NRC 2013-0040, Core Operating Limits Report (COLR) Unit 1 Cycle 35 (U1C35)
| ML13108A313 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/18/2013 |
| From: | Millen M Point Beach |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NRC 2013-0040, U1C35 | |
| Download: ML13108A313 (20) | |
Text
April 18, 201 3 EN*FTGvJ POINT ~~ACH F NRC 201 3-0040 TS 5.6.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant Unit 1 Docket No. 50-266 Renewed License No. DPR-24 Core Operatinn Limits Report (COLR) Unit 1 Cvcle 35 (U1 C35) In accordance with the requirements of Point Beach Nuclear Plant (PBNP) Technical Specification 5.6.4, enclosed is revised TRM 2.1, COLR, Unit 1, Cycle 35. The enclosure to this letter contains the revised PBNP U1 C35 COLR that was issued on April 2, 2013. This letter contains no new regulatory commitments and no revisions to existing commitments.
Very truly yours, NextEra Energy Point Beach, LLC Michael Millen Licensing Manager Enclosure 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, UNlT 1 CORE OPERATING LIMITS REPORT (COLR)
UNlT I CYCLE 35 (UlC35) 18 pages follow TRM 2.1 CORE OPERATING LIMITS REPORT (COLR) UNIT I CYCLE 35 REVISION 15 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 35 TRM 2.1 U1 Revision 15 April 2, 2013 1.0 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. I 2.2 2.12 Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 Figure 5A Figure 6 Table 1 PBNP TS - 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 (Fo(Z)) Nuclear Enthalpy Rise Hot Channel Factor (F~~~) 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 ChanneFactor Normalized Operating Envelope (K(Z)) Summary of W(Z) as a Function of Core Height BOC Part-Power Summary of W(Z) as a Function of Core Height Flux Difference Operating Envelope NRC Approved Methodologies for COLR Parameters Page 2 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
TRM 2.1 U1 Revision 15 April 2, 201 3 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 have been developed using the NRC approved methodologies specified in Technical Specification 5.6.4. 2.1 Reactor Core Safety Limits (TS 2.1.1) 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 1 and 2 2.2 Shutdown Marain (TS 3.1.1 and referenced in TS 3.1.4, 3.1.5, 3.1.6, and 3.1.8) SDM shall be 22.0% AWk (see Figure 2). Applicability:
MODES 1, 2, and 3 SDM shall be 21 % AWk. Applicability:
MODES 4 and 5 2.3 Moderator Temperature Coefficient (TS 3.1.3) The upper MTC limits shall be maintained within the limits. The maximum upper MTC limits shall be: 15 pcmPF for power levels 170% RTP 10 pcmPF for power levels >70% RTP Applicability:
MODE 1 and MODE 2 with bff 21 .O. 2.4 Shutdown Bank Insertion Limit (TS 3.1.5) NOTE: This limit is not applicable while performing SR 3.1.4.2. Each shutdown bank shall be fully withdrawn. Fully withdrawn is defined as
> 225 steps.
Applicability:
MODES 1 and 2 Page 3 of 18 TRM 2.1 U1 Revision 15 April 2, 2013 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 35 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. Applicability:
MODE 1 and MODE 2 with bff 21.0 2.6 Nuclear Heat Flux Hot Channel Factor (Fo(Z)) (TS 3.2.1) The Heat Flux Hot Channel Factor shall be within the following limits: for P > 0.5 FQ(Z) I CFQ
- K(Z) / 0.5 for P 5 0.5 Where P is the fraction of Rated Power at which the core is operating.
FQ(Z) is both: Steady State Transient F~'(Z) = FQ(Z)
- 1.08 F~~(z) = F~'(Z)
- W(Z) / P for P>0.5 F~~(z) = F~'(Z)
- W(Z) / 0.5 for P5 0.5 CFQ = 2.60 K(Z) is the function in Figure 4 W(Z) is the function in Figures 5 and 5A. The following Fa penalty factors are applicable to Cycle 35. Applicability:
MODE 1 Cycle Burnup (MWDIMTU)
BOL TO 1 178 1179TO 1473 1474 TO 1 620 1621 TO EOL Page 4 of 18 ~~~(2) Penalty Factors 1.0378 1.0298 1.0218 1.02 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 35 TRM 2.1 U1 Revision 15 April 2, 201 3 2.7 Nuclear Enthal~v Rise Hot Channel Factor (FNAH) (TS 3.2.2) The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit: 2.7.1 F~AH <I -68 x [I + 0.3(1-P)]
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) The AFD target band is %5%. The AFD Acceptability Operation Limits are provided in Figure 6. Applicability:
MODE 1 with THERMAL POWER 21 5% RTP POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
TRM 2.1 U1 Revision 15 April 2, 2013 2.9 Overtemperature AT Setpoint (TS 3.3.1, Table 3.3.1-1 note 1) Overtemperature AT setpoint parameter values (for 1800 MWt core power):
indicated AT at RTP, OF indicated RCS average temperature, OF 576.0°F pressurizer pressure, psig 2235 psig I. I 75 (NTSP)~ 1.188 (AV)' 0.01 6 0.00081 1 40 sec 8 sec 4 sec 2 sec 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 RTP, such that:
For qt - qb within -12, +6 percent, f(Al) = 0. For each percent that the magnitude of qt - qb exceeds +6 percent, the AT trip setpoint shall be automatically reduced by an equivalent of 2.00 percent of Rated Power.
