NRC 2013-0040, Core Operating Limits Report (COLR) Unit 1 Cycle 35 (U1C35)

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

ENFTGvJ F POINT ~ ~ A C H April 18, 2013 NRC 2013-0040 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 (U1C35)

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 U1C35 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 ICYCLE 35 REVISION 15

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 35 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. I Reactor Core Safety Limits 2.2 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 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 ChanneFactor Normalized Operating Envelope (K(Z))

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 Table 1 NRC Approved Methodologies for COLR Parameters Page 2 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 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 2.1.1)

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 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.

Each shutdown bank shall be fully withdrawn.

Fully withdrawn is defined as > 225 steps.

Applicability: MODES 1 and 2 Page 3 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 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 bff21.0 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 F~'(Z) = FQ(Z)* 1.08 Transient 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.

Cycle Burnup ~ ~ ~Penalty( 2 )

(MWDIMTU) Factors BOL TO 1178 1.0378 1179TO 1473 1.0298 1474 TO 1620 1.0218 1621 TO EOL 1.02 Applicability: MODE 1 Page 4 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 35 2.7 Nuclear Enthal~vRise 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 ~ A H< 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 215% RTP

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR) 2.9 OvertemperatureAT 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. I75 (NTSP)~

1.188 (AV)'

0.016 0.000811 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR) 2.10 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 2.11 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 2186,000 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR)

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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 35 FIGURE 2 REQUIRED SHUTDOWN MARGIN Page 9 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 35 FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))

CORE BEIGELT 0 Page 11 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR)

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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR)

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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 35 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 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 35 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 35 FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE OPERATION 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2, 2013 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 35 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 LEFM~TM System,"

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 Coefficient WCAP-9272-P-A, "Westinghouse Reload Safety 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 Height Dependent Heat Flux Hot WCAP-8403 (non-proprietary), "Power Channel Factor (FQ) 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 Page 17 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 15 April 2,2013 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 35 COLR Parameter NRC Approved Methodology Section 2.7 Nuclear Enthalpy Rise Hot Channel WCAP-9272-P-A, "Westinghouse Reload Factor ( F ~ ~ ~ ) 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.

2.8 Axial Flux Difference (AFD) 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, I "Power Distribution Control Analysis," 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 2.1 1 RCS Pressure, Temperature, and WCAP-11397-P-A, "Revised Thermal Design Flow Departure from Nucleate Procedure," April 1989, for those events Boiling (DNB) Limits 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 2.12 Refueling Boron Concentration WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 Page 18 of 18