NRC 2011-0035, Cycle 32 (U2C32) Core Operating Limits Report

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

POINT BEACH March 23,201 1 NRC 2011-0035 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 R e ~ o r t 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, 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 32 (U2C32)

TRM 2.

CORE OPtRA TS REPORT T 2 CYCLE 32 REVISION 13

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 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 (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 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 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 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 TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23,201 1 CORE OPERATING LIMITS REPORT (COLR) 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 TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23,201 1 CORE OPERATING LIMITS REPORT (COLR) 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 TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23,201 1 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 32 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 TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23, 201 1 CORE OPERATING LIMITS REPORT (COLR)

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 TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23,201 1 CORE OPERATING LIMITS REPORT (COLR)

TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS 2.6 Nuclear Heat Flux Hot WCAP-10216-P-A, Revision IA, "Relaxation of Channel Factor (FQ(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 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 Page 15 of 16

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 13 March 23,201 1 CORE OPERATING LIMITS REPORT (COLR)

TABLE I 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 2.10 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 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 2.1 2 Refueling Boron Concentration WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 Page 16 of 16