ML13133A070

Cycle 23 Core Operating Limits Report, Revision 1 and 2

ML13133A070
Person / Time
Site:	North Anna
Issue date:	05/07/2013
From:	Huber T Dominion, Dominion Resources Services
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13133A070 (45)

Text

Dominion Resources Services, Inc.

lnnsbrook Technical Center 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 FDominioln May 7, 2013 U. S. Nuclear Regulatory Commission Serial No.13-281 Attention: Document Control Desk NLOS/ETS One White Flint North Docket No. 50-339 11555 Rockville Pike License No. NPF-7 Rockville, MD 20852-2738 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STATION UNIT 2 CYCLE 23 CORE OPERATING LIMITS REPORT, REVISIONS 1 AND 2 Pursuant to North Anna Technical Specification 5.6.5.d, attached are copies of the Dominion Core Operating Limits Report for North Anna Unit 2 Cycle 23, Pattern BND, Revisions 1 and 2. Revision 1 was only applicable to operating Modes 6 and 5 with RCS Temperature less than 140 OF and the RCS vented. Revision 2 replaces Revision 1 and is applicable to all operating Modes.

If you have any questions regarding this submittal, please contact Mr. Thomas Shaub at (804) 273-2763.

Sincerely, T. R. Huber, Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc.

for Virginia Electric and Power Company Attachments:

1. Core Operating Limits Report for North Anna Unit 2 Cycle 23 - Pattern BND, Revision 1.

2. Core Operating Limits Report for North Anna Unit 2 Cycle 23 - Pattern BND, Revision 2.

Commitments made in this letter: None

Serial No.13-281 Docket No. 50-339 Cycle 23 - Pattern BND COLR Page 2 of 2 cc: U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 Mr. J. E. Reasor, Jr.

Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.

Suite 300 Glen Allen, Virginia 23060 NRC Senior Resident Inspector North Anna Power Station Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, Maryland 20852-2738

Serial No.13-281 Docket No. 50-339 ATTACHMENT 1 CORE OPERATING LIMITS REPORT FOR NORTH ANNA UNIT 2 CYCLE 23 PATTERN BND, REVISION I

• • • OPERATING MODES 6 and 5 with RCS Temperature < 140 OF, RCS Vented ONLY*** I NORTH ANNA POWER STATION VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 N2C23 CORE OPERATING LIMITS REPORT

[***OPERATING MODES 6 and 5 with RCS Temperature < 140 °F, RCS Vented ONLY***

The Core Operating Limits Report (COLR) for North Anna Unit 2 Cycle 23 has been prepared in accordance with North Anna Technical Specification 5.6.5. This COLR is only applicable to MODES 5 (at RCS Temperature less than 140 OF, RCS vented) and 6 of operation. A COLR applicable to all MODES of operation will be issued concurrently with a Reload Safety Evaluation supporting all MODES of operation.

The technical specifications affected by this report are listed below. TS items which are not applicable in MODES 5 (at RCS Temperature less than 140 OF, RCS vented) and 6 are marked "Not Applicable":

Not Applicable: TS 2.1.1 Reactor Core Safety Limits TS 3.1.1 Shutdown Margin (SDM)

Not Applicable: TS 3.1.3 Moderator Temperature Coefficient (MTC)

Not Applicable: TS 3.1.4 Rod Group Alignment Limits Not Applicable: TS 3.1.5 Shutdown Bank Insertion Limit Not Applicable: TS 3.1.6 Control Bank Insertion Limits Not Applicable: TS 3.1.9 PHYSICS TESTS Exceptions - Mode 2 Not Applicable: TS 3.2.1 Heat Flux Hot Channel Factor Not Applicable: TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNAH)

Not Applicable: TS 3.2.3 Axial Flux Difference (AFD)

Not Applicable: TS 3.3.1 Reactor Trip System (RTS) Instrumentation Not Applicable: TS 3.4.1 RCS Pressure, Temperature, and Flow DNB Limits Not Applicable: TS 3.5.6 Boron Injection Tank (BIT)

TS 3.9.1 Boron Concentration In addition, a technical requirement (TR) in the NAPS Technical Requirements Manual (TRM) refers to the COLR:

Not Applicable: TR 3.1.1 Boration Flow Paths - Operating The analytical methods used to determine the core operating limits are those previously approved by the NRC and discussed in the documents listed in the References Section.

Cycle-specific values are presented in bold. Text in italics is provided for information only.

Page 1 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 REFERENCES

1. VEP-FRD-42, Rev. 2.1-A, "Reload Nuclear Design Methodology," August 2003.

Methodology for:

TS 3.1.1 - Shutdown Margin, Not Applicable: TS 3.1.3 - Moderator Temperature Coefficient, Not Applicable: TS 3.1.4 - Rod Group Alignment Limits Not Applicable: TS 3.1.5 - Shutdown Bank Insertion Limit, Not Applicable: TS 3.1.6 - Control Bank Insertion Limits, Not Applicable: TS 3.1.9 - Physics Tests Exceptions - Mode 2, Not Applicable: TS 3.2.1 - Heat Flux Hot Channel Factor, Not Applicable: TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor Not Applicable: TS 3.5.6 - Boron Injection Tank (BIT) and TS 3.9.1 - Boron Concentration

2. Plant-specific adaptation of WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM),"

as approved by NRC Safety Evaluation Report dated February 29, 2012.

