off-rated power APLHGR limit [APLHGRRATED

  • MAPFACp]

APLHGRF off-rated flow APLHGR limit [APLHGRRATED

  • MAPFACF]

APLHGRSLO SLO APLHGR limit [APLHGRRATED* SLO Multiplier]

2.1 Rated Power and Flow Limit: APLHGRRATED The rated conditions APLHGR, for the different fuel types, are identified in References 1, 2, & 3, and are shown in Figure 2.1.

2.2 Off-Rated Power Dependent Limit: APLHGRp References 1 & 6 for GE14 fuel do not specify a power dependent APLHGR. Therefore, MAPFACp is set to a value of 1.0.

2.3 Off-Rated Flow Dependent Limit: APLHGRF References 1 & 6 for GE14 fuel do not specify a flow dependent APLHGR. Therefore, MAPFACF is set to a value of 1.0.

2.4 Single Loop Operation Limit: APLHGRSLo The single loop operation multiplier is 0.93, per Reference 1.

Browns Ferry Unit 1 Cycle 9 Page 3 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final) r

Nuclear Fuel Engineering - BWRFE i NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 15 12 6

< 6 3

0 0 20 40 60 80 Planar Average Exposure (GWd/MTU)

Planar Avg. Planar Avg. APLHGR Exposure Exposure Limit (GWd/MTU), (GWd/ST) (kW/ft) 0.00 0.00 12.82 21.09 19.13 12.82 63.50 57.61 8.00 70.00 63.50 5.00 Figure 2.1 APLHGRRATED Browns Ferry Unit 1 Cyde 9 Page 4 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE S]NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 2.5 Equipment Out-Of-Service Corrections The limit shown in Figure 2.1 is applicable for operation with all equipment In-Service as well as the following Equipment Out-Of-Service (EOOS) options; including combinations of the options.*

In-Service All equipment In-Service RPTOOS EOC-Recirculation Pump Trip Out-Of-Service TBVOOS Turbine Bypass Valve(s) Out-Of-Service PLUOOS Power Load Unbalance Out-Of-Service FHOOS (or FFWTR) Feedwater Heaters Out-Of-Service or Final Feedwater Temperature Reduction Single Recirculation Loop Operation (SLO) requires the application of the SLO multipliers to the rated APLHGR limits as described previously.

All equipment service conditions assume 1 SRVOOS.

Browns Ferry Unit 1 Cycle 9 Page 5 Core Operating Umits Report, (105% OLTP) TVA-COLR-BFIC9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 3 LHGR Limits (Technical Specification 3.2.3, 3.3.4.1, & 3.7.5)

The LHGR limit is determined by adjusting the rated power LHGR limit for off-rated power and off-rated flow conditions. The most limiting of these is then used as follows:

LHGR limit = MIN (LHGRp, LHGRF) where:

LHGRp off-rated power LHGR limit [LHGRRATED

  • LHGRFACp]

LHGRF off-rated flow LHGR limit [LHGRRATED* LHGRFACF]

LHGRSLO SLO LHGR limit [LHGRRATED

  • SLO Multiplier]

3.1 Rated Power and Flow Limit: LHGRRATED The rated conditions LHGR is identified in Reference 4, and shown in Figure 3.1 for U0 2 fuel.

Separate, concentration dependent limits apply for rods containing Gadolinium; LHGR limits are provided in Reference 4.

3.2 Off-Rated Power Dependent Limit: LHGRp LHGR limits are adjusted for off-rated power conditions using the LHGRFACp multiplier provided in Reference 1. The multiplier is dependent on EOOS conditions. Consequently, the multipliers are shown in Figure 3.2 thru Figure 3.5, for various EOOS conditions/combinations.

3.3 Off-Rated Flow Dependent Limit: LHGRF LHGR limits are adjusted for off-rated flow conditions using the LHGRFACF multiplier provided in Reference 1. There are no EOOS dependencies for the multiplier. The multiplier is shown in Figure 3.6.

3.4 Single Loop Operation Limit: LHGRSLO The single loop operation multiplier is 0.93, per Reference 1.

3.5 Equipment Out-Of-Service Corrections The limit shown in Figure 3.1 is applicable for operation with all equipment In-Service as well as the following Equipment Out-Of-Service (EOOS) options; including combinations of the options.*

In-Service All equipment In-Service RPTOOS EOC-Recirculation Pump Trip Out-Of-Service TBVOOS Turbine Bypass Valve(s) Out-Of-Service All equipment service conditions assume 1SRVOOS.

