NRC 2009-0052, Submittal of Cycle 32 (U1C32) Core Operating Limit Report
| ML091210698 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/30/2009 |
| From: | Jim Costedio Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2009-0052, TS 5.6.4 | |
| Download: ML091210698 (18) | |
Text
POINT BEACH April 30, 2009 NRC 2009-0052 TS 5.6.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant, Unit 1 Docket 50-266 Renewed License No. DPR-24 Unit 1 Cycle 32 (U1C32) Core Operating Limits Report In accordance with Technical Specification 5.6.4, Core Operating Limits Report (COLR),
Revision 10 of the Core Operating Limits Report for Point Beach Nuclear Plant (PBNP),
Unit ICycle 32 ( U l C32) is enclosed.
The PBNP U1C32 COLR was issued on April 20,2009.
This letter contains no new regulatory commitments and no revisions to existing regulatory commitments.
Very truly yours, NextEra Energy Point Beach, LLC
/+@pa
" ames Costedio Licensing Manager Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241
ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT I CORE OPERATING LIMITS REPORT REVISION 10, ISSUED APRIL 20,2009 16 pages follow
TRM 2.1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 32 REVISION 10
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
I.O CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Point Beach Nuclear Plant has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.4.
A cross-reference between the COLR sections and the PBNP Technical Specifications affected by this report is given below:
COLR PBNP Description Section TS 7
2.1 2.1.1 Reactor Core Safety Limits 2.2 3.1 .I Shutdown Margin 3.1.4 Rod Group Alignment Limits 3.1.5 Shutdown Bank lnsertion Limits 3.1.6 Control Bank lnsertion Limits 3.1.8 Physics Test Exceptions 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank lnsertion Limit 3.1.6 Control Bank lnsertion Limits 3.2.1 Nuclear Heat Flux Hot Channel Factor (FQ(Z))
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( F ~ ~ H )
3.2.3 Axial Flux Difference (AFD) 3.3.1 Overtemperature AT Setpoint 3.3.1 Overpower AT Setpoint 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.12 Refueling Boron Concentration Figure 1 Reactor Core Safety Limits Curve Figure 2 Required Shutdown Margin Figure 3 Control Bank lnsertion Limits Figure 4 Hot Channel Factor Normalized Operating Envelope (K(Z)) for 0.422Vl- Fuel Figure 5 RAOC Summary of W(Z) with HFP AFD Band of -81+9%
Figure 6 Flux Difference Operating Envelope Page 2 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 32 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section I.O are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 5.6.4.
2.1 Reactor Core Safety Limits (TS 2. I. 1)
The combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 1.
Applicability: MODES Iand 2 2.2 Shutdown Margin (TS 3.1. Iand referenced in TS 3.1.4, 3.1.5, 3. I.6, and 3. I.8) 2.2.1 SDM shall be within the limits provided in Figure 2.
Applicability: MODES 1, 2, and 3 2.2.2 SDM shall be 21% Auk.
Applicability: MODES 4 and 5 2.3 Moderator Temperature Coefficient (TS 3.1.3) 2.3.1 The upper MTC limits shall be maintained within the limits.
2.3.2 The maximum upper MTC limits shall be:
55 pcmI0Ffor power levels 570% RTP 50 pcmI0Ffor power levels >70% RTP Applicability: MODE 1 and MODE 2 with kerfr 1.O.
2.4 Shutdown Bank Insertion Limit (TS 3.1.5)
NOTE: This limit is not applicable while performing SR 3.1.4.2.
2.4.1 Each shutdown bank shall be fully withdrawn.
2.4.2 Fully withdrawn is defined as 2228 steps.
Applicability: MODES 1 and 2 2.5 Control Bank insertion Limits (TS 3.1.6)
NOTE: This limit is not applicable while performing SR 3.1.4.2.
The control banks shall be within the insertion, sequence and overlap limits specified in Figure 3.
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 32 Applicability: MODE 1 and MODE 2 with keRrl.O 2.6 Nuclear Heat Flux Hot Channel Factor (FdZ)) (TS 3.2.1)
The Heat Flux Hot Channel Factor shall be within the following limits:
FQ(Z)s CFQ* K(Z) / Pfor P > 0.5 FQ(Z)s CFQ* K(Z) / 0.5 for P 20.5 Where P is the fraction of Rated Power at which the core is operating.
FQ(Z)is both:
e Steady State F~'(Z) = FQ(Z)* I.08 Transient F ~ ~ (=zF~'(Z)
)
- W(Z) / P for P>0.5 F ~ ~ (=z F~'(Z)
)
- W(Z) 10.5 for P< 0.5 CFQ= 2.60 (422V+ Fuel)
K(Z) is the function in Figure 4.
NOTE: The W(Z) factors in Figure 5 are based on steady state Fq at 100% power.
W(Z) is the function in Figure 5.
The following FQpenalty factors are applicable to Cycle 32.