Not Applicable: Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor

3. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.

Not Applicable: Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor

4. WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code," August 1985.

Not Applicable: Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor

5. WCAP- 126 10-P-A, "VANTAGE+ FUEL ASSEMBLY - REFERENCE CORE REPORT,"

April 1995.

Methodology for:

Not Applicable: TS 2.1.1 - Reactor Core Safety Limits Not Applicable: TS 3.2.1 - Heat Flux Hot Channel Factor

6. VEP-NE-2, Rev. 0-A, Statistical DNBR Evaluation Methodology, June 1987.

Methodology for:

Not Applicable: TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor and Not Applicable: TS 3.4.1 - RCS Pressure, Temperature and Flow DNB Limits Page 2 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1

7. VEP-NE- 1, Rev. 0. 1-A, Relaxed Power Distribution Control Methodology and Associated FQ Surveillance Technical Specifications, August 2003.

Methodology for:

Not Applicable: TS 3.2.1 - Heat Flux Hot Channel Factor and Not Applicable: TS 3.2.3 - Axial Flux Difference

8. WCAP-8745-P-A, Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions, September 1986.

Methodology for:

Not Applicable: TS 2.1.1 - Reactor Core Safety Limits and Not Applicable: TS 3.3.1 - Reactor Trip System Instrumentation

9. WCAP-14483-A, Generic Methodology for Expanded Core Operating Limits Report, January 1999.

Methodology for:

Not Applicable: TS 2.1.1 - Reactor Core Safety Limits, TS 3.1.1 - Shutdown Margin, Not Applicable: TS 3.1.4 - Rod Group Alignment Limits Not Applicable: TS 3.1.9 - Physics Tests Exceptions - Mode 2 Not Applicable: TS 3.3.1 - Reactor Trip System Instrumentation, Not Applicable: TS 3.4.1 - RCS Pressure, Temperature, and Flow DNB Limits Not Applicable: TS 3.5.6 - Boron Injection Tank (BIT) and TS 3.9.1 - Boron Concentration

10. BAW-10227P-A, Rev. 0, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel," February 2000.

Methodology for:

Not Applicable: TS 2.1.1 - Reactor Core Safety Limits and Not Applicable: TS 3.2.1 - Heat Flux Hot Channel Factor

11. EMF-2103 (P) (A), Rev. 0, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," April 2003.

Not Applicable: Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor

12. EMF-96-029 (P) (A), Rev. 0, "Reactor Analysis System for PWRs," January 1997.

Not Applicable: Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor

13. BAW- 10168P-A, Rev. 3, "RSG LOCA - BWNT Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," December 1996. Volume II only (SBLOCA models).

Not Applicable: Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor Page 3 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1

14. DOM-NAF-2, Rev. 0.2- P-A, "Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code," including Appendix A, "Qualification of the F-ANP BWU CHF Correlations in the Dominion VIPRE-D Computer Code," and Appendix C, "Qualification of the Westinghouse WRB-2M CHF Correlation in the Dominion VIPRE-D Computer Code,"

August 2010.

Methodology for:

Not Applicable: TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor and Not Applicable: TS 3.4.1 - RCS Pressure, Temperature and Flow DNB Limits

15. WCAP- 12610-P-A and CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLOTM, July 2006.

Methodology for:

Not Applicable: TS 2.1.1 - Reactor Core Safety Limits and Not Applicable: TS 3.2.1 - Heat Flux Hot Channel Factor Note: The North Anna COLR lists multiple methodologies that are used to verify Technical Specificationsparameters. This is due to the transitionfrom AREVA fuel to Westinghousefuel which requires the use ofdifferent vendor proprietarymethodologies to verify the two fuel products meet the applicableregulatorylimits.

Page 4 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in COLR Figure 2.1-1; and the following SLs shall not be exceeded.

Not Applicable: 2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained greater than or equal to the 95/95 DNBR criterion for the DNB correlations and methodologies specified in the References Section.

Not Applicable: 2.1.1.2 The peak fuel centerline temperature shall be maintained <

5080'F, decreasing by 58°F per 10,000 MWD/MTU of burnup, for Westinghouse fuel and < 51730 F, decreasing by 65°F per 10,000 MWD/MTU of burnup, for AREVA fuel.

Page 5 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 COLR Figure 2.1-1 Not Applicable Page 6 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.1 SDM shall be_ 1.77 % Ak/k.

3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.3 The MTC shall be maintained within the limits specified below. The upper limit of MTC is NOT APPLICABLE, when < 70% RTP, and NOT APPLICABLE when >

70% RTP.

The BOC/ARO-MTC shall be _<NOT APPLICABLE (upper limit), when < 70%

RTP, and < NOT APPLICABLE when > 70% RTP.

The EOC/ARO/RTP-MTC shall be less negative than NOT APPLICABLE (lower limit).

The MTC surveillance limits are:

The 300 ppm/ARO/RTP-MTC should be less negative than or equal to NOT APPLICABLE [Note 2].

The 60 ppm/ARO/RTP-MTC should be less negative than or equal to NOT APPLICABLE [Note 3].

