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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML18039A7671999-04-0808 April 1999
Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr.
ML18039A7361999-03-11011 March 1999
Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr.
ML18039A6941999-02-0303 February 1999
Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr.
ML18039A6931999-02-0303 February 1999
Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 Colr.
ML18039A5621998-09-17017 September 1998
Rev 0 to TVA-COLR-BF3C9, Bfnp Unit 3,Cycle 9 Colr.
ML18039A4831998-07-0909 July 1998
Rev 3 to Unit 3 Cycle 8 Colr.
ML18039A4821998-07-0909 July 1998
Rev 2 to Unit 2 Cycle 10 Colr.
ML18039A4191998-05-28028 May 1998
Rev 2 to TVA-COLR-BF3C8, BFN Unit 3,Cycle 8 Colr.
ML18039A4171998-05-28028 May 1998
Rev 1 to TVA-COLR-BF2C10, BFN Unit 2,Cycle 10 Colr.
ML18039A3431998-04-17017 April 1998
Rev 1 to COLR Cycle 8 for Browns Ferry Nuclear Plant Unit 3.
ML18038B9731997-09-26026 September 1997
Cycle 10 Colr.
ML18038B8311997-02-0606 February 1997
Rev 0 to Colr,Bfn Unit 3,Cycle 8.
ML20113B1971996-06-0606 June 1996
Bfnp Unit 2,Cycle 9 Colr
ML20132B7691996-05-31031 May 1996
Supplemental Reload Licensing Rept for Brown Ferry Nuclear Plant Unit 2,Reload 8,Cycle 9
ML18038B6471996-03-14014 March 1996
Rev 0 to Browns Ferry Nuclear Plant Unit 2,Cycle 9 Colr.
ML20093G8471995-09-22022 September 1995
Rev 0 to Brown Ferry Nuclear Plant Unit 3,COLR
ML18038B3961995-07-27027 July 1995
Cycle 8,COLR.
ML18038B2661995-03-24024 March 1995
Rev 1 to Bfnp Unit 2,Cycle 8 Colr.
ML18038A9851994-10-0606 October 1994
Cycle 8,Core Operating Limits Rept.
ML18037A8271994-03-14014 March 1994
Rev 2 to Browns Ferry Nuclear Plant Unit 2,Cycle 7.
ML20044G2101993-05-0707 May 1993
Rev 1 to TVA-COLR-BF2C7, Browns Ferry Nuclear Plant Unit 2, Cycle 7 Colr.
ML18036A8201992-08-20020 August 1992
Draft Rev 0 to TVA-COLR-000, Browns Ferry Nuclear Plant Unit 2,Cycle 6 Colr.
ML18033A3601988-07-31031 July 1988
Rev 2 to Reload Licensing Rept.
ML18030A9801985-04-30030 April 1985
Rev 1 to Browns Ferry Nuclear Plant Reload Licensing Rept, Unit 2,Cycle 6.
ML20095G8591984-07-31031 July 1984
Reload Licensing Rept for Browns Ferry Unit 2,Cycle 6. Determination of No Significant Hazards Encl
ML20077K9291983-05-31031 May 1983
Rev 0 to Supplemental Reload Licensing Submittal for Browns Ferry,Unit 1,Reload 5
ML20069J1601982-07-31031 July 1982
Supplemental Reload Licensing Submittal for Browns Ferry Nuclear Plant,Cycle 5,Unit 2,Reload 4
ML20039B7081981-11-30030 November 1981
Suppl Reload Licensing Submittal for Browns Ferry,Reload 4 (Cycle 5).
ML20126J6111981-03-31031 March 1981
Supplemental Reload Licensing Submittal for Browns Ferry Unit 1 Reload 4(Cycle 5)
ML19320C6891980-06-30030 June 1980
Supplemental Reload Licensing Submittal for Browns Ferry Nuclear Power Station,Unit 2,Reload 3.
ML19209B7651979-08-31031 August 1979
Supplemental Reload Licensing Submittal for Reload 3.
ML19242B4411979-06-30030 June 1979
Supplemental Reload Licensing Submittal for Unit 3 Reload 2.
