NRC 2011-0035, Cycle 32 (U2C32) Core Operating Limits Report
| ML110830008 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/23/2011 |
| From: | Jim Costedio Point Beach |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NRC 2011-0035 | |
| Download: ML110830008 (18) | |
Text
March 23,201 1 POINT BEACH NRC 201 1-0035 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 32 (U2C32) Core Operating Limits Re~ort In accordance with the requirements of Point Beach Nuclear Plant (PBNP)
Technical Specification 5.6.4, "Core Operating Limits Report (COLR),"
NextEra Energy Point Beach, LLC (NextEra) is submitting the COLR for PBNP Unit 2 Cycle 32 (U2C32) this COLR is applicable for MODES 5 and 6 only.
The enclosure contains the PBNP U2C32 COLR that was issued on March 21,201 1.
This letter contains no new regulatory commitments and no revisions to existing commitments.
Very truly yours, NextEra Energy Point Beach, LLC ames Costedio 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, UNlT 2 CORE OPERATING LIMITS REPORT (COLR)
UNlT 2 CYCLE 32 (U2C32)
TRM 2.
CORE OPtRA TS REPORT T 2 CYCLE 32 REVISION 13
POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U2 Revision 13 March 23, 201 1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 32 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 2.12 Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 Figure 5A Figure 6 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 ~ ~ 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 422V+ Fuel 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 Page 2 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23, 201 1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 32 2.0 OPERATING LIMITS EC262993 allows entering Cycle 32 Mode 6 and Mode 5 only under the current licensing basis. This core reload EC also allows entering Mode 6 and Mode 5 under the EPU conditions. However, Mode 4 cannot be entered prior to the NRC approval and PBNP implementation of LARS 241 (AST) and 261 (EPU). Operation in all Modes is allowed subsequent to the NRC approval and PBNP implementation of LAR 241 (AST) and 261 (EPU).
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 Safetv Limits (TS 2.1.I
)
I Data not available. Pending NRC approval.
I Applicability: NIA 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)
I 2.2.1 Data not available. Pending NRC approval.
I Applicability: NIA 2.2.2 SDM shall be 21 % AWk.
Applicability: MODES 4 and 5 2.3 Moderator Temperature Coefficient (TS 3.1.3)
I 2.3.1 Data not available. Pending NRC approval.
I 2.3.2 Data not available. Pending NRC approval.
I Applicability: NIA 2.4 Shutdown Bank Insertion Limit (TS 3.1.5)
NOTE:
This limit is not applicable while performing SR 3.1.4.2.
I 2.4.1 Data not available. Pending NRC approval.
I 2.4.2 Data not available. Pending NRC approval.
1 Applicability: NIA Page 3 of 16
POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
TRM 2.1 U2 Revision 13 March 23,201 1 2.5 Control Bank Insertion Limits (TS 3.1.6)
NOTE:
This limit is not applicable while performing SR 3.1.4.2.
Data not available. Pending NRC approval.
Applicability: NIA 2.6 Nuclear Heat Flux Hot Channel Factor (Fo(Z)) (TS 3.2.1)
Data not available. Pending NRC approval.
Applicability: NIA 2.7 Nuclear Enthalpv Rise H O
~
~
~
)
(TS 3.2.2)
The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit:
2.7.1 Data not available. Pending NRC approval.
Applicability: NIA 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.
Data not available. Pending NRC approval.
Applicability: NIA 2.9 Overtemperature AT Setpoint (TS 3.3.1, Table 3.3.1-1 note 1)
Data not available. Pending NRC approval.
2.9.1 Data not available. Pending NRC approval.
2.9.2 Data not available. Pending NRC approval.
2.9.3 Data not available. Pending NRC approval.
Applicability: NIA 2.10 Overpower AT Setpoint (TS 3.3.1, Table 3.3.1-1 note 2)
Data not available. Pending NRC approval.
Applicability: NIA Page 4 of 16
POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
TRM 2.1 U2 Revision 13 March 23,201 1 2.1 1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (TS 3.4.1)
I 2.1 1.1 Data not available. Pending NRC approval.
I 2.1 1.2 Data not available. Pending NRC approval.
I 2.1 1.3 Data not available. Pending NRC approval.
I Applicability: N/A 2.12 Refueling Boron Concentration (TS 3.9.1)
Boron concentrations of the Reactor Coolant System, the refueling canal, and the I
refueling cavity shall be maintained 22300 ppm.
Applicability: MODE 6 Page 5 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23, 201 1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 32 FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE (Cores containing 422V+ fuel)
Data not available. Pending NRC approval.
Page 6 of 16
POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 32 TRM 2.1 U2 Revision 13 March 23,201 1 FIGURE 2 REQUIRED SHUTDOWN MARGIN Data not available. Pending NRC approval.
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23, 201 1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 32 FIGURE 3 CONTROL BANK INSERTION LIMITS 1
Data not available. Pending NRC approval.
NOTE:
The "fully withdrawn" parking position range > 225 steps can be used without violating this Figure.
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23, 201 1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 32 FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))
FOR 422V+ FUEL Data not available. Pending NRC approval.
Page 9 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23,201 1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 32 FIGURE 5 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
I Data not available. Pending NRC approval.
Page 10 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23, 201 1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 32 FIGURE 5 (con't)
Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
I Data not available. Pending NRC approval.
Page 11 of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23, 201 1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 32 FIGURE 5A BOC Part-Power Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
I Data not available. Pending NRC approval.
Page 12of 16
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23, 201 1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 32 FIGURE 5A (con't)
BOC Part-Power Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
I Data not available. Pending NRC approval.
Page 13of 16
POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR)
TRM 2.1 U2 Revision 13 March 23, 201 1 FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE I
Data not available. Pending NRC approval.
I NOTE:
Data not available. Pending NRC approval.
Page 14 of 16
POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U2 Revision 13 March 23,201 1 CORE OPERATING LIMITS REPORT (COLR)
TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS Page 15 of 16 2.6 Nuclear Heat Flux Hot Channel Factor (FQ(Z))
WCAP-10216-P-A, Revision I A, "Relaxation of 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 I,
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-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," January 2005.
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
POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U2 Revision 13 March 23,201 1 CORE OPERATING LIMITS REPORT (COLR)
TABLE I NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS Page 16 of 16 COLR Section 2.7 2.8 2.9 2.10 2.1 1 2.1 2 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 NRC Approved Methodology WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control," 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 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 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985