SR 3.1.3.2 Verify MTC is within NOT APPLICABLE (lower limit).

Note 2: If the MTC is more negative than NOT APPLICABLE, SR 3.1.3.2 shall be repeated once per 14 EFPD during the remainder of the fuel cycle.

Note 3: SR 3.1.3.2 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of < 60 ppm is less negative than NOT APPLICABLE.

3.1.4 Rod Group Alignment Limits Required Action A. 1.1 Verify SDM to be > NOT APPLICABLE.

Required Action B. 1.1 Verify SDM to be > NOT APPLICABLE.

Required Action D. 1.1 Verify SDM to be > NOT APPLICABLE.

Page 7 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.5 Each shutdown bank shall be withdrawn to at least NOT APPLICABLE steps.

Required Action A. 1.1 Verify SDM to be > NOT APPLICABLE.

Required Action B. 1 Verify SDM to be > NOT APPLICABLE.

SR 3.1.5.1 Verify each shutdown bank is withdrawn to at least NOT APPLICABLE steps.

3.1.6 Control Bank Insertion Limits LCO 3.1.6 Control banks shall be limited in physical insertion as shown in COLR Figure 3.1-1.

Sequence of withdrawal shall be A, B, C and D, in that order; and the overlap limit during withdrawal shall be NOT APPLICABLE steps.

Required Action A. 1.1 Verify SDM to be > NOT APPLICABLE.

Required Action B. 1.1 Verify SDM to be > NOT APPLICABLE.

Required Action C. 1 Verify SDM to be > NOT APPLICABLE.

SR 3.1.6.1 Verify estimated critical control bank position is within the insertion limits specified in COLR Figure 3.1-1.

SR 3.1.6.2 Verify each control bank is within the insertion limits specified in COLR Figure 3.1-1.

SR 3.1.6.3 Verify each control bank not fully withdrawn from the core is within the sequence and overlap limits specified in LCO 3.1.6 above.

3.1.9 PHYSICS TESTS Exceptions - MODE 2 LCO 3.1.9.b SDM is > NOT APPLICABLE.

SR 3.1.9.4 Verify SDM to be > NOT APPLICABLE.

Page 8 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 COLR Figure 3.1-1 NOT APPLICABLE Page 9 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

LCO 3.2.1 FQ(Z), as approximated by FQM(Z), shall be within the limits specified below.

CFQ = NOT APPLICABLE The Measured Heat Flux Hot Channel Factor, FQM(Z), shall be limited by the following relationships:

CFQ K(Z)

FA (Z) < P- -

N(Z) for P>0.5 CFQ K(Z)

FQ (Z) < for P:0.5 0.5 N(Z) where: P= THERMAL POWER and RATED THERMAL POWER' K(Z) is provided in COLR Figure 3.2-1.

N(Z) is a cycle-specific non-equilibrium multiplier on FQM(Z) to account for power distribution transients during normal operation, provided in COLR Table 3.2-1.

The discussion in the Bases Section B 3.2. 1for this LCO requires the applicationof a cycle dependent non-equilibriummultiplier,N(Z), to the CFQ limit. N(Z) accountsfor power distributiontransientsencountered duringnormaloperation.As function N(Z) is dependent on the predictedequilibrium FQ(Z) andis sensitive to the axialpower distribution,it is typically generatedfrom the actualEOC burnup distributionthat can only be obtainedafter the shutdown of the previous cycle. The cycle-specific N(Z)function is presentedin COLR Table 3.2-1.

Page 10 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 COLR Table 3.2-1 NOT APPLICABLE N(z) data will be provided in a revision of the COLR.

These decks are generated for normal operation flux maps that are typically taken at full power ARO.

Additional N(z) decks may be generated, if necessary, consistent with the methodology described in the RPDC topical (Reference 7). EOR is defined as Hot Full Power End of Reactivity.

Page 11 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 COLR Figure 3.2-1 NOT APPLICABLE Page 12 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 tN 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F NAH)

LCO 3.2.2 F NAH shall be within the limits specified below.

FN < NOT APPLICABLE where: P THERMAL POWER RATED THERMAL POWER SR 3.2.2.1 Verify FN AH is within limits specified above.

3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.3 The AFD in % flux difference units shall be maintained within the limits specified in COLR Figure 3.2-2.

Page 13 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. I COLR Figure 3.2-2 NOT APPLICABLE Page 14 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation TS Table 3.3.1-1 Note 1: Overtemperature AT The Overtemperature AT Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2% of AT span, with the numerical values of the parameters as specified below.

AT<* ATo{ K-K,_(I TJ) [T-T']+K3 (P-P')-f (AJ)}

where: AT is measured RCS AT, °F ATo is the indicated AT at RTP, OF is the Laplace transform operator, sec-T is the measured RCS average temperature, OF T' is the nominal Tavg at RTP, <NOT APPLICABLE P is the measured pressurizer pressure, psig p, is the nominal RCS operating pressure, >_NOT APPLICABLE Kl* N OT APPLICABLE K2 > NOT APPLICABLE K 3 - NOT APPLICABLE rT, r2 = time constants utilized in the lead-lag controllerfbr T"vg 1l _>NOT APPLICABLE T2 _5 NOT APPLICABLE (1 + rzs)/(1 + r2s) = function generated by the lead-lag controllerfor Tavg dynamic compensation fl(AI) > NOT APPLICABLE {NOT APPLICABLE - (qt - qb)}

when (qt - qb) < NOT APPLICABLE RTP NOT APPLICABLE when NOT APPLICABLE RTP <-(qt - qb) - NOT APPLICABLE RTP NOT APPLICABLE ((qt - qb) - NOT APPLICABLE}

when (qt - qb) > NOT APPLICABLE RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.