ML18024A6791979-01-31031 January 1979
Suppl Reload Licensing Submittal Presented as Justification for Proposed Amend Changes
ML20062E1961978-11-30030 November 1978
Suppl Reload Licensing Submittal for Browns Ferry Unit 1, Reload 2, Revision 1
1999-04-08
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18039A9041999-10-15015 October 1999
LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily
ML18039A8981999-10-14014 October 1999
LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug
ML18039A8951999-10-0808 October 1999
LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions
ML18039A8751999-09-30030 September 1999
LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr
ML20217F9671999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With
ML20212E6341999-09-23023 September 1999
Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension
ML20212D3831999-09-20020 September 1999
Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV
ML20212B8561999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With
ML18039A8821999-08-31031 August 1999
Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept.
ML18039A8391999-08-0606 August 1999
BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts.
ML20210N1221999-08-0202 August 1999
Safety Evaluation Accepting Licensee Request for Relief from ASME B&PV Code,Section XI Requirements.Request 3-ISI-7, Pertains to Second 10-year Interval ISI for Plant,Unit 3
ML20210R0931999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With
ML18039A8201999-07-26026 July 1999
LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position
ML18039A8171999-07-20020 July 1999
LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr
ML18039A8161999-07-19019 July 1999
LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr
ML20209J0771999-07-16016 July 1999
Safety Evaluation Concluding That Licensee Provided Adequate Information to Resolve ampacity-related Points of Concern Raised in GL 92-08 for BFN & That No Outstanding Issues Re GL 92-08 Ampacity Issues for Browns Ferry NPP Exist
ML18039A8121999-07-12012 July 1999
LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr
ML20209H4381999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With
ML18039A8101999-06-28028 June 1999
LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset
ML20196F8811999-06-23023 June 1999
Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves
ML18039A8071999-06-14014 June 1999
LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram
ML18039A8021999-06-14014 June 1999
LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr
ML18039A8011999-06-14014 June 1999
LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr
ML20196B8051999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With
ML18039A7791999-05-0606 May 1999
LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened
ML18039A7761999-04-30030 April 1999
Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3.
ML20206R0731999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Bfnp.With
ML18039A7561999-04-23023 April 1999
Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal.
ML18039A7671999-04-0808 April 1999
Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr.
ML18039A7461999-04-0707 April 1999
LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable
ML20205N8341999-04-0101 April 1999
Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified
ML20205F9341999-04-0101 April 1999
Safety Evaluation Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST Testing,Valve Program for Plant,Units 1,2 & 3
ML20205T5441999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Bfnp.With
ML20205S0601999-03-31031 March 1999
Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331
ML20205S0661999-03-31031 March 1999
Rept on Status of Public Petitions Under 10CFR2.206 with No Status Change from Previous Update,990331, Atlas Corp
ML18039A7361999-03-11011 March 1999
Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr.
ML20204C7891999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With
ML18039A6951999-02-19019 February 1999
LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr
ML18039A6871999-02-12012 February 1999
LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr
ML18039A6931999-02-0303 February 1999
Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 Colr.
ML18039A6941999-02-0303 February 1999
Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr.