Browns Ferry Unit 1Cycle 9 Page 6 Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

I

Nuclear Fuel Engineering - BWRFE i NPG Date: October15,2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 PLUOOS Power Load Unbalance Out-Of-Service FHOOS (or FFWTR) Feedwater Heaters Out-Of-Service or Final Feedwater Temperature Reduction SLO Single Loop Operation, One Recirculation Pump Out--Of-Service Off-rated power corrections shown in Figure 3.2 thru Figure 3.5 cover various EOOS scenarios.

The limits have no dependency on FHOOS/FFWTR.

Browns Ferry Unit 1 Cycle 9 Page 7 Core Operating ULmits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15,2010 1101 Market Street Chattanooga, TN 37402 EDMS: L32 101015 801 15 12 9

C,

=

-J 6

3 0

0 20 40 60 80 Pellet Exposure (GWd/MTU)

Pellet Pellet LHGR Exposure Exposure Limit (GWd/MTU) (GWd/ST) (kW/ft) 0.00 0.00 13.40 16.00' 14.51 13.40 55.50 50.35 8.80 63.50 57.61 7.10 70.00 63.50 5.00 Figure 3.1 LHGRRATED for GE14 U0 2 Fuel Browns Ferry Unit 1 Cycle 9 Page 8 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 1.10 1.00 0.90 0.80 C.

0.70

,-J 0.60 0.50 SCore Flow 4 80%

0.40

. ..-- 0 0.30 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Core Power LHGRFACp

(%Rated) 100.0 1.000 50.0 0.739 50.0 0.688 30.0 0.614 Core Flow > 50% Rated 30.0 0.460 25.0 0.428 Core Flow <= 50% Rated 30.0 0.538 25.0 0.533 Figure 3.2 LHGRFACp for All EIS or RPTOOS Conditions (with and without FHOOS)

Browns Ferry Unit 1 Cycle 9 Page 9 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE t

i NPG Date: October 15,2010 1101 Market Street Chattanooga, TN 37402 EDMS: L32 101015 801 1.10 1.00 0.90 0.80 0.70 C.)

-- I 0.60 0.50 0.40 0.30 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Core Power LHGRFACp

(% Rated) _

100.0 1.000 50.0 0.739 50.0 0.688 30.0 0.614 Core Flow > 50% Rated 30.0 0.371 25.0 0.315 Core Flow <= 50% Rated 30.0 0.549 25.0 0.473 Figure 3.3 LHGRFACp for TBVOOS Conditions (with and without FHOOS)

Browns Ferry Unit 1 Cyde 9 Page 10 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1 C9, Revisbn 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 1.10 1.00 0.90 0.80 I,

0.70 nJ 0.60 0.50 0.40' 0.30 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Core Power LHGRFACp

(%Rated) 100.0 1.000 70.0 0.843 60.0 0.725 30.0 0.614 Core Flow > 50% Rated 30.0 0.460 25.0 0.428 Core Flow <= 50% Rated

30. 0 .[ 0.538 25.0 0.533 Figure 3.4 LHGRFACp for PLUOOS Conditions (with and without FHOOS)

Browns Ferry Unit 1 Cycle 9 Page 11 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE i NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 1.10 1.00 0.90 0.80 0.

  • 0.70

"-J 0.60 0.50 0.40 0.30 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Core Power LHGRFACp

(%Rated) 100.0 1.000 70.0 0.843 60.0 0.725 30.0 0.614 Core Flow > 50% Rated 30.0 0.371 25.0 0.315 Core Flow <= 50% Rated 30.0 " 0.54 9 25.0 0.473 Figure 3.5 LHGRFACp for RPTOOS, TBVOOS, and PLUOOS Conditions (with and without FHOOS)

Browns Ferry Unit 1 Cycle 9 Page 12 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE i NPG Date: October 15, 2010 1101 Market Street Chattanooga, TN 37402 EDMS: L32 101015 801 1.10 1.00 0.90 U.