Page 15 of 20

Serial No.13-281 Docket No, 50-339 NAPS2 COLR Pattern BND Rev. 1 TS Table 3.3.1-1 Note 2: Overpower AT The Overpower AT Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2% of AT span, with the numerical values of the parameters as specified below.

AT ATO {K 4 -K 5 [ '-2S 3 ]T-K 6 [T-T' ]-f 2 (A1)}

where: AT is measured RCS AT, OF.

AT 0 is the indicated AT at RTP, OF.

S is the Laplace transform operator, sec- .

T is the measured RCS average temperature, OF.

T' is the nominal Tavg at RTP, <NOT APPLICABLE.

K4_: NOT APPLICABLE K5 > NOT APPLICABLE for increasing Tavg K6 - NOT APPLICABLE /`F when T > T' NOT APPLICABLE for decreasing Tavg NOT APPLICABLE when T < T' 7

z-= time constant utilized in the rate lag controllerfor ',g T3 NOT APPLICABLE r3s/(1 + r3s) = function generated by the rate lag controllerfor Tg dynamic compensation f 2(AI) = NOT APPLICABLE Page 16 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:

a. Pressurizer pressure is greater than or equal to NOT APPLICABLE

b. RCS average temperature is less than or equal to NOT APPLICABLE; and

c. RCS total flow rate is greater than or equal to NOT APPLICABLE.

SR 3.4.1.1 Verify pressurizer pressure is greater than or equal to NOT APPLICABLE.

SR 3.4.1.2 Verify RCS average temperature is less than or equal to NOT APPLICABLE.

SR 3.4.1.3 Verify RCS total flow rate is greater than or equal to NOT APPLICABLE.

SR 3.4.1.4 ------------------------ NOTE --------------------

Not required to be performed until 30 days after > 90% RTP.

Verify by precision heat balance that RCS total flow rate is _>NOT APPLICABLE Page 17 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.6 Boron Injection Tank (BIT)

Required Action B.2 Borate to a SDM > NOT APPLICABLE.

Page 18 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System (RCS), the refueling canal, and the refueling cavity shall be maintained > 2600 ppm.

SR 3.9.1.1 Verify boron concentration is within the limit specified above.

Page 19 of 20

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 1 NAPS TECHNICAL REQUIREMENTS MANUAL TRM 3.1 REACTIVITY CONTROL SYSTEMS TR 3.1.1 Boration Flow Paths - Operating Required Action D.2 Borate to a SHUTDOWN MARGIN > NOT APPLICABLE after xenon decay.

Page 20 of 20

Serial No.13-281 Docket No. 50-33 ATTACHMENT 2 CORE OPERATING LIMITS REPORT FOR NORTH ANNA UNIT 2 CYCLE 23 PATTERN BND, REVISION 2 NORTH ANNA POWER STATION VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 N2C23 CORE OPERATING LIMITS REPORT INTRODUCTION The Core Operating Limits Report (COLR) for North Anna Unit 2 Cycle 23 has been prepared in accordance with North Anna Technical Specification 5.6.5. The technical specifications affected by this report are listed below:

TS 2.1.1 Reactor Core Safety Limits TS 3.1.1 Shutdown Margin (SDM)

TS 3.1.3 Moderator Temperature Coefficient (MTC)

TS 3.1.4 Rod Group Alignment Limits TS 3.1.5 Shutdown Bank Insertion Limit TS 3.1.6 Control Bank Insertion Limits TS 3.1.9 PHYSICS TESTS Exceptions - Mode 2 TS 3.2.1 Heat Flux Hot Channel Factor TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F NAH)

TS 3.2.3 Axial Flux Difference (AFD)

TS 3.3.1 Reactor Trip System (RTS) Instrumentation TS 3.4.1 RCS Pressure, Temperature, and Flow DNB Limits TS 3.5.6 Boron Injection Tank (BIT)

TS 3.9.1 Boron Concentration In addition, a technical requirement (TR) in the NAPS Technical Requirements Manual (TRM) refers to the COLR:

TR 3.1.1 Boration Flow Paths - Operating The analytical methods used to determine the core operating limits are those previously approved by the NRC and discussed in the documents listed in the References Section.

Cycle-specific values are presented in bold. Text in italics is provided for information only.