Cycle Burnup (MWDIMTU) F ~ ~ ( Penalty z)
Factors Beginning-of-Cycle to End-of- 1.02 Cycle Applicability: MODE 1
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR) 2.7 Nuclear Enthalpy Rise Hot Channel Factor (TS 3.2.2)
The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit:
2.7. I F~~~< I .77 x [ I + 0.3(1-P)] (422V-t. Fuel) where: P is the fraction of Rated Power at which the core is operating.
Applicability: MODE I 2.8 Axial Flux Difference (AFD) (TS 3.2.3)
NOTE: The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.
The indicated axial flux difference in % flux difference units shall be maintained within the allowed operational space defined by Figure 6.
Applicability: MODE 1 with THERMAL POWER 250% RTP 2.9 Overtem~eratureAT Setpoint (TS 3.3.1, Table 3.3.1-1 note 1)
Overtemperature AT setpoint parameter values:
indicated AT at Rated Power, OF average temperature, OF 569.0°F 2235 psig 1.16 0.0149 0.00072 25 sec 3 sec 2 sec for Rosemont or equivalent R I D 0 sec for Sostman or equivalent RTD 2 sec for Rosemont or equivalent RTD 0 sec for Sostman or equivalent RTD f(Al) is an even function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests, where qt and qb are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of Rated Power, such that:
Page 5 o f 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 32 2.9.1 For qt - qbwithin -12, +5 percent, f(A1) = 0.
2.9.2 For each percent that the magnitude of qt - qb exceeds +5 percent, the AT trip setpoint shall be automatically reduced by an equivalent of 2.12 percent of Rated Power.
2.9.3 For each percent that the magnitude of qt - qb exceeds -12 percent, the AT trip setpoint shall be automatically reduced by an equivalent of 2.0 percent of Rated Power.
Applicability: MODES 1 and 2 2.1 0 Overpower AT Setpoint (TS 3.3.1, Table 3.3.1-1 note 22 Overpower AT setpoint parameter values: 1 indicated AT at Rated Power, OF average temperature, OF 569.0°F 1.10 of Rated Power 0.0262 for increasing T 0.0 for decreasing T 0.00103 for T r T' 0.0 for T < T' 10 sec 2 sec for Rosemont or equivalent RTD 0 sec for Sostman or equivalent RTD 2 sec for Rosemont or equivalent RTD 0 sec for Sostman or equivalent RTD Applicability: MODES Iand 2 2.1 I RCS Pressure, Temperature, and Flow Departure from Nucleate Boilinq (DNB) Limits (TS 3.4.1 )
2.1II Tavgshall be 1574°F.
2.1 1.2 Pressurizer pressure shall be maintained 22205 psig during operation.
NOTE: Pressurizer pressure limit does not apply during:
I) THERMAL POWER ramp >5% RTP per minute; or
- 2) THERMAL POWER step >lo% RTP.
2.1 I.3 Reactor Coolant System raw measured Total Flow Rate shall be maintained 2182,400 gpm.
Applicability: MODE 1 Page 6 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR) 2.12 Refueling Boron Concentration (TS 3.9.1)
Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained 22200 ppm.
Applicability: MODE 6
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE (Cores containing 422V + fuel) 680 Unacceptable Operation i-r fn Acceptable Operation 560 --
5 4 0 i " ' ~ ' " ~ " ' ~ " ' ! '
0 0.2 0.4 0.6 0.8 1 1.2 1.4 Core Power (fraction of 1540 MWt)
Page 8 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 10 I CORE OPERATING LIMITS REPORT (COLR)
Revision 10 April 20, 2009 UNIT ICYCLE 32 FIGURE 2 REQUIRED SHUTDOWN MARGIN 0.0%
0 10 20 30 40 50 60 Core Burnup (%)
Page 9 of 26
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
UNIT ICYCLE 32 FIGURE 3 CONTROL BANK INSERTION LIMITS NOTE: The "fully withdrawn" parking position range r 225 steps can be used without violating this Figure.