ML18039A6671998-12-31031 December 1998
LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr
ML18039A6661998-12-31031 December 1998
Ro:On 981215,HRPCRM 2-RM-90-273C Was Declared Inoperable. Caused by Downscale Indication.Containment RM Will Be Utilized as Planned Alternate Method of Monitoring Until Hrpcrm 2-RM-90-273C Can Be Returned to Operable Status
ML20199K8951998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With
ML20199F2721998-12-31031 December 1998
ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation
ML18039A6471998-12-15015 December 1998
LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor
ML18039A6371998-12-0707 December 1998
LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr
ML20199F2791998-12-0303 December 1998
Bfnp Unit 3 Cycle 8 ASME Section XI NIS-2 Data Rept
ML20198D9621998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Bfn,Units 1,2 & 3. with
ML18039A6071998-11-12012 November 1998
LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr
1999-09-30
[Table view] |
Text
TVA-CPLR-BF2CS Revision 1, Psge 1 Browns Ferry Nuclear Plant Unit 2, Cycle 8 CORE OPERATING LIMITS REPORT (COLR)TENNESSEE VALLEY AUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By: Date:~S<&Kenneth.Welch, Engineering'Specialist BWR Fuel Engineering Verified By: A an L.Bruce, Nuclear Engineer BWR Fuel Engineering Date: 3 l>'I4 Approved By: T.A.Keys, anager BWR Fuel Engineering Reviewed By: Date: 5 Zt Reactor Engineering Sup is r Reviewed By: PO C Chairman Date: ,cy5050>p>
050002bp q5pq24 pDR AQQCK o pDR P' (j'l TVA Nuclear F Core Operating Limits Report TVA-COLR-BF2CS Revision 1, Page 2 Revision Log~Revi i n Date 0 10/6/94 Desecri tion Initial Release Affec ed P Change APRM flow biased rod block setpoint;incorporate changes due to Tech Spec Amendment no.232.5,6
TVA Nuclear Ft Core Operating Limits Report TVA-COLR-BF2C8 Revision 1, Page 3 1.INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 2, Cycle 8 is prepared in accordance with the requirements of Browns Ferry Technical Specification 6.9.1.7.The core operating limits presented here were developed using NRC-approved methods (References 1 and 2).Results from the reload analyses for Browns Ferry Unit 2, Cycle 8 are documented in Reference 3.The cycle 8 loading includes four Westinghouse QUAD+demonstration assemblies.
The locations of these assemblies satisfy the criteria specified in References 4 and 5.Evaluations performed by Westinghouse (Reference 5)show that the results of licensing analyses for the lead PSxSR fuel assembly bound those for the QUAD+demonstration assemblies.
Cycle specific analyses confirm this conclusion.
The following core operating limits are included in this report: a.Average Planar Linear Heat Generation Rate (APLHGR)Limit (Technical Specification 3.5.1)b.Linear Heat Generation Rate (LHGR)Limit (Technical Specification 3.5.J)c.Minimum Critical Power Ratio Operating Limit (OLMCPR)(Technical Specification 3.5.K/4.5.K) d.APRM Flow Biased Rod Block Trip Setting (Technical Specification 2.1.A.l.c, Table 3.2.C, and Specification 3.5.L)e.RBM Upscale (Flow Bias)Trip Setting and Clipped Value (Technical Specification Table 3.2.C)2.APLHGR LIMIT (TECHNICAL SPECIFICATION 3.5.1)The APLHGR limit for each type of fuel as a function of exposure is shown in Tables 1-7.The APLHGR limits for the GE9B bundles (GESXSNB)are for the most limiting lattice at each exposure point.The specific values for each lattice are given in Reference 6.
TVA Nuclear F Core Operating Limits Report TVA-COLR-BF2C8 Revision 1, Page 4 3.LHGR LIMIT (TECHNICAL SPECIFICATION 3.5 J)The LHGR limit for unit 2 cycle 8 is fuel type dependent, as shown below:~FI~T~PSX8R/BPSXSR/QUAD+
GE8X8NB LH R Limi 13.4 kw/ft 14.4 kw/ft a.OLMCPR (TECHNICAL SPECIFICATION 3.5.K/4.5.K) whichever is greater ZA ZB a.The OLMCPR is equal to the fuel type and exposure dependent MCPR limit at rated flow and rated power shown in Figures 1-2 multiplied by the Kf shown in Figure 3, where;Zow ZB Z=00 or Z-Zi=0.90 sec (Specification 3.3.C.1 scram time limit to 20%insertion from fully withdrawn)i Zi=0.710+1.65-(0.053)N 2 n n g Zi Zave n where;n=Number of surveillance rod tests performed to date in cycle (including BOC test).Zi=Scram time to 20%insertion from fully withdrawn of the i fod N=Total number of active rods measured in Specification 4.3.C.1 at BOC b.For the performance of Surveillance Requirement 4,5.K.2.a (prior to initial scram time measurements for the cycle),
TVA Nuclear F Core Operating limits Report TVA-COLR-BF2C8 Revision 1 Page 5 c.For the performance of Surveillance Requirement 4.5.K.2.b,'6 shall be determined in accordance with 4.a above.5.APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL SPECIFICATION 2.1.A.1.c, TABLE 3.2.C, AND SPECIFICATION 3.5.L)The APRM Rod Block trip setting shall be: SRB S (0.58W+57%)where: SRB=Rod Block setting in percent of rated thermal power (3293 MWt)W=Loop recirculation fiow rate in percent of rated Note: Under certain conditions, the APRM Rod Block setting must be adjusted by FRP/CMFLPD.