Page 1 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 REFERENCES

1. VEP-FRD-42, Rev. 2.1-A, "Reload Nuclear Design Methodology," August 2003.

Methodology for:

TS 3.1.1 - Shutdown Margin, TS 3.1.3 - Moderator Temperature Coefficient, TS 3.1.4 - Rod Group Alignment Limits TS 3.1.5 - Shutdown Bank Insertion Limit, TS 3.1.6 - Control Bank Insertion Limits, TS 3.1.9 - Physics Tests Exceptions - Mode 2, TS 3.2.1 - Heat Flux Hot Channel Factor, TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor TS 3.5.6 - Boron Injection Tank (BIT) and TS 3.9.1 - Boron Concentration

2. Plant-specific adaptation of WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," as approved by NRC Safety Evaluation Report dated February 29, 2012.

Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor

3. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.

Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor

4. WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code," August 1985.

Methodology for: TS 3.21 - Heat Flux Hot Channel Factor

5. WCAP-126 10-P-A, "VANTAGE+ FUEL ASSEMBLY - REFERENCE CORE REPORT,"

April 1995.

Methodology for:

TS 2.1.1 - Reactor Core Safety Limits TS 3.2.1 - Heat Flux Hot Channel Factor

6. VEP-NE-2, Rev. 0-A, Statistical DNBR Evaluation Methodology, June 1987.

Methodology for:

TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor and TS 3.4.1 - RCS Pressure, Temperature and Flow DNB Limits Page 2 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2

7. VEP-NE-1, Rev. 0.1-A, Relaxed Power Distribution Control Methodology and Associated FQ Surveillance Technical Specifications, August 2003.

Methodology for:

TS 3.2.1 - Heat Flux Hot Channel Factor and TS 3.2.3 - Axial Flux Difference

8. WCAP-8745-P-A, Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions, September 1986.

Methodology for:

TS 2.1.1 - Reactor Core Safety Limits and TS 3.3.1 - Reactor Trip System Instrumentation

9. WCAP-14483-A, Generic Methodology for Expanded Core Operating Limits Report, January 1999.

Methodology for:

TS 2.1.1 - Reactor Core Safety Limits, TS 3.1.1 - Shutdown Margin, TS 3.1.4 - Rod Group Alignment Limits TS 3.1.9 - Physics Tests Exceptions - Mode 2 TS 3.3.1 - Reactor Trip System Instrumentation, TS 3.4.1 - RCS Pressure, Temperature, and Flow DNB Limits TS 3.5.6 - Boron Injection Tank (BIT) and TS 3.9.1 - Boron Concentration

10. BAW- 10227P-A, Rev. 0, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel," February 2000.

Methodology for:

TS 2.1.1 - Reactor Core Safety Limits and TS 3.2.1 - Heat Flux Hot Channel Factor

11. EMF-2103 (P) (A), Rev. 0, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," April 2003.

Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor

12. EMF-96-029 (P) (A), Rev. 0, "Reactor Analysis System for PWRs," January 1997.

Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor

13. BAW- 10168P-A, Rev. 3, "RSG LOCA - BWNT Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," December 1996. Volume II only (SBLOCA models).

Methodology for: TS 3.2.1 - Heat Flux Hot Channel Factor Page 3 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2

14. DOM-NAF-2, Rev. 0.2-P-A, "Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code," including Appendix A, "Qualification of the F-ANP BWU CHF Correlations in the Dominion VIPRE-D Computer Code," and Appendix C, "Qualification of the Westinghouse WRB-2M CHF Correlation in the Dominion VIPRE-D Computer Code," August 2010.

Methodology for:

TS 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor and TS 3.4.1 - RCS Pressure, Temperature and Flow DNB Limits

15. WCAP- 12610-P-A and CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLOTM, July 2006.

Methodology for:

TS 2.1.1 - Reactor Core Safety Limits and TS 3.2.1 - Heat Flux Hot Channel Factor Note: The North Anna COLR lists multiple methodologies that are used to verify Technical Specificationsparameters.This is due to the transitionfrom AREVA fuel to Westinghousefuel which requires the use of different vendor proprietary methodologies to verify the two fuel products meet the applicable regulatorylimits.

Page 4 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in COLR Figure 2.1-1; and the following SLs shall not be exceeded.

2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained greater than or equal to the 95/95 DNBR criterion for the DNB correlations and methodologies specified in the References Section.

2.1.1.2 The peak fuel centerline temperature shall be maintained < 5080 0 F, decreasing by 58°F per 10,000 MWD/MTU of bumup, for Westinghouse fuel and < 5173'F, decreasing by 65 0 F per 10,000 MWD/MTU of burnup, for AREVA fuel.

Page 5 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 COLR Figure 2.1-1 NORTH ANNA REACTOR CORE SAFETY LIMITS 665 660 655 650 645 640 635 630 625 CL E 620 to 615 I- 610 605 600 595 590 585 580 575 570 0 10 20 30 40 50 60 70 80 90 100 110 120 Percent of RATED THERMAL POWER Page 6 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.1 SDM shall be > 1.77 % Ak/k.

3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.3 The MTC shall be maintained within the limits specified below. The upper limit of MTC is +0.6 x 10-4 Alk/°F, when < 70% RTP, and 0.0 Ak/k/°F when _>70%

RTP.

The BOC/ARO-MTC shall be < +0.6 x 10-4 Ak/k/0 F (upper limit), when < 70%

RTP, and <0.0 Alk/kF when Ž70% RTP.

The EOC/ARO/RTP-MTC shall be less negative than -5.0 x 10-4 Ak/k/°F (lower limit).

