NRC 2012-0108, Cycle 33 (U2C33) Core Operating Limits Report
| ML12332A332 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/27/2012 |
| From: | Millen M Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2012-0108, TS 5.6.4 | |
| Download: ML12332A332 (20) | |
Text
November 27,2012 NRC 2012-0108 TS 5.6.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant Unit 2 Docket No. 50-301 Renewed License No. DPR-27 Unit 2 Cvcle 33 (U2C33) Core Operating Limits Report In accordance with the requirements of Point Beach Nuclear Plant (PBNP)
Technical Specification 5.6.4, enclosed is revised TRM 2.1, COLR, Unit 2, Cycle 33.
The enclosure to this letter contains the revised PBNP U2C33 COLR that was issued on November 16,2012.
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 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, UNlT 2 CORE OPERATING LIMITS REPORT (COLR)
UNlT 2 CYCLE 33 (U2C33) 18 pages follow
TRM 2.1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 33 REVISION 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR) 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 PBNP Description Section -
TS 2.1 2.1 .I Reactor Core Safety Limits 2.2 3.1.1 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 Insertion Limits 3.2.1 Nuclear Heat Flux Hot Channel Factor (Fo(Z))
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( F ~ ~ ~ )
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 I 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 422V+ Fuel Figure 5 Summary of W(Z) as a Function of Core Height Figure 5A BOC Part-Power Summary of W(Z) as a Function of Core Height Figure 6 Flux Difference Operating Envelope Page 2 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16.201 2 CORE OPERATING LIMITS REPORT (COLR) 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. I )
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 Margin (TS 3.1.1 and referenced in TS 3.1.4, 3.1-5,3.1.6, and 3.1.8) 2.2.1 SDM shall be 22.0% Aklk (see Figure 2).
Applicability: MODES 1, 2, and 3 2.2.2 SDM shall be 21% AWk.
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 pcml"F for power levels 570% RTP 50 pcmPF for power levels >70% RTP Applicability: MODE 1 and MODE 2 with keff 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.
2.4.1 Each shutdown bank shall be fully withdrawn.
2.4.2 Fully withdrawn is defined as 2225 steps.
- Applicability
- MODES 1 and 2 Page 3 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 33 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 bR21.0 2.6 Nuclear Heat Flux Hot Channel Factor (Fa(Z)) (TS 3.2.1)
The Heat Flux Hot Channel Factor shall be within the following limits:
FQ (Z) s CFQ
- K(Z) / P for P > 0.5 FQ (Z) 5 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 FQ'(Z) = FQ(Z)* 1.08 Transient F Q ~ ( Z=) FQC(z)* W(Z) / P for P > 0.5 F Q ~ ( Z=) F~'(Z)
- W(Z) / 0.5 for P S 0.5 K(Z) is the function in Figure 4 W(Z) is the function in Figures 5 and 5A The following FQ penalty factors are applicable to Cycle 33.
Cycle Burnup (MWDIMTU) ~ ~ ~Penalty
( 2 )Factors BOL to 738 1.02 739 to 2061 I,0246 2062 to 3091 1.0308 3092 to 3825 1.0247 3826 to EOL 1.02 Applicability: MODE 1
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR) 2.7 Nuclear Enthalpv Rise Hot Channel Factor ( F ~ (TS ~ )3.2.2)
The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit:
2.7.1 F~~~15% RTP 2.9 Overtem~eratureAT Set~oint(TS 3.3.1, Table 3.3.1-1 note 1)
OvertemperatureAT setpoint parameter values (for 1800 MWt core power):
ATo = indicated AT at RTP, OF T = indicated RCS average temperature, OF T' 5 576.0°F P -
- pressurizer pressure, psig P' = 2235 psig KI -< I. I75 (NTSP)'
K1 5 1.188 (AV)'
K2
-- 0.016 K3
-- 0.00081 1
- 40 sec 71 z2 - 8 sec 73
- 4 sec 74
- 2 sec f(Al) is an event 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 q, and qb are the percent power in the top and bottom halves of the core respectively, and ql + q b is total core power in percent of RTP, such that:
Nominal Setpoint Value Allowable Value Page 5 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 33.