See Technical Specification 3.5.L 6.RBM UPSCALE (FLOW BIAS)TRIP SETTING AND CLIPPED VALUE (TECHNICAL SPECIFICATION TABLE 3.2.C)The RBM Upscale trip setting shall be: 5 (0.66W+43%)where: Trip level setting is in percent of rated thermal power (3293 MWt)W=Loop recirculation fiow rate in percent of rated RBM upscale flow-biased setpoint clipped at 109 percent rated reactor power.
TVA Nuclear F Core Operating Limits Report TVA-COLR-BF2CS Revision 1 Page 6 7.REFEMPlCKS 1.NEDE-24011-P-A-10,"General Electric Standard Application for Reactor Fuel", February 1991.2.NEDE-24011-P-A-10-US,"General Electric Standard Application for Reactor Fuel", March 1991.3.24A5153, Rev.0,"Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 7 Cycle 8," September 1994.4.Safety Evaluation by the office of Nuclear Reactor Regulation Supporting Amendment No.125 to Facility Operating License No.DPR-52, Tennessee Valley Authority, Browns Ferry Nuclear Power Plant, Unit 2, Docket No.50-260.5.WCAP-10507 dated March 1984,"QUAD+Demonstration Assembly Report," Westinghouse Electric Corportion.
6.24A5153AA, Rev.0,"Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 2 Reload 7 Cycle 8", September 1994.7.Safety Evaluation by the office of Nuclear Reactor Regulation Supporting Amendment No.232 to Facility Operating License No.DPR-52, Tennessee Valley Authority, Browns Ferry Nuclear Power Plant, Unit 2, Docket No.50-260.
TVA Nuclear Core Operating L>mits Report TVA-COLR-BF2CS Revision 1, Page 7 Tab1l: 1 APLHGR Limits for Bundle Type GE9B-P8DWB319-9GZ (GE8X8NB)Most Limiting Lattice for Each Exposure Point Average Planar Exposure{QW~D/T}0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 12.5 15.0 20.0 25.0 35.0 45.0 51.20 APLHGR Limit~kw ft 11.64 11.68 11.77 11.88 12.01 12.12 12.22 12.32 12.49 12.65 12.77 12.86 12.86 12.62 12.06 11.47 10.41'.81 5.91
TVA Nuclear Core Operating Limits Report TVA-COLR-BF2CS Revision 1, Page 8 Table 2 APLHGR Limits'for Bundle Type GE9B-P8DWB325-10GZ (GE8X8NB)Most Limiting Lattice for Each Exposure Point Average PIanar Exposure++AT}0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 12.5 15.0 20.0 25.0 35.0 45.0 50.27 APLHGR Limit~kwf-10.97 11.00 11.11 11.31 11.54 11.79 11.97 12.10 12.23 12.35 12.46 12.58 12.58 12.35 11.86 11.33 10.12 8.60 5.92
TVA Nuclear F Core Operating Limits Report TVA-COLR-BF2CS Revision 1, Page 9 Table 3 APLHGR Limits for Bundle Type GE9B-P8DWB326-7GZ (GE8X8NB)Most Limiting Lattice for Each Exposure Point Average Planar Exposure$QW~D~0.'0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 12.5 15.0 20.0 25.0 35.0 45.0 50.5 51.4 APLHGR Limit~f 11.45 11.47 11.55 11.70 11.87 12.01 12.13 12.22 12.31 12.41 12.51 12.63 12.64 12.41 11.91 11.35 10.15 8.72 5.93 5.87' 0
