BYRON 2007-0014, Cycle 15 Core Operating Limits Report, Revision 4
| ML070230469 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/23/2007 |
| From: | Hoots D Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 1.10.0101, BYRON 2007-0014 | |
| Download: ML070230469 (16) | |
Text
Exe~n January 23, 2007 LTR: BYRON 2007 0014 File: tlO.0101 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-000 1 Byron Station, Unit 1 Facility Operating License No. NPF- 37 NRC Docket No. STN 50-454
Subject:
Byron Station Unit 1 Cycle 15 Core Operating Limits Report, Revision 4 In accordance with Technical Specification 5~6~5, Core Operating Limits Report (COLR),
we are submitting a revision to the Unit 1 Cycle 15 COLR. The revision involves a change to the W(z) values due to a small difference observed between the predicted and measured value of Axial Offset after start up of the current cycle.
Should you have any questions concerning this report, please contact William Grundmann, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, avid M Hoots Site Vice President Byron Nuclear Generating Station
Attachment:
Byron Station Unit 1 Cycle 15 COLR, Revision 4 DMH/J EL/rah
ATTACHM ENT Byron Station Unit 1 Cycle 15 Core Operating Limits Report Revision 4
CORE OPERATING LIMiTS REPORT (COLR)
FOR BYRON UNIT 1 CYCLE 15 EXELON TRACKING ID:
COLR BYRON 1 REVISiON 4
COLR BYRON 1 Revision 4 Page 1 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 15 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).
The Technical Specifications affected by this report are listed below:
SL 2.1.1 Reactor Core Safety Limits (SLs)
LCO 3.1.1 SHUTDOWN MARGIN (SDM)
LCO 3.1.3 Moderator Temperature Coefficient (MTC)
LCO 3.1.4 Rod Group Alignment Limits LCO 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.6 Control Bank Insertion Limits LCO 3.1.8 PHYSICS TESTS Exceptions MODE 2 LCO 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
LCO 3.2.2 Nuclear Enthaipy Rise Hot Channel Factor (F~H)
LCO 3.2.3 AXIAL FLUX DIFFERENCE (AFD)
LCO 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)
LCO 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.9 Boron Dilution Protection System (BDPS)
LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration The portions of the Technical Requirements Manual affected by this report are listed below:
TRM TLCO 3.1 .b Boration Flow Paths Operating TRM TLCO 3.1 .d Charging Pumps Operating TRM TLCO 3.1.f Borated Water Sources Operating TRM TLCO 3.1 .g Position Indication System Shutdown TRM TLCO 3.1 .h Shutdown Margin (SDM) MODE 1 and MODE 2 with keff 1.0 TRM TLCO 3.1.i Shutdown Margin (SDM) MODE 5 TRM TLCO 3.1.1 Shutdown and Control Rods TRM TLCO 3.1 .k Position Indication System Shutdown (Special Test Exception)
COLR BYRON I Revision 4 Page 2 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits are applicable for the entire cycle unless otherwise identified. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5.
2.1 Reactor Core Safety Limits (SLs) (SL 2.1.1) 2.1.1 In MODES I and 2, the combination of Thermal Power, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 2.1.1.
680 660 a,
V I-a)
E 620 600 580 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits
Exe~n January 23, 2007 LTR: BYRON 2007 0014 File: tlO.0101 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-000 1 Byron Station, Unit 1 Facility Operating License No. NPF- 37 NRC Docket No. STN 50-454
Subject:
Byron Station Unit 1 Cycle 15 Core Operating Limits Report, Revision 4 In accordance with Technical Specification 5~6~5, Core Operating Limits Report (COLR),
we are submitting a revision to the Unit 1 Cycle 15 COLR. The revision involves a change to the W(z) values due to a small difference observed between the predicted and measured value of Axial Offset after start up of the current cycle.
Should you have any questions concerning this report, please contact William Grundmann, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, avid M Hoots Site Vice President Byron Nuclear Generating Station
Attachment:
Byron Station Unit 1 Cycle 15 COLR, Revision 4 DMH/J EL/rah
ATTACHM ENT Byron Station Unit 1 Cycle 15 Core Operating Limits Report Revision 4
CORE OPERATING LIMiTS REPORT (COLR)
FOR BYRON UNIT 1 CYCLE 15 EXELON TRACKING ID:
COLR BYRON 1 REVISiON 4
COLR BYRON 1 Revision 4 Page 1 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 15 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).