2.9.1 For qt - qb within -12, +6 percent, f(Al) = 0.
2.9.2 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.
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 2.69 percent of Rated Power.
Applicability: MODES 1 and 2 2.10 Overpower AT Setpoint (TS 3.3.1. Table 3.3.1-1 note 21 Overpower AT setpoint parameter values (for 1800 MWt core power):
indicated AT at RTP, "F indicated RCS average temperature, OF 576.0°F 1.098 (NTSP)'
1.111 (AV)~
0.0 for increasing T 0.0 for decreasing T 0.00123 for T L T' 0.0 for T < T' 0 sec 4 sec 2 sec Applicability: MODES 1 and 2
' Nominal Setpoint Value Allowable Value Page 6 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 33 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (TS 3.4.1) 2.1 1.I Tavg shall be 577°F.
2.1 1.2 Pressurizer pressure shall be maintained 22205 psig during operation.
NOTE: Pressurizer pressure limit does not apply during:
1 THERMAL POWER ramp >5% RTP per minute; or
- 2) THERMAL POWER step >lo% RTP.
2.11 -3 Reactor Coolant System raw measured Total Flow Rate shall be maintained 1186,000 gpm.
Applicability: MODE I 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 maintained22300 ppm, Applicability: MODE 6 Page 7 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 33 FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE (Cores containing 422V+ fuel) 0.0 0.2 0.4 0.6 0.8 I.O 1.2 1.4 Core Power (fraction of 1800 MWt)
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 33 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 2 225 steps).
Page 10 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 33 FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))
FOR 422V+ FUEL 0 1 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (Kc')
Page 11 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 33 FIGURE 5 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
Page 12 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 33 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 TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR)
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 TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 33 FIGURE 5A (con't)
BOC Part-Power Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
- 1. Height (feet) 1 1
Part-Power W(Z) with Correction Factor Hot Full Power I 75% Power 6.2 I.0688 I.0566 10.4 1.OOOO 1.OOOO 10.6 1,0000 1.OOOO 10.8 1.OOOO 1.OOOO II 1.oooo 1.oooo 11.2 1.0000 1.oooo 11.4 1.OOOO 1.OOOO 11,6 1.OOOO 1.oooo 11.8 1.OOOO 1.OOOO 12 I.oooo Innnn Page 150f 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR)
FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE OPERATION Axial Flux Difference NOTE:
I. 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 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 2 15% RTP.
Page 16 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 33 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS COLR Parameter NRC Approved Methodology Section All Reactor Thermal Output 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 L E F M ~ TSystem,"
M Revision 0, May 2000.
2.1 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 WCAP-9272-P-A, "Westinghouse Reload Safety Coefficient Evaluation Methodology," 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 Nuclear Heat Flux Hot WCAP-8403 (non-proprietary), "Power Distribution Channel Factor (FQ(Z)) Control and Load Following Procedures,"
Westinghouse Electric Corporation, 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 to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSl Condensation Model," Addendum 2, Revision 1, July 1997 Page 17 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 16 November 16,2012 CORE OPERATING LIMITS REPORT (COLR)
TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS COLR Parameter NRC Approved Methodology Section 2.7 Nuclear Enthalpy Rise Hot WCAP-9272-P-A, "Westinghouse Reload Safety Channel Factor ( F ~ ~ H ) Evaluation Methodology," July 1985 WCAP-16259-P-A, "Westinghouse Methodology for Applications of 3-D Transient Neutronics to Non-LOCA Accident Analysis," August 2006.
2.8 Axial Flux Difference (AFD) WCAP-8403 (nonproprietary), "Power Distribution Control and Load Following Procedures,"
Westinghouse Electric Corporation, 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, " July 16, 1975.
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. II RCS Pressure, Temperature, WCAP-I 1397-P-A, "Revised Thermal Design and Flow Departure from Procedure," April 1989, for those events analyzed Nucleate Boiling (DNB) Limits using RTDP WCAP-14787-P, Rev. 3, "Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wisconsin Electric Power Company 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 2.12 Refueling Boron Concentration WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 Page 18 of 18