The MTC surveillance limits are:

The 300 ppm/ARO/RTP-MTC should be less negative than or equal to

-4.0 x 104 Ak/k/0 F [Note 2].

The 60 ppm/ARO/RTP-MTC should be less negative than or equal to

-4.7 x 104 Ak/k/0 F [Note 3].

SR 3.1.3.2 Verify MTC is within -5.0 x 104 Ak/k/ 0 F (lower limit).

Note 2: If the MTC is more negative than -4.0 x 10-4 Akk/kF, SR 3.1.3.2 shall be repeated once per 14 EFPD during the remainder of the fuel cycle.

Note 3: SR 3.1.3.2 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of < 60 ppm is less negative than -4.7 x 10-4 Ak/k/0 F.

3.1.4 Rod Group Alignment Limits Required Action A. 1.1 Verify SDM to be > 1.77 % Ak/k.

Required Action B. 1.1 Verify SDM to be > 1.77 % Ak/k.

Required Action D. 1.1 Verify SDM to be > 1.77 % Ak/k.

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Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.5 Each shutdown bank shall be withdrawn to at least 230 steps.

Required Action A. 1.1 Verify SDM to be >_1.77 % Ak/k.

Required Action B. 1 Verify SDM to be __1.77 % Ak/k.

SR 3.1.5.1 Verify each shutdown bank is withdrawn to at least 230 steps.

3.1.6 Control Bank Insertion Limits LCO 3.1.6 Control banks shall be limited in physical insertion as shown in COLR Figure 3.1-1. Sequence of withdrawal shall be A, B, C and D, in that order; and the overlap limit during withdrawal shall be 102 steps.

Required Action A. 1.1 Verify SDM to be > 1.77 % Ak/k.

Required Action B. 1.1 Verify SDM to be > 1.77 % Ak/k.

Required Action C. 1 Verify SDM to be _ 1.77 % Ak/k.

SR 3.1.6.1 Verify estimated critical control bank position is within the insertion limits specified in COLR Figure 3.1-1.

SR 3.1.6.2 Verify each control bank is within the insertion limits specified in COLR Figure 3.1-1.

SR 3.1.6.3 Verify each control bank not fully withdrawn from the core is within the sequence and overlap limits specified in LCO 3.1.6 above.

3.1.9 PHYSICS TESTS Exceptions - MODE 2 LCO 3.1.9.b SDM is _>1.77 % Ak/k.

SR 3.1.9.4 Verify SDM to be >_1.77 % Ak/k.

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Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 COLR Figure 3.1-1 North Anna 2 Cycle 23 Control Rod Bank Insertion Limits 230 220 210 200 190 180 170 4A

0. 160 150 140 0.w W.130 0

I..

120 0

0*

110 100 90 80 70 60 50 40 30 20 10 0

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of Rated Thermal Power Page 9 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

LCO 3.2.1 FQ(Z), as approximated by FQM(Z), shall be within the limits specified below.

CFQ = 2.32 The Measured Heat Flux Hot Channel Factor, FQM(Z), shall be limited by the following relationships:

CFQ K(Z)

FN((Z)QP< N(Z) for P>0.5 CFQ K(Z)

F* (Z)<for P<0.5 0.5 N(Z)

THERMAL POWER where: P = RATED THERMAL POWER ; and K(Z) is provided in COLR Figure 3.2-1.

N(Z) is a cycle-specific non-equilibrium multiplier on FQM(Z) to account for power distribution transients during normal operation, provided in COLR Table 3.2-1.

The discussion in the Bases Section B 3.2.1]for this LCO requires the applicationof a cycle dependent non-equilibriummultiplier,N(Z), to the CFQ limit. N(Z) accountsfor power distributiontransientsencountered duringnormal operation.Asffunction N(Z) is dependent on the predicted equilibriumFQ(Z) and is sensitive to the axialpower distribution,it is typically generatedfrom the actualEOC burnup distributionthat can only be obtainedafter the shutdown of the previous cycle. The cycle-specific N(Z)function is presented in COLR Table 3.2-1.

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Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 COLR Table 3.2-1 N2C23 Normal Operation N(Z)