The Technical Specifications affected by this report are listed below:
SL 2.1.1 Reactor Core Safety Limits (SLs)
LCO 3.1.1 SHUTDOWN MARGIN (SDM)
LCO 3.1.3 Moderator Temperature Coefficient (MTC)
LCO 3.1.4 Rod Group Alignment Limits LCO 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.6 Control Bank Insertion Limits LCO 3.1.8 PHYSICS TESTS Exceptions MODE 2 LCO 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
LCO 3.2.2 Nuclear Enthaipy Rise Hot Channel Factor (F~H)
LCO 3.2.3 AXIAL FLUX DIFFERENCE (AFD)
LCO 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)
LCO 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.9 Boron Dilution Protection System (BDPS)
LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration The portions of the Technical Requirements Manual affected by this report are listed below:
TRM TLCO 3.1 .b Boration Flow Paths Operating TRM TLCO 3.1 .d Charging Pumps Operating TRM TLCO 3.1.f Borated Water Sources Operating TRM TLCO 3.1 .g Position Indication System Shutdown TRM TLCO 3.1 .h Shutdown Margin (SDM) MODE 1 and MODE 2 with keff 1.0 TRM TLCO 3.1.i Shutdown Margin (SDM) MODE 5 TRM TLCO 3.1.1 Shutdown and Control Rods TRM TLCO 3.1 .k Position Indication System Shutdown (Special Test Exception)
COLR BYRON I Revision 4 Page 2 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits are applicable for the entire cycle unless otherwise identified. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5.
2.1 Reactor Core Safety Limits (SLs) (SL 2.1.1) 2.1.1 In MODES I and 2, the combination of Thermal Power, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 2.1.1.
680 660 a,
V I-a)
E 620 600 580 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits
COLR BYRON 1 Revision 4 Page 3 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 15 2.2 SHUTDOWN MARGIN (SDM)
The SDM limit for MODES 1, 2, 3, and 4 is:
2.2.1 The SDM shall be greater than or equal to 1.3% Ak/k (LCO5 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.3.9; TRM TLCOs 3.1.b, 3.1,d, 3.1.f, 3.1.h, and 3.1.j).
The SDM limit for MODE 5 is:
2.2.2 SDM shall be greater than or equal to 1.3% Ak/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3,1.i and 3.l.j).
2.3 Moderator Temperature Coefficient (MTC) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +2.1 x ~ Ak/k/°F.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10~Ak/k/°F.
2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x i0~Ak/k/°F.
2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10~Ak/kI°F.
where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Limits (LCO 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.
2.5 Control Bank Insertion Limits (LCO 3.1.6) 2.5.1 The control banks, with Bank A greater than or equal to 224 steps, shall be limited in physical insertion as shown in Figure 2.5.1.
2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps.
2.5.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C and Bank D. The control banks shall be sequenced in reverse order upon insertion.
2.5.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap limits as a function of park position:
Park Position (step) Overlap Limit (step) 231 115
COLR BYRON 1 Revision 4 Page 4 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 Figure 2.5.1:
Control Bank Insertion Units Versus Percent Rated Thermal Power 224 (26.52%, 224) (76.96%, 224) 220 200 180
~160 (100%, 161) 140
~120 0
~1O0 0
a-
~60 40 20 0
0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)
COLR BYRON 1 Revision 4 Page 5 of 13 CORE OPERATING LiMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 2.6 Heat Flux Hot Channel Factor (FQ~fl(LCO 3.2.1) 2.6.1 Total Peaking Factor:
F~T~
FQ(Z) 9-----xK(Z) forP0.5 F
FQ(Z) ~-xK(Z) forP>0.5 where: P the ratio of THERMAL POWER to RATED THERMAL POWER F~T~2,60=
K(Z) is provided in Figure 2.6.1.
2.6.2 W(Z) Values:
a) When PDMS is OPERABLE, W(Z) = 1.00000 for all axial points.
b) When PDMS is inoperable, W(Z) is provided in Table 2.6.2.a.
The normal operation W(Z) values have been determined at burnups of 1211, 6000, 14000, and 20000 MWD/MTU.
Table 2.6.2.b shows the F%(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FWa(z) as per Surveillance Requirement 3.2.1.2. A 2% penalty factor shall be used at all cycle burnups that are outside the range of Table 2.6.2.b.
2.6.3 Uncertainty
The uncertainty, UFQ, to be applied to the Heat Flux Hot Channel Factor F0(Z) shall be calculated by the following formula U/~Q_Uq, .U where:
Uqu = Base FQ measurement uncertainty 1.05 when PDMS is inoperable (Uqu is defined by PDMS when OPERABLE.)
Ue = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:
FQ(Z) Warning Setpoint 2% of F~(Z)Margin FQ(Z) Alarm Setpoint 0% of F~(Z)Margin
COLR BYRON Revision 4 1 Page 6 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 Figure 2.6.1 K(Z) Normalized FQ(Z) as a Function of Core Height 1.1
.924) 0.9 0.8
~ 0.7 a
U-0.6 0.4 10.5 0.3 0.2 0.1 0
0 1 2 3 4 5 6 7 8 9 101112 BOTTOM Core Height (ft) TOP
COLR BYRON 1 RevisiOn 4 Page 7 of 13 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 Note: W(Z) vatues at 20000 MWD/MTU may be appfted to cycle burnupS greater than 20000 MWO/MTU to prevent W(Z) functiOn extrapolation
COLR BYRON 1 Revision 4 Page 8 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 1~ ~
aue Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) FCQ(z) 0 1.0200 150 1.0232 323 1.0277 496 1,0318 669 1.0356 841 1.0388 1014 1.0412 1187 1.0429 1360 1.0436 1533 1.0402 1706 1.0368 1878 1.0335 2051 1.0305 2224 1.0279 2397 1.0257 2570 1.0239 2743 1.0225 2915 1.0215 3088 1.0207 3261 1.0200 Notes:
Linear interpolation is adequate for intermediate cycle burnups.