U-

_1 0.80 0.70 0.60 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Core Flow LHGRFACF

(% Rated) 30.0 0.66 80.3 1 110.0 1 Figure 3.6 LHGRFACF (Values bound all EOOS conditions)

(110.0% maximum core flow line is used to support 105% rated flow operation,ICF)

Browns Ferry Unit 1 Cycle 9 Page 13 Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 4 OLMCPR Limits (Technical Specification 3.2.2, 3.3.4.1, & 3.7.5)

OLMCPR is calculated to be the most limiting of the flow or power dependent values OLMCPR limit = MAX ( MCPRF, MCPRp )

where:

MCPRp off-rated power MCPR limit [MCPRRATED

  • KpJ MCPRF off-rated flow MCPR limit MCPRSLO SLO MCPR limit [MCPRp + SLO Adder]

4.1 Rated Power and Flow Limit: MCPRRATED The rated conditions MCPR is identified in Reference 1. The rated power and flow limits for various cycle exposure windows, and EOOS scenarios, are shown in Figure 4.2 & Figure 4.3.

OLMCPR is calculated to be the most limiting of the flow or power dependent values.

4.1.1 Scram Timing Dependence The MCPRRATED has a scram timing dependence which is assessed after control blade timing shortly after startup, and is discussed as follows:

T = 0.0 or, Tave TB r

whichever is greater TA- TB where: TA = 1.096 sec (analytical Option A scram time limit based on dropout time for notch position 36) n~

T ave n

TB -t I+1.65

  • cy* N]ý Browns Ferry Unit 1 Cycle 9 Page 14 Core Operating Ulmits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 where: = 0.830 sec (mean scram time used in transient analysis based on dropout time for notch position 36)

(Y= 0.019 sec (standard deviation of pt)

N= Total number of active rods measured in Technical Specification Surveillance Requirement SR 3.1.4.1 n = Number of surveillance rod tests performed to date in cycle 1= Scram time (dropout time) from fully withdrawn to notch position 36 for the ith rod For reactor startup, Option A limits (T=1.0) shall be used prior to the determination of T in accordance with SR 3.1.4.1.

4.1.2 Equipment Out-Of-Service (EOOS) Options All equipment service conditions support 1 SRVOOS. EOOS options, including combinations, covered by MCPRp limits are given by the following:

In-Service All equipment In-Service RPTOOS EOC-Recirculation Pump Trip Out-Of-Service TBVOOS Turbine Bypass Valve(s) Out-Of-Service PLUOOS Power Load Unbalance Out-Of-Service FHOOS (or FFWTR) Feedwater Heaters Out-Of-Service (or Final Feedwater Temperature Reduction) 4.1.3 Exposure Dependent Limits Exposures are tracked on a cycle exposure basis. Higher exposure limits are always more limiting, and may be used for any cycle exposure up to the ending exposure. Cycle Exposure Ranges are defined as follows:

BOC to MOC: where MOC corresponds to EOR* - 3208 MWd/MTU (2910 MWd/ST).

BOC to EOC EOC exposure includes cycle extension options such as final feedwater reduction (FFTR) and power coastdown.

EOR isdefined as the end of rated power capability for rated core flow and nominal feedwater temperature conditions.

Browns Ferry Unit 1Cycle 9 Page 15 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

/1 Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 4.2 Flow Dependent MCPR Limit: MCPRF MCPRF limits are dependent upon core flow (% of Rated), and the max core flow limit, (Rated or Increased Core Flow, ICF). MCPRF limits are shown in Figure 4.1, per Reference 1. Limits are valid for all EOOS combinations. No adjustment is required for SLO conditions.

4.3 Single Loop Operation Limit: MCPRSLO The single loop operation adder is 0.02, per Reference 1.

4.4 Power Dependent MCPR Limit: MCPRp MCPRp limits are dependent upon core power level (% of Rated) and EOOS conditions. Kp Multipliers and/or MCPRp values are provided in Figure 4.4 thru Figure 4.7. Determination of power dependent MCPR is differentiated relative to Pbypass (30% Rated Power) as follows:

P > 30% (above Pbypass): MCPRP = [MCPRRATED* Kp]

P < 30% (below Pbypass): MCPRp = MCPRp Browns Ferry Unit 1 Cycle 9 Page 16 Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 2.00 1.80 1.60 Li.

1.40 1.20 1.00 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Core Flow MCPRF

(% Rated) 30.0 1.55 71.9 1.30 110.0 1.30 Figure 4.1 MCPRF (Values bound all EOOS, and SLO conditions)

(110.0% maximum core flow line is used to support 105% rated flow operation,ICF)

Browns Ferry Unit 1 Cycle 9 Page 17 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 1.60 1.55 1.50 1.45 a.