NODE HEIGHT 0 to 1000 1000 to 3000 3000 to 5000 5000 to 7000 7000 to 9000 (FEET) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 10 10.2 1.115 1.106 1.114 1.119 1.134 11 10.0 1.114 1.107 1.113 1.117 1.131 12 9.8 1.112 1.115 1.118 1.118 1.128 13 9.6 1.112 1.126 1.126 1.123 1.125 14 9.4 1.113 1.131 1.131 1.123 1.121 15 9.2 1.119 1.135 1.135 1.127 1.125 16 9.0 1.128 1.145 1.144 1.143 1.141 17 8.8 1.138 1.153 1.153 1.160 1.160 18 8.6 1.144 1.156 1.155 1.168 1.168 19 8.4 1.148 1.156 1.157 1.174 1.174 20 8.2 1.154 1.156 1.161 1.182 1.182 21 8.0 1.157 1.156 1.165 1.187 1.186 22 7.8 1.159 1.158 1.168 1.189 1.189 23 7.6 1.159 1.159 1.170 1.189 1.188 24 7.4 1.158 1.158 1.171 1.188 1.188 25 7.2 1.155 1.155 1.171 1.187 1.188 26 7.0 1.151 1.151 1.169 1.186 1.189 27 6.8 1.150 1.150 1.169 1.184 1.190 28 6.6 1.147 1.147 1.167 1.179 1.190 29 6.4 1.140 1.140 1.163 1.171 1.189 30 6.2 1.130 1.130 1.156 1.159 1.186 31 6.0 1.124 1.124 1.152 1.151 1.186 32 5.8 1.119 1.119 1.142 1.143 1.180 33 5.6 1.112 1.111 1.122 1.134 1.167 34 5.4 1.107 1.107 1.107 1.128 1.152 35 5.2 1.104 1.104 1.105 1.124 1.146 36 5.0 1.104 1.108 1.110 1.122 1.137 37 4.8 1.104 1.115 1.115 1.118 1.122 38 4.6 1.106 1.122 1.122 1.118 1.115 39 4.4 1.109 1.126 1.126 1.120 1.118 40 4.2 1.112 1.131 1.131 1.121 1.121 41 4.0 1.118 1.136 1.136 1.122 1.125 42 3.8 1.127 1.140 1.141 1.121 1.131 43 3.6 1.138 1.145 1.146 1.121 1.138 44 3.4 1.147 1.147 1.148 1.125 1.143 45 3.2 1.156 1.152 1.150 1.132 1.145 46 3.0 1.167 1.161 1.150 1.137 1.145 47 2.8 1.179 1.175 1.154 1.144 1.146 48 2.6 1.192 1.189 1.163 1.150 1.147 49 2.4 1.206 1.203 1.174 1.159 1.154 50 2.2 1.220 1.213 1.183 1.172 1.169 51 2.0 1.233 1.223 1.192 1.182 1.179 52 1.8 1.241 1.233 1.201 1.188 1.181 These decks are generated for normal operation flux maps that are typically taken at full power ARO.

Additional N(z) decks may be generated, if necessary, consistent with the methodology described in the RPDC topical (Reference 7). EOR is defined as Hot Full Power End of Reactivity.

Page 11 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 COLR Table 3.2-1 (continued)

N2C23 Normal Operation N(Z)

NODE HEIGHT 9000 to 11000 11000 to 13000 13000 to 15000 15000 to 17000 17000 to EOR (FEET) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 10 10.2 1.134 1.115 1.115 1.115 1.079 11 10.0 1.131 1.114 1.114 1.114 1.091 12 9.8 1.128 1.118 1.115 1.112 1.099 13 9.6 1.128 1.127 1.120 1.112, 1.105 14 9.4 1.129 1.130 1.121 1.110 1.109 15 9.2 1.134 1.134 1.126 1.116 1.116 16 9.0 1.143 1.145 1.141 1.131 1.132 17 8.8 1.154 1.158 1.158 1.150 1.150 18 8.6 1.159 1.164 1.164 1.158 1.159 19 8.4 1.164 1.170 1.170 1.169 1.169 20 8.2 1.173 1.182 1.182 1.188 1.188 21 8.0 1.178 1.190 1.190 1.201 1.201 22 7.8 1.180 1.191 1.191 1.206 1.206 23 7.6 1.181 1.193 1.193 1.213 1.213 24 7.4 1.182 1.197 1.197 1.224 1.224 25 7.2 1.185 1.198 1.198 1.231 1.231 26 7.0 1.188 1.198 1.198 1.233 1.233 27 6.8 1.191 1.199 1.199 1.235 1.235 28 6.6 1.190 1.200 1.200 1.236 1.236 29 6.4 1.189 1.202 1.202 1.237 1.237 30 6.2 1.186 1.202 1.202 1.234 1.234 31 6.0 1.185 1.203 1.203 1.234 1.234 32 5.8 1.180 1.199 1.199 1.227 1.227 33 5.6 1.169 1.188 1.188 1.211 1.211 34 5.4 1.157 1.176 1.175 1.195 1.195 35 5.2 1.152 1.171 1.170 1.189 1.189 36 5.0 1.144 1.162 1.163 1.180 1.180 37 4.8 1.131 1.147 1.152 1.164 1.165 38 4.6 1.127 1.137 1.145 1.153 1.158 39 4.4 1.132 1.134 1.143 1.152 1.160 40 4.2 1.135 1.134 1.140 1.153 1.163 41 4.0 1.137 1.136 1.138 1.151 1.163 42 3.8 1.138 1.137 1.137 1.145 1.160 43 3.6 1.139 1.140 1.140 1.138 1.154 44 3.4 1.142 1.144 1.144 1.129 1.148 45 3.2 1.145 1.148 1.148 1.129 1.147 46 3.0 1.145 1.151 1.151 1.138 1.149 47 2.8 1.146 1.154 1.154 1.153 1.158 48 2.6 1.147 1.156 1.156 1.161 1.165 49 2.4 1.152 1.160 1.161 1.172 1.177 50 2.2 1.164 1.168 1.169 1.185 1.191 51 2.0 1.172 1.174 1.177 1.197 1.204 52 1.8 1.173 1.176 1.179 1.204 1.213 These decks are generated for normal operation flux maps that are typically taken at full power ARO.