For each percent that the magnitude of qt - qb exceeds -12 percent, the AT trip setpoint shall be automatically reduced by an equivalent of 2.69 percent of Rated Power.
Applicability:
MODES 1 and 2 Nominal Setpoint Value 2 Allowable Value Page 6 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) TRM 2.1 U1 Revision 15 April 2, 2013 2.1 0 Overpower AT Setpoint (TS 3.3.1, Table 3.3.1 -1 note 2) Overpower AT setpoint parameter values (for 1800 MWt core power):
indicated AT at RTP, OF indicated RCS average temperature, OF 576.0°F 1.098 (NTsP)' 1 .I 11 (Av)2 0.0 for increasing T 0.0 for decreasing T 0.00123 for T 2 T' 0.0 for T < T' 0 sec 4 sec 2 sec Applicability:
MODES 1 and 2 2.1 1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (TS 3.4.1) T,, shall be 1577°F. Pressurizer pressure shall be maintained 22205 psig during operation.
NOTE: Pressurizer pressure limit does not apply during:
- 1) THERMAL POWER ramp 95% RTP per minute; or 2) THERMAL POWER step >lo% RTP. Reactor Coolant System raw measured Total Flow Rate shall be maintained 21 86,000 gpm. Applicability:
MODE 1 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 22350 ppm. Applicability:
MODE 6 ' Nominal Setpoint Value Allowable Value POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) TRM 2.1 U1 Revision 15 April 2, 2013 FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE 0.0 0.2 0.4 0.6 0.8 1 .O 1.2 1.4 Core Power (fraction of 1800 MWt) Page 8 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 35 TRM 2.1 U1 Revision 15 April 2, 2013 FIGURE 2 REQUIRED SHUTDOWN MARGIN Page 9 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 35 FIGURE 3 CONTROL BANK INSERTION LIMITS Power Level (% of Rated Power)
NOTE: The Figure is applicable for any fully withdrawn position of 2 225 steps (Limits are always considered met when withdrawn position is, 225 steps). Page 10 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 35 TRM 2.1 U1 Revision 15 April 2, 2013 FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z)) CORE BEIGELT 0 Page 11 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) TRM 2.1 U1 Revision 15 April 2, 2013 FIGURE 5 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12%
Excluded)
Page 120f 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
TRM 2.1 U1 Revision 15 April 2, 2013 UNIT 1 CYCLE 35 FIGURE 5 (con't) Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded) Page 13 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 35 TRM 2.1 U1 Revision 15 April 2, 2013 FIGURE 5A BOC Part-Power Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
Page 14 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 35 TRM 2.1 U1 Revision 15 April 2, 2013 FIGURE 5A (con't) BOC Part-Power Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
Page 150f 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 35 TRM 2.1 U1 Revision 15 April 2, 2013 OPERATION FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE Axial Flux Differenc;e NOTES: 1) This figure represents the Constant Axial Offset Control (CAOC) band used in safety analyses, it may be administratively tightened depending on in-core flux map results. Refer to Figure 2 of Reactor Operating Data (ROD) 1.2 for the administrative limit. 2) The AFD may deviate outside the target band with THERMAL POWER < 50% RTP. 3) The AFD target band is +I-5% for THERMAL POWER 215% RTP.
Page 16 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 35 TRM 2.1 U1 Revision 15 April 2, 201 3 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS Page 17 of 18 NRC Approved Methodology Caldon, Inc., Engineering Report-80P, "TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM~TM System," Revision 0, Mar 1997. Caldon, Inc., Engineering Report-16OP, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM~TM System," Revision 0, May 2000. 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 Methodology," 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-8403 (non-proprietary), "Power Distribution Control and Load Following Procedures," September 1974 WCAP-14449-P-A, "Application of Best Estimate Large Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection," Revision I, October 1999 (cores containing 422V
+ fuel) WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," January 2005.
WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985 WCAP-10054-P-A, Addendum 2, Revision I, "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 COLR Section All 2.1 2.2 2.3 2.4 2.5 2.6 Parameter Reactor Thermal Output 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)
POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 35 TRM 2.1 U1 Revision 15 April 2,2013 Page 18 of 18 I COLR Section 2.7 2.8 2.9 2.1 0 2.1 1 2.1 2 Parameter Nuclear Enthalpy Rise Hot Channel Factor (F~~~) Axial Flux Difference (AFD) Overtemperature AT Setpoint Overpower AT Setpoint RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Refueling Boron Concentration NRC Approved Methodology WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 WCAP-16259-P-A, "Westinghouse Methodology for Applications of 3-D Transient Neutronics to Non-LOCA Accident Analysis," August 2006. WCAP-8403 (non-proprietary), "Power Distribution Control and Load Following Procedures," September 1974 NS-TMA-2198, Westinghouse to NRC Letter
Attachment:
"Operation and Safety Analysis Aspects of an Improved Load Follow Package," January 31, 1980. NS-CE-687, Westinghouse to NRC Letter, "Power Distribution Control Analysis," July 16, 1975. 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-P, Rev. 3, "Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for Point Beach Units 1 & 2 Power Uprate 1775 MWt Core-Power with Feedwater Venturis, or 1800 MWt Core-Power with LEFM on Feedwater Header)," February 2009. 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