NRC 2008-0020, Cycle 30 (U2C30) Core Operating Limits Report
| ML081210474 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/24/2008 |
| From: | Mccarthy J Florida Power & Light Energy Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2008-0020 | |
| Download: ML081210474 (18) | |
Text
FPL Energy Point Beach, LLC, 6590 Nuclear Road, Two Rivers, WI 54241 FPL Energy, Point Beach Nuclear Plant April 24, 2008 NRC 2008-0020 10 CFR 50.36 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant Unit 2 Docket No. 50-301 License No. DPR-27 1 Unit 2 Cycle 30 (U2C30) Core Operatinn Limits Report In accordance with the requirements of Point Beach Nuclear Plant (PBNP)
Technical Specification 5.6.4, "Core Operating Limits Report (COLR),"
FPL Energy Point Beach, LLC, is submitting the Core Operating Limits Report for PBNP Unit 2 Cycle 30 (U2C30).
The PBNP U2C30 COLR was issued on April 19,2008.
This letter contains no new commitments and no revisions to existing commitments.
Very truly yours, FPL Enerav Poir LLC bite Vice President Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW An FPL Group company
ENCLOSURE CORE OPERATING LIMITS REPORT POINT BEACH NUCLEAR PLANT, UNIT 2 CYCLE 30 (U2C30)
TRM 2.1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 REVISION 10
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 I 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 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 (p,~)
I Axial Flux Difference (AFD)
Overtemperature AT Setpoint Overpower AT Setpoint 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 422V+ Fuel I Figure 5 RAOC Summary of W(Z) with HFP AFD Band of -81+g0h (Top 15% and Bottom 12% Excluded)
Figure 6 Flux Difference Operating Envelope Page 2 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 I 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.
I Applicability: 'MODES 1 and 2 2.2 Shutdown Margin (TS 3.1.Iand referenced in TS 3.1.4, 3.1.5, 3.1.6, and 3.1.8)
I 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% 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 170% RTP 10 pcml°F for power levels >70% RTP Applicability: MODE 1 and MODE 2 with bff21.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
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 I 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 kR 21.0 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) I CFQ* K(Z) 1 P for P > 0.5 FQ(Z) I CFQ* K(Z) 10.5 for P I 0.5 Where P is the fraction of Rated Power at which the core is operating.
Fa (Z) is both:
Steady State F~'(Z) = Fa (Z)
- 1.08 Transient F ~ ~ ( =z F~'(Z)
)
- W(Z)
CFQ= 2.60 (422V+ Fuel)
K(Z) is the function in Figure 4 W(Z) is the function in Figure 5 The following FQ penalty factors are applicable to Cycle 30. I Linear interpolation is adequate for intermediate cycle burnups. I Applicability: MODE 1 Page 4 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 I 2.7 Nuclear Enthal~vRise Hot Channel Factor (TS 3.2.2)
The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit:
2.7.1 F~~~< I .77 x [ I + 0.3(1-P)] (422V+ Fuel) where: P is the fraction of Rated Power at which the core is operating.
Applicability: MODE 1 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~erafureAT 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 RTD 0 sec for Sostman or equivalent RTD 2 sec for Rosemont or equivalent RTD 0 sec for Sostman or equivalent RTD f(AI) 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 q and qb are the percent power in the top and bottom halves of the core respectively, and q + qb is total core power in percent of Rated Power, such that:
Page 5 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 I 2.9.1 For qt - qb within -12, +5 percent, f(Al) = 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 2.10 Over~owerAT Set~oint(TS 3.3.1, Table 3.3.1-1 note 2)
Overpower AT setpoint parameter values:
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 2 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 1 and 2 Page 6 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 I 2.1 1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boilina (DNB) Limits (TS 3.4.1) 2.11.1 ,T
, shall be 5574°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 95% RTP per minute; or
- 2) THERMAL POWER step >lo% RTP.
2.11.3 Reactor Coolant System raw measured Total Flow Rate shall be maintained 2182,400 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 22200 ppm.
Applicability: 'MODE 6 Page 7 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 I FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE (Cores containing 422V+ fuel)
Core Power (fraction of 1540 MWj Page 8 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 FIGURE 2 REQUIRED SHUTDOWN MARGIN Page 9 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 FIGURE 3 CONTROL BANK INSERTION LIMITS NOTE: ~ d "fully e withdrawn" parking position range 2 225 steps can be used without violating this Figure.
Page 10 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))
FOR 422V+ FUEL CORE HEIGHT 0 Page 11 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 FIGURE 5 RAOC Summary of W(Z) with HFP AFD Band of -8/+9 %
(Top 15% and Bottom 12% Excluded)
Page 12 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 FIGURE 5 (con't)
RAOC Summary of W(Z) with HFP AFD Band of -81+9 %
(Top 15% and Bottom 12% Excluded)
Page 13 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE 50
-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 the administrative limit.
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 30 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS COLR Parameter NRC Approved Methodology Section 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-10216-P-A, Revision 1A, "Relaxation of Channel Factor (Fo(Z)) Constant Axial Offset Control," February 1994 WCAP-14449-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-10924-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-10924-P-A, "LBLOCA Best Estimate Methodology: Model Description and Validation:
Model Revisions," Volume 1, Addendum 4, August 1990 (cores not containing 422V + fuel)
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 15 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 10 0411912008 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 2.8 Axial Flux Difference (AFD) WCAP-10216-P-A, Revision I A , "Relaxation of Constant Axial Offset Control," 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 2.1 0 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, WCAP-11397-P-A, "Revised Thermal Design and Flow Departure from Procedure," April 1989, for those events analyzed Nucleate Boiling (DNB) Limits using RTDP WCAP-14787-PI Rev. 2, "Westinghouse Revised 1
Thermal Design Procedure Instrument Uncertainty Methodology for Wisconsin Electric Power Company Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 MWt-NSSS Power with Feedwater Venturis, or 1679 MWt-NSSS 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