Additional N(z) decks may be generated, if necessary, consistent with the methodology described in the RPDC topical (Reference 7). EOR is defined as Hot Full Power End of Reactivity.

Page 12 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 COLR Figure 3.2-1 K(Z) - Normalized FQ as a Function of Core Height 1.2 1.1 6, 1.0 1.0 0.9 (12 .925) 0.8 N

. 0.7 N

-j 4 0.6 0Z N

. 0.5 0.4 0.3 0.2 0.1 0.0 0 1 2 3 4 5 6 7 8 9 10 11 12 13 CORE HEIGHT (FT)

Page 13 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F NA)

LCO 3.2.2 FNAH shall be within the limits specified below.

F tNn _<1.587{1 + 0.3(1 - P)}

THERMAL POWER RATED THERMAL POWER SR 3.2.2.1 Verify FN AH is within limits specified above.

3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.3 The AFD in % flux difference units shall be maintained within the limits specified in COLR Figure 3.2-2.

Page 14 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 COLR Figure 3.2-2 North Anna 2 Cycle 23 Axial Flux Difference Limits 120 110o

(-12, 100) (+6, 100) 100 Unaccep able Opera ion Un ccep able 90 perat ion S80 _

0 C. Ac cepta le Op ration m 70 60

• 050 _

(-27, 50) (+20, 50) 0.40 30 20 10 0

-30 -20 -10 0 10 20 30 Percent Flux Difference (Delta-I)

Page 15 of 2l

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation TS Table 3.3.1-1 Note 1: Overtemperature AT The Overtemperature AT Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2% of AT span, with the numerical values of the parameters as specified below.

AT<*ATo KI -K* [fr)s)1 where: AT is measured RCS AT, °F ATo is the indicated AT at RTP, °F s is the Laplace transform operator, sec' T is the measured RCS average temperature, OF T'

is the nominal Tavg at RTP, _< 586.8 OF P is the measured pressurizer pressure, psig p1 is the nominal RCS operating pressure, > 2235 psig K _<1.2715 K2 >-0.02174 /OF K3 ->0.001145 /psig zl, r2 = time constants utilized in the lead-lag controllerfor Tavg

-tl > 23.75 sec ;2 -<4.4 sec (1 + rs)/(1J + r2s) = function generatedby the lead-lag controllerfor Tavg dynamic compensation f1(AI) >_0.0291{-13.0 - (qt - qb)} when (qt - qb) < -13.0% RTP 0 when -13.0% RTP < (qt - qb) < +7.0% RTP 0.0251 {(qt - qb) - 7.0} when (qt - qb) > +7.0% RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.

Page 16 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 TS Table 3.3.1-1 Note 2: Overpower AT The Overpower AT Function Allowable Value shall not exceed the following nominal trip setpoint by more than 2% of AT span, with the numerical values of the parameters as specified below.

ATýATb {K 4 -K 5 [ 21 1T-K 6[T-T']-f 2 (AI) where: AT is measured RCS AT, °F.

AT0 is the indicated AT at RTP, OF.

s is the Laplace transform operator, sec-1 .

T is the measured RCS average temperature, °F.

T' is the nominal Tavg at RTP, <586.8 OF.

K4__ 1.0865 K5 >! 0.0198 /0 Ffor increasing Tavg K 6 Ž 0.00 162 /OF when T > T' 0 /OF for decreasing Tavg 0 /OF when T _<T' r3 = time constant utilized in the rate lag controllerfor Tm,g T3 > 9.5 sec r3s/(1 + r3s) = function generatedby the rate lag controllerfor T~vg dynamic compensation f 2(AI) = 0, for all Al.

Page 17 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:

a. Pressurizer pressure is greater than or equal to 2205 psig;

b. RCS average temperature is less than or equal to 591 IF; and

c. RCS total flow rate is greater than or equal to 295,000 gpm.

SR 3.4.1.1 Verify pressurizer pressure is greater than or equal to 2205 psig.

SR 3.4.1.2 Verify RCS average temperature is less than or equal to 591 OF.

SR 3.4.1.3 Verify RCS total flow rate is greater than or equal to 295,000 gpm.

SR 3.4.1.4 ----------------------- NOTE -------------------------

Not required to be performed until 30 days after:>__ 90% RTP.

Verify by precision heat balance that RCS total flow rate is > 295,000 gpm.

Page 18 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.6 Boron Injection Tank (BIT)

Required Action B.2 Borate to a SDM > 1.77 % Ak/k at 200 OF.

Page 19 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System (RCS), the refueling canal, and the refueling cavity shall be maintained > 2600 ppm.

SR 3.9.1.1 Verify boron concentration is within the limit specified above.

Page 20 of 21

Serial No.13-281 Docket No. 50-339 NAPS2 COLR Pattern BND Rev. 2 NAPS TECHNICAL REQUIREMENTS MANUAL TRM 3.1 REACTIVITY CONTROL SYSTEMS TR 3.1.1 Boration Flow Paths - Operating Required Action D.2 Borate to a SHUTDOWN MARGIN > 1.77 % Akdk at 200 OF, after xenon decay.

Page 21 of 21