0o 1.40 1.35 1.30 0.00 0.20 0.40 0.60 0.80 1.00 Tau Option A Option B Out-of-Service Condition Tau = 1.0 Tau = 0.0 All Equipment In-Service 1.41 1.38 RPTOOS 1.52 1.41 TBVOOS 1.47 1.44 PLUOOS 1.52 1.41 Combined RPTOOS, TBVOOS, & PLUOOS 1.57 1.46 Figure 4.2 MCPRRated : BOC to MOC Exposure (Values support ISRVOOS &FHOOS/FFTRconditions)

Browns Ferry Unit 1 Cycle 9 Page 18 Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 1.75 1.70 Combined RPTOOS, TBVOOS, &PLUOOS .I 1.65 1.60 a, TRPTOOS C.)1.55 1.50 All EquPLUOOS 1.45

  • All EquipmentlIn-Service 1.40 1.35 0.00 0.20 0.40 0.60 0.80 1.00 Tau Option A Option B Out-of-Service Condition Tau = 1.0 Tau = 0.0 All Equipment In-Service 1.46 1.43 RPTOOS 1.62 1.45 TBVOOS 1.51 1.48 PLUOOS 1.62 1.45 Combined RPTOOS, 'TBVOOS, & PLUOOS 1.69 '1.52 Figure 4.3 MCPRRated: BOC to EOC Exposure (Values support ISRVOOS &FHOOS/FFTR conditions)

Browns Ferry Unit 1 Cycle 9 Page 19 Core Operating Umnits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE i NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 5.00 4.50 4.00 3.50 3.00 C_o2.50 MCPR for Core Flow >50%

  • . ~~MCIR fo Cor r u 2.00 1.50 1.00 Kp Multiplier 0.50 0.00 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Core Power Kp

(% Rated) -

100.0 1.000 60.0 1.150 50.0 1.237 50.0 1.384 30.0 1.552 Core Flow > 50% Rated MCPRp 30.0 2.640 25.0 2.820 Core Flow <= 50% Rated MCPRp 30.0 2.150 25.0 2.200 Figure 4.4 Kp Multiplier and MCPRp for All Equipment In Service or RPTOOS (Values support ISRVOOS & FHOOS/FFTRconditions)

Browns Ferry Unit 1 Cyde 9 Page 20 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 5.00 4.50 4.00

\MCPRp for Core Flow >50%

3.50 3.00 lk CPRpfor Co r Flow y-O%

2.50 2.00 1.50 1.00 Kp Multiplier 0.50 0.00 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Core Power Kp

(% Rated) _

100.0 1.000 60.0 1.150 50.0 1.237 50.0 1.384 30.0 1.552 Core Flow > 50% Rated MCPRp 30.0 3.550 25.0 4.290 Core Flow <= 50% Rated MCPRp 30.0 2.630 25.0 3.060 Figure 4.5 Kp Multiplier and MCPRp for TBVOOS (Values support 1SRVOOS &FHOOS/FFTRconditions)

Browns Ferry Unit 1 Cyde 9 Page 21 Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Sbreet Chattanooga, TN 37402 -- EDMS: L32 101015 801 5.00 4.50 4.00 3.50 3.00 (L &4S"

  • MCPRp for Core Flow p50%

L) 2.50

-MCPRforCore Flow <= 80%

1.50 ="

  • 1.00 Kp Multiplier 0.50 0.00 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Core Power Kp I (% Rated) _

100.0 1.000 70.0 1.160 60.0 1.300 30.0 1.552 Core Flow > 50% Rated MCPRp 30.0 2.640 25.0 2.820 Core Flow <= 50% Rated MCPRp 30.0 2.150 25.0 2.200 Figure 4.6 Kp Multiplier and MCPRp for PLUOOS (Values support ISRVOOS & FHOOS/FFTRconditions)

Browns Ferry Unit 1 Cycle 9 Page 22 Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 5.00 4.50 4.00 MCPRP for Core Flow >50%

3.50 3.00 0t o 2.50

\ MCPRp for Coro Flow - 80%

2.00 1.50 1.00 Kp Multiplier 0.50 0.00 20 30 40 50 60 70 80 90 100 110 Core Power (% Rated)

