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
April 30, 2009 POINT BEACH 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 (U1 C32) 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 I Cycle 32 (Ul C32) is enclosed.
The PBNP U1 C32 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 ames Costedio
/+@pa 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, 661 0 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 TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
TRM 2.1 U1 Revision 10 April 20, 2009 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 Section 2.1 2.2 2.12 Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 Figure 6 PBNP TS 7
2.1.1 3.1.I 3.1.4 3.1.5 3.1.6 3.1.8 3.1.3 3.1.5 3.1.6 3.2.1 3.2.2 3.2.3 3.3.1 3.3.1 3.4.1 Description Reactor Core Safety Limits Shutdown Margin Rod Group Alignment Limits Shutdown Bank lnsertion Limits Control Bank lnsertion Limits Physics Test Exceptions Moderator Temperature Coefficient Shutdown Bank lnsertion Limit Control Bank lnsertion Limits Nuclear Heat Flux Hot Channel Factor (FQ(Z))
Nuclear Enthalpy Rise Hot Channel Factor ( F ~ ~ H )
Axial Flux Difference (AFD)
Overtemperature AT Setpoint Overpower AT Setpoint RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Refueling Boron Concentration Reactor Core Safety Limits Curve Required Shutdown Margin Control Bank lnsertion Limits Hot Channel Factor Normalized Operating Envelope (K(Z)) for 0.422Vl-Fuel RAOC Summary of W(Z) with HFP AFD Band of -81+9%
Flux Difference Operating Envelope Page 2 of 16
POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U l 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 I and 2 2.2 Shutdown Margin (TS 3.1. I and 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 pcmI0F for power levels 570% RTP 50 pcmI0F for power levels >70% RTP Applicability: MODE 1 and MODE 2 with kerf r 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 keR rl.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 ~ ~ ( z )
= F~'(Z)
- W(Z) / P for P>0.5 F ~ ~ ( z )
= F~'(Z)
- W(Z) 1 0.5 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 FQ penalty factors are applicable to Cycle 32.
Applicability: MODE 1 Cycle Burnup (MWDIMTU)
Beginning-of-Cycle to End-of-Cycle F ~ ~ ( z )
Penalty Factors 1.02
POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
TRM 2.1 U l Revision 10 April 20, 2009 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~erature AT 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 5of 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 - qb within -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 2.1 2 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 0.001 03 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 I and 2 2.1 I RCS Pressure, Temperature, and Flow Departure from Nucleate Boilinq (DNB) Limits (TS 3.4.1 )
2.1 I I Tavg shall 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 TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
TRM 2.1 U1 Revision 10 April 20, 2009 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 TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U l 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 TECHNICAL REQUIREMENTS MANUAL I
CORE OPERATING LIMITS REPORT (COLR)
UNIT I CYCLE 32 TRM 2.1 U1 Revision 10 Revision 10 April 20, 2009 FIGURE 2 REQUIRED SHUTDOWN MARGIN 0.0%
0 10 20 30 40 50 60 Core Burnup (%)
Page 9 of 26
POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
UNIT I CYCLE 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 TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
TRM 2.1 U l Revision 10 April 20, 2009 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 I CYCLE 32 FIGURE 5 RAOC Summary of W(Z) with HFP AFD Band of -8/+9%
(Top 15% and Bottom 12% Excluded)
Page 12 of 16 Height
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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 Page 15 of 16 COLR
- 2. I 2.2 2.3 2.4 2.5 2.6 Parameter Reactor Core Safety Limits Shutdown Margin Moderator Temperature Coefficient Shutdown Bank Insertion Limit Control Bank Insertion Limits Height Dependent Heat Flux Hot Channel Factor (FQ)
NRC Approved Methodology WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodolagy," July 1985 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control FQ Surveillance 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
POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U l Revision 10 April 20, 2009 CORE OPERATING LIMITS REPORT (COLR)
UNIT I CYCLE 32 TABLE I NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS Page 16 of 16 NRC Approved Methodology WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 WCAP-I 021 6-P-A, Revision I A, "Relaxation of Constant Axial Offset Control Fa Surveillance Technical Specification," February 1994 WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"
September 1986 WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"
September 1986 WCAP-11397-P-A, "Revised Thermal Design Procedure," April 1989, for those events 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 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 COLR Section 2.7 2.8 2.9 2.10 2.1 1 2.12 Parameter Nuclear Enthalpy Rise Hot Channel Factor ( F ~ ~ H )
Axial Flux Difference (AFD)
Overtemperature AT Setpoint Overpower AT Setpoint RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Refueling Boron Concentration