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Document Control Desk NSS&LIMLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 CORRECTION TO PREVIOUSLY SUBMITTED CORRESPONDANCE FOR CYCLE 14 CORE OPERATING LIMITS REPORT The-purpose of this letter is to correct an error that was inadvertently introduced to the docket for Millstone"Power Station Unit 3 (MPS3). On May 6, 2010, Dominion Nuclear...Connecticut, Inc. (DNC),submitted the Core Operating Limits Report (COLR) for MPS3 Cycle 14. On June 22, 2010, while referencing the electronic version of the MPS3 Technical Requirements Manual (TRM), DNC discovered that Figure 7 of the COLR (Page 8.1-16) contained a duplicatecopy of the graph contained in Figure 8 (Page 8.1-17). This error was introduced during electronic publishing of the TRM change for the Cycle 14 COLR, which has since been corrected.
Document Control Desk NSS&LIMLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 CORRECTION TO PREVIOUSLY SUBMITTED CORRESPONDANCE FOR CYCLE 14 CORE OPERATING LIMITS REPORT The-purpose of this letter is to correct an error that was inadvertently introduced to the docket for Millstone"Power Station Unit 3 (MPS3). On May 6, 2010, Dominion Nuclear...Connecticut, Inc. (DNC),submitted the Core Operating Limits Report (COLR) for MPS3 Cycle 14. On June 22, 2010, while referencing the electronic version of the MPS3 Technical Requirements Manual (TRM), DNC discovered that Figure 7 of the COLR (Page 8.1-16) contained a duplicatecopy of the graph contained in Figure 8 (Page 8.1-17). This error was introduced during electronic publishing of the TRM change for the Cycle 14 COLR, which has since been corrected.
Controlled hard copies of the TRM, including control room copies, were not affected by this error. -Enclosure I contains the corrected version of the MPS3 Cycle 14 COLR.We apologize for any inconvenience this may have caused.-If you have any questions or require additional information, please contact Mr. William D.-Bartron at (860) 444-4301.Sincerely, S e rden SiteV~ ne Peident;-
Controlled hard copies of the TRM, including control room copies, were not affected by this error. -Enclosure I contains the corrected version of the MPS3 Cycle 14 COLR.We apologize for any inconvenience this may have caused.-If you have any questions or require additional information, please contact Mr. William D.-Bartron at (860) 444-4301.Sincerely, S e rden SiteV~ ne Peident;-
M~illstone-Serial No. 10-287A'Docket No. 50-423 , ,Correction to Cycle 14.COLR Page 2 of 2 Epdloures:  
M~illstone-Serial No. 10-287A'Docket No. 50-423 , ,Correction to Cycle 14.COLR Page 2 of 2 Epdloures:
(1)Commitmebts Made in this letter: 'None.,cc: U.S. Nuc'learRegulatory-Comhrission Region I 475 Allendale Road ,King of Prussia, PA 194,06-J 4 15 Ms. C., J.-Sanders NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail'Stop 8B3 11555 Rockville Pike Rockville, MD .20852:2738 NRC Senior Resident Inspector'Millstone Power-Station SSeral.No. 287A Doc-ket'No.
(1)Commitmebts Made in this letter: 'None.,cc: U.S. Nuc'learRegulatory-Comhrission Region I 475 Allendale Road ,King of Prussia, PA 194,06-J 4 15 Ms. C., J.-Sanders NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail'Stop 8B3 11555 Rockville Pike Rockville, MD .20852:2738 NRC Senior Resident Inspector'Millstone Power-Station SSeral.No. 287A Doc-ket'No.
50-423 ENCLOSURE 1 CORE OPERATING LIMITS REPORT, CYCLE 14 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 TECHNICAL REQUIREMENTS MANUAL ,APPENDIX 8.1::,,CORE OPERATINGJLIMITS'REPORT
50-423 ENCLOSURE 1 CORE OPERATING LIMITS REPORT, CYCLE 14 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 TECHNICAL REQUIREMENTS MANUAL ,APPENDIX 8.1::,,CORE OPERATINGJLIMITS'REPORT
Line 37: Line 37:
3./4.1.1.3 3/4.1.3:5 3/4.1.3.6 3/14.2.1.1 3/4.2.2.1 3/4.2.3.1 3/4.2.5 3/4.3.5 3/.4.9.1.1 SafetyLimits Limiting Safety System Settings Shutdown.Margin  
3./4.1.1.3 3/4.1.3:5 3/4.1.3.6 3/14.2.1.1 3/4.2.2.1 3/4.2.3.1 3/4.2.5 3/4.3.5 3/.4.9.1.1 SafetyLimits Limiting Safety System Settings Shutdown.Margin  
-MODE 1 and 2 Shutdown Margin -MODES 3,4 and5 Loops Filled ShutdownMargin  
-MODE 1 and 2 Shutdown Margin -MODES 3,4 and5 Loops Filled ShutdownMargin  
-MODE-5 LoopsNot Filled Moderator Temperature Coefficient Shutdown Rod Insertion Limit ControlRod Insertion Limits Axial Flux Difference Heat Flux Hot Channel Factor RCS Total Flow Rate and'NuclearEnthalpy Rise Hot Channel Factor DNB Parameters Shutdown Margin Monitor Alarm Setpoint Refueling Boron Concentration
-MODE-5 LoopsNot Filled Moderator Temperature Coefficient Shutdown Rod Insertion Limit ControlRod Insertion Limits Axial Flux Difference Heat Flux Hot Channel Factor RCS Total Flow Rate and'NuclearEnthalpy Rise Hot Channel Factor DNB Parameters Shutdown Margin Monitor Alarm Setpoint Refueling Boron Concentration 2.0 Operating Limits The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections.
 
===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 6.9.1.6.b.
These limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.9.1.6.b.
2.1 Safety-Limits (Specification 2.1.1)2.1.1 Reactor Core The combination of THERMAL POWER, Reactor Coolant System highest loop average temperature, and pressurizer pressure shall not exceed the limits shown in..Figure .1.0 MILLSTONE  
2.1 Safety-Limits (Specification 2.1.1)2.1.1 Reactor Core The combination of THERMAL POWER, Reactor Coolant System highest loop average temperature, and pressurizer pressure shall not exceed the limits shown in..Figure .1.0 MILLSTONE  
Line 56: Line 52:
.2.4.1 The SHUTDOWN MARGIN shall bergreater than orequal to the limits shown inFigures 2, 3 and 4.235 Shutdown Margin -MODE 5 Loops Not Filled (Specification 3/4.1.1.2)
.2.4.1 The SHUTDOWN MARGIN shall bergreater than orequal to the limits shown inFigures 2, 3 and 4.235 Shutdown Margin -MODE 5 Loops Not Filled (Specification 3/4.1.1.2)
.2.5.1 The SHUTDOWN MARGIN shall be.greater than or,