All cycle burnups outside the range of the table shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.
COLR BYRON 1 Revision 4 Page 9 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 2.7 Nuclear Enthalpy Rise Hot Channel Factor (F~ (LCO 3.2.2) 2.7.1 Ft~ F~[1.0+ PF~H(1.0 P)] -
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER
~RTP r~,H PF~H= 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UF~H,to be applied to the Nuclear Enthalpy Rise Hot Channel Factor F~Hshall be calculated by the following formula:
UF~,H= UF~Hm where:
UF~1Hm= Base FN~Hmeasurement uncertainty = 1.04 2.7.3 PDMS Alarms:
FN~HWarning Setpoint 2% of FN~HMargin F~HAlarm Setpoint 0% of F~HMargin 2.8 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3) 2.8.1 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in Figure 2.8.1 or the latest valid PDMS Surveillance Report, whichever is more conservative.
2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.
2.9 Departure from Nucleate Boiling Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL 1.536 The Axial Power Shape Limiting DNBR (DNBRAPSL) is applicable with THERMAL POWER 50% RTP when PDMS is OPERABLE.
2.9.2 PDMS Alarms:
DNBR Warning Setpoint 2% of DNBR Margin DNBR Alarm Setpoint 0% of DNBR Margin
COLR BYRON 1 Revision 4 Page 10 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits w ith PDMS Inoperable 120 100 Unaccepta~Ie /
(-15, 100)
\
~÷1O,100)
Unacceptable
~ 80 Operatior~ / Operation
/
\
Accept ble 60 ___________ Operaton _______
40 (-35, 5_~)_______
20 I 0
40 20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON 1 Revision 4 Page 11 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip setpointK1 shall be equal to 1.325.
2.10.2 The Overtemperature AT reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 / °F.
2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00181 / psi.
2.10.4 The nominal Tavgat RTP (indicated)T shall be less than or equal to 588.0 °F.
2.10.5 The nominal RCS operating pressure (indicated) P shall be equal to 2235 psig.
2.10.6 The measured reactor vessel AT lead/lag time constant t 1
shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant t2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant t3 shall be less than or equal to 2 sec.
2.10.9 The measured reactor vessel average temperature lead/lag time constant t 4
shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant t5shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant t 6
shall be less than or equal to 2 sec.
2.10.12 The f1 (Al) positive breakpoint shall be +10% Al.
2.10.13 The f1 (Al) negative breakpoint shall be -18% Al.
2.10.14 The f1 (Al) positive slope shall be +3.47% / % Al.
2.10.15 The f1 (Al) negative slope shall be -2.61% / % Al.
COLR BYRON 1 Revision 4 Page 12 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint K4 shall be equal to 1.072.
2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0.02 / °F for increasing Tavg 2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 / °Ffor decreasing Tavg.
2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245 / F when T > T.
2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0 / °Fwhen I T.
2.11.6 The nominal Tavg at RTP (indicated) T shall be less than or equal to 588.0 °F 2.11.7 The measured reactor vessel AT lead/lag time constant t1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel AT lead/lag time constant t2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel AT lag time constant t~shall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperature lag time constant t6 shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant t~shall be equal to 10 sec.
2.11,12 The f2 (Al) positive breakpoint shall be 0 for all Al.
2.11.13 The f2 (Al) negative breakpoint shall be 0 for all Al.
2.11.14 The f2(AI) positive slope shall be 0 for all Al.
2.11.15 The f2(Al) negative slope shall be 0 for all Al.
COLR BYRON 1 Revision 4 Page 13 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 15 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (LCO 3.4.1) 2.12.1 The pressurizer pressure shall be greater than or equal to 2209 psig.
2.12.2 The RCS average temperature (Tavg) shall be less than or equal to 593.1 F.
2.12.3 The RCS total flow rate shall be greater than or equal to 386,000 gpm.
2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to the value given in the Table below (LCO 3.9.1). The reported value also bounds the end-of-cycle requirements for the previous cycle.
2.13.2 To maintain keff 0.987 with all shutdown and control rods fully withdrawn in MODES 3, 4, or 5 (TRM TLCO 3.1.g Required Action B.2 and TRM TLCO 3.1.k.2), the Reactor Coolant System boron concentration shall be greater than or equal to the values given in the Table below.
COLR Conditions Boron Concentration Section (ppm) 2.13.1 Refueling 1739 2.13.2 a) prior to initial criticality 1819 2.13.2 b) all other times in core life 2026