TVA Nuclear Fu Core Operating L ts Report TVA-COLR-BF2CS Revision 1, Page 10 Table 4 APLHGR Limits for Bundle Type BP8DRB301L (BP8X8R)Average Planar Exposure K~SR 0.0 0.2 1.0 2.0 3.0 40 5.0 6.0 7.0 8.0 9.0 10.0 12.5 15.0 20.0 25.0 35.0 43.5 APLHGR Limit~kw f 11.32 11.33 11.40 11.50 11.61 11.73 11.86 11.93 11.98 12.03 12.11 12.19 12.34 12.47 12.58 12.03 10.82 9.17 TVA Nuclear Fu Core Operating L Report TVA-COLR-BF2C8 Revision 1, Page ll Table 5'PLHGR Limits for Bundle Type BP8DRB299 (BP8X8R)Average Planar Exposure gQWD~0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 12.5 15.0 20.0 25.0 35.0 42.1 APLHGR Limit~f 10.71 10.75 10.86 11.01 11.19 11.35 11.47 11.62 11.78 11.95 12.09 12.20 12.37 12.47 12.37 11.77'0.65 9.36 TVA Nuclear F Core Operating L>mits Report TVA-COLR-BF2C8 Revision 1, Page 12 Table 6 APLHGR Limits for Bundle Type P8DRB284L and Westinghouse QUAD+LTAs (PSX8R)Average Planar Exposure{Q~&5K 0.2 1.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 APLHGR Limit~f 11.2 11.3 11.8 12.0 12.0 11.8 11.2 10.8 10.2 9.5 8.8 TVA Nuclear Fu Core Operating LiMnts Report TVA-COLR-BF2CS Revision 1, Page 13 Table 7 APLHGR Limits for Bundle Type P8DRB265H (P8X8R)Average Planar Exposure t'(~WD$T}0.2 1.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 APLHGR Limit~kw f 11.5 11.6 11.9 12.1 12.1 11.9 11.3 10.7 10.2 9.6 TVA Nuclear Fu~Core Operating Liats Report TVA-COLR-BF2CB Revision 1, Page 14 Figure 1 MCPR Operating Limit for PBXBR/BPBXBR/QUAD+
1.33 1.32 1.31 1.30'E 1.29 g-1.28 1.27 1.26 1.25 1.24 1.23 (EOCS-3080) to EOCS BOCS to (EOCS-3080) 0.0 0.1 OE2 OE3 0.4 0.5 OE6 0.7 0.8 OE9 1.0 Option B Option A E~ERR BOC8 to (EOC8-3080 MWD/ST)(EOC8-3080 MWD/ST)to EOC8 tion A Tau=i 0 1.26*1.30 0 tion B Tau=0.0 1.25 1.27*Use this value at BOC8 prior to performing scram time testing.
TVA Nuclear Fu Core Operating Liats Report TVA-COLR-BF2CS Revision 1, Page 1S E Figure 2 MCPR Operating Limit for GESXSNB It 1.33 1.32 1.31 1.3 g 1.29 g 128 1.27 1.26 BO CS-30&0)toE OCS-3 CS to(E OCS 0&0)1.25 1.24 1.23 0 0.'1 OE2 OE3 OA OE5 OE6 0.7 OE8 0.9 1 Option B Option A~E BOC8 to (EOC8-3080 MWD/ST)(EOC8-3080 MWD/ST)to EOC8 0 tion A Tau=1.0 1.27*1.32 0 tion8 Tau=0.0 1.25 1.29*Use this value at BOC8 prior to performing scram time testing.
TVA Nuclear Fu~Core Operating L~Report TVAWOLR-BF2C8 Revision 1, Page 16 (Final)1.4 Figure 3 GEXL-Plus Kf Curve OLMCPR Flow Corrections 1.3 None 117.0,%n2.0%107.0%102.5%1.0 20 30 40 60 60 70 80 80 100 Total Core Flow (%rated)For 40%(WT (100%, Kf=MAX[1.0, A-0.00441~WT]
WT (40%, Kf=[A-0.00441*WT
]~[1.0+0.0032*(40-WT)]WT>100%, Kf=1.0 where: WT=Percent of Rated Core Flow, and.A=constant which depends on the Flow Control Mode and the Scoop Tube Setpoint as noted below.Fl w n I Mod MANUAL MANUAL MANUAL MANUAL AUTOMATIC co Tu t oin 102.5%107.0%112.0%117.0%N/A 1.3308 1.3528 1.3793 1.4035 1A410
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