Core Power Kp

(% Rated) 100.0 1.000 70.0 1.160 60.0 1.300 30.0 1.552 Core Flow > 50% Rated MCPRp F

30.0 3.550 25.0 4.290 Core Flow <= t50% Rated MCPRp 30.0 2.630 25.0 3.060 Figure 4.7 Kp Multiplier and MCPRp for RPTOOS, TBVOOS, and PLUOOS (Values support ISRVOOS & FHOOS/FFTRconditions)

Page 23 Ferry Un~

Browns Feny Cycle 9 1 Cyde Unit 1 9 Page 23 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1 C9, Rek4sion 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street Chattanooga, TN 37402 EDMS: L32 101015 801 5 APRM Flow Biased Rod Block Trip Settings (Technical Requirements Manual Section 5.3.1 and Table 3.3.4-1)

The APRM rod block trip setting is based upon References 7 & 8, and is defined by the following:

SRB _ (0.66(W-AW) + 61%) Allowable Value SRB < (0.66(W-AW) + 59%) Nominal Trip Setpoint (NTSP) where:

SRB = Rod Block setting in percent of rated thermal power (3458 MWt)

W = Loop recirculation flow rate in percent of rated AW = Difference between two-loop and single-loop effective recirculation flow at the same core flow (AW=0.0 for two-loop operation)

The APRM rod block trip setting is clamped at a maximum allowable value of 115%

(corresponding to a NTSP of 113%).

Browns Ferry Unit 1 Cycle 9 Page 24 Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE SNPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 6 Rod Block Monitor (RBM) Trip Setpoints and Operability (Technical Specification Table 3.3.2.1-1)

The RBM trip setpoints and applicable power ranges, based on References 7 & 8, are shown in Table 6.1. Setpoints are based on an HTSP, unfiltered analytical limit of 117%. Unfiltered setpoints are consistent with a nominal RBM filter setting of 0.0 seconds; filtered setpoints are consistent with a nominal RBM filter setting less than 0.5 seconds.

Table 6.1 Analytical RBM Trip Setpoints*

Allowable Nominal Trip RBM Value Setpoint Trip Setpoint (AV) (NTSP)

LPSP 27% 25%

IPSP 62% 60%

HPSP 82% 80%

LTSP - unfiltered 124.7% 123.0%

- filtered 123.5% 121.8%

ITSP - unfiltered 119.7% 118.0%

- filtered 118.7% 117.0%

HTSP - unfiltered 114.7% 113.0%

- filtered 113.7% 112.0%

DTSP 90% 92%

Generic CRWE based OLMCPR values were reported and verified per References 7, 8, 9, and

10. However, Reference 10 generic values were developed assuming a SLMCPR < 1.07.

Consequently, cycle specific CRWE analyses were performed to support the current SLMCPR; values are reported in Reference 1. Cycle specific analysis results indicate the SLMCPR remains protected for RBM inoperable conditions (i.e., unblocked). RBM setpoints in Technical Specification Table 3.3.2.1-1 are applicable as shown in Table 6.2.

Table 6.2 RBM Setpoint Applicability Thermal Power Applicable Notes from

(% Rated) MCPRt Table 3.3.2.1-1 Comment

> 27% and < 90% < 1.70 (a), (b), (f), (h) two loop operation

< 1.72 (a), (b), (f), (h) single loop operation

->90% < 1.40 (g) two loop operationt Values are considered maximums. Using lower values, due to RBM system hardware/software limitations, is conservative, and acceptable.

t -MCPR values shown correspond with, (support), SLMPCR values identified inReference 1.

Greater than 90% rated power is not attainable insingle loop operation.

Browns Ferry Unit 1 Cycle 9 Page 25 Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE i NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 Table 6.3 Control Rod Withdrawal Error Results RBM CRWE Setpoint OLMCPR Unfiltered

'107 1.31 111 1.31 114 1.32 117 1.38 Results, compared against the base case OLMCPR results of Reference 1, indicate SLMCPR remains protected for RBM inoperable conditions (i.e., unblocked).