Page 10 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))
FOR 0.422V+ FUEL CORE ElEIGIBir (FT)
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
UNIT ICYCLE 32 FIGURE 5 RAOC Summary of W(Z) with HFP AFD Band of -8/+9%
(Top 15% and Bottom 12% Excluded)
Height %FLTpyI
[festJb 1SO 2008 8000 14000
~.a"~rn,mav amxfmimu L B D A ~ ~ I ~
Q .iJ 1,UtIDD I~00069 3 -Q DUtD 3.001lO Ir.2 1.UQCID 4 .0;0iRO 3-69 DUO !.QOO D 0-4 1,OQDD I.08QKl + -0I0OIDI "6.80QlD 0.6 1-00UQ I.E3rCIUQ 2 -0DC)ICk l.0Ra D 0.8 1-0U-DQ 1.YIQIrO 9 -QDLIQ 3 .iolaa~D 1-43 1"DQcl0 I.aaIra 9 "QDO0 3 -000D 3 -2 1.UrJDO I.01~010 % -63 D001 4 .DOID D 1.4 I.CTQ 00 I.UOtYQ .li-0aoo 3.8CllD CI 1-6 1-22B8 1-1726 % -1743 3.1756 4 -8 1.2133 1-1594 2.1 824 3.1 649 2-0 1-3965 I. 1482 ?.I498 3.1532 2.2 1.4 789 1.1383 9 -1363 3:14Q;ir 2-4 l..dfi'lIQ T I2723 3.1256 3.1284 2.8 I-1435 11.1 175 4.1 1161 4.1 4fi$
2.8 1-4261 1-1073 % -1062 3.10131 3-0 1-1IlDY 3 -13963 T -Q99$ "10992 3-2 I. 'la37 1.094131 4 .QGT11fi 3.09B3 3-4 1.dQ3[9 ll-Q834 7 .Q 952 "r.09234 3-6 l.lfJD8 1-0917 1.Q 936 1.ltlr98111 3.8 1-0982 1-a897 % -1i11949 1.0975 4 .0 1xi954 11-rJ576 "EQ967 3 -0958
- 4.2 1.Q9-1i8 1.63844 4 .Q$38431 d .0957 4.4 1-0884 I-U$22 9.099 I 1.r[11983 4.8 1-0874 4 -a8423 2 -099s 3.101D 4.8 1-0883 1LIB75 ll.1~504 3.1CI48 5-0 I-0893 1-0896 ?-I4204 1.1 089 5.2 I-09c34 1-ug35 3.1 DCIB 1.1 120 5-4 I-0934 .1.11930 2.15018 A.1152 5.6 1-0984 1-$I952 2.14338 "ii.1215 5.8 1.3036 I-1Q30 T *I DO87 1.I33'9 6-0 1-7Q98 1-14384 2-11167 1.1479 6.2 1.3 178 1-1157 -
.I 1255 3.1613g 6.4 1-3257 1-1223 3 -1337 3.1 728 6-6 I-4 33M 1'-13017 3.1442 3.183B 6.8 1.1393 1- 1382' % - 9 477 3.1935 Page 12 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 32 FIGURE 5 (con't)
RAOC Summary of W(Z) with HFP AFD Band of -8/+9%
(Top 15% and Bottom 12% Excluded)
Page 13 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE
-35.00 -30.00 -25.00 -20.00 -15.00 -10.00 -5.00 0.00 5.00 10.00 15.00 20.00 25.00 30.00 35.00 Delta I (%)
NOTE: This figure represents the Relaxed Axial Offset Control (RAOC) band used in safety analyses, it may be administratively tightened depending on in-core flux map results. Refer to Figure 2 of ROD 1.2 for administrative limit.
Page 14 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 32 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS COLR Parameter NRC Approved Methodology
- 2. I Reactor Core Safety Limits WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 2.2 Shutdown Margin WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 2.3 Moderator Temperature Coefficient WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodolagy," July 1985 2.4 Shutdown Bank Insertion Limit WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 2.5 Control Bank Insertion Limits WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 2.6 Height Dependent Heat Flux Hot WCAP-10216-P-A, Revision IA, "Relaxation of Channel Factor (FQ) Constant Axial Offset Control FQSurveillance Technical Specification," February 1994 WCAP-I 4449-P-A, "Application of Best Estimate Large Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection," Revision 1, October 1999 (cores containing 422V + fuel)
WCAP-I 0924-P-A, "Large Break LOCA Best Estimate Methodology, Volume 2: Application to Two-Loop PWRs Equipped with Upper Plenum Injection," and Addenda, December 1988 (cores not containing 422V + fuel)
WCAP-I 0924-P-A, "LBLOCA Best Estimate Methodology: Model Description and Validation: Model Revisions," Volume 1, Addendum 4, August 1990 (cores not containing 422V + fuel)
WCAP-I 0054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985 WCAP-10054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSl Condensation Model," July 1997 Page 15 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
UNIT ICYCLE 32 TABLE I NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS COLR Parameter NRC Approved Methodology Section 2.7 .. Nuclear Enthalpy Rise Hot Channel WCAP-9272-P-A, "Westinghouse Reload Factor ( F ~ ~ H ) Safety Evaluation Methodology," July 1985 2.8 Axial Flux Difference (AFD) WCAP-I 0216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control Fa Surveillance Technical Specification," February 1994 2.9 Overtemperature AT Setpoint WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"
September 1986 2.10 Overpower AT Setpoint WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"
September 1986 2.1 1 RCS Pressure, Temperature, and WCAP-11397-P-A, "Revised Thermal Design Flow Departure from Nucleate Procedure," April 1989, for those events Boiling (DNB) Limits analyzed using RTDP WCAP-14787-PI Rev. 2, "Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wisconsin Electric Power Company Point Beach Units I& 2 (Fuel Upgrade & Uprate to 1656 MWt-NSSS Power with Feedwater Venturis, or 1679 MWt-MSSS Power with LEFM on Feedwater Header)",
October 2002.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 for those events not utilizing RTDP 2.12 Refueling Boron Concentration WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 Page 16 of 16