Browns Ferry Unit 1 Cycle 9 Page 26 Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1 C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE

~NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 7 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 Page 27 Bmwns Ferry Unit Browns Ferry R 9 Unit 1 Cyde Cycle 9 Page 27 Core Operating Limits Report, (1105% OLTP)

TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE

[ NPG Date: October 15,2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 Appendix A: Thermal-Hydraulic Stability Browns Ferry Unit 1 Cyde 9 Page 28 Core Operating Limits Report, (105% OLTP) TVA-COLR-BF1 C9, Revisin 0 (Final)

fNuclear Fuel Engineering - BWRFE NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 RPS Instrumentation (Technical Specification 3.3.1.1)

Technical Specification Section 3.3.1.1, LCO 3.3.1.1 states:

The RPS instrumentationfor each Function in Table 3.3.1.1-1 shall be OPERABLE.

Table 3.3.1.1-1, Function 2f, identifies the OPRM upscale function. This function must be operable in conjunction with the following surveillance requirements:

SR 3.3.1.1.1 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 SR 3.3.1.1.17

Background

Browns Ferry uses the Option III stability Detect and Suppress solution as part of the PRNM system. The Option Ill system is based upon combining groups of local LPRM's into cells known as OPRM's. The OPRM's generate a combined LPRM signal that is examined for the characteristics of a reactor instability event, and if detected, a reactor trip is generated.

The PBDA is the licensing basis portion of the Option III system, requiring a cycle-specific calculation to determine the amplitude setpoint to generate a reactor trip in time to protect the fuel from exceeding the SLMCPR.

The OPRM Upscale Trip function is required to be operable when the plant is in a region of power-flow operation where actual thermal-hydraulic oscillations might occur (T.S. enabled region ,

greaterthan 25% rated thermalpower and loss than 60% reclrculation drive flow).

Setpoints Instrument setpoints are established such that the reactor will be tripped before an oscillation can grow to the point where the SLMCPR is exceeded. An Option III stability analysis is performed for each reload core to determine allowable OLMCPR's as a function of OPRM setpoint. Analyses consider both steady state startup operation, and the case of a two recirculation pump trip from rated power.

The resulting stability based OLMCPR's are reported in Reference 1. The OPRM setpoint (sometimes referred to as the Amplitude Trip, Sp) is selected such that required margin to the SLMCPR is provided without stability being a limiting event. Analyses are based on cycle specific DIVOM analyses. The calculated OLMCPR's are shown.in Table A.1. Review of results, relative to the base case operation shown in Figure 4.2 indicates an OPRM setpoint of 1.15 can be supported. Extrapolation beyond a setpoint of 1.15 is not allowed.

Browns Ferry Unit 1 Cycle 9 Page 29 Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

Nuclear Fuel Engineering - BWRFE

[ NPG Date: October 15, 2010 1101 Market Street, Chattanooga, TN 37402 EDMS: L32 101015 801 Table A.1 OPRM Setpoints OPRM OLMCPR OLMCPR Setpoint (SS) (2PT) 1.05 1.177 1.122 1.06 1.195 1.139 1.07 1.214 1.157 1.08 1.233 1.176 1.09 1.253 1.195 1.10 1.273 1.214 1.11 1.294 1.233 1.12 1.315 1.253 1.13 1.336 1.274 1.14 1.358 1.295 1.15 1.382 1.317 Backup Stability Should the Option III system be declared inoperable, alternate methods/procedures (i.e.,

stability ICA's) are incorporated restricting plant operation in the high power, low core flow region of the power/flow map. ICA's contain specific operator actions, providing clear instructions (depending upon the plant type) for operator response to a reactor inadvertently (or under controlled conditions) entering any of the defined regions. ICA's provide appropriate guidance to reduce the likelihood of hydraulic instability, and enhance early detection in the very unlikely event a stability threshold is exceeded in spite of the ICA guidelines.

In July 2002, GE recommended the original ICAs, established generically in 1994, be re-evaluated to assure adequate conservatism, given the trend to higher energy cores and more aggressive fuel management strategies. The recommended replacement regions and the associated calculational procedure are referred to as BSP, and need to be confirmed on a plant/cycle specific basis. The vendor has performed an ICA/BSP confirmation calculation using NRC approved methods.

Based upon the above discussion, appropriate stability analyses and evaluations have been performed to satisfy licensing requirements.

Browns Ferry Unit 1 Cyde 9 Page 30 Core Operating Umits Report, (105% OLTP) TVA-COLR-BF1C9, Revision 0 (Final)

Retrieved from "https://kanterella.com/w/index.php?title=ML103260116&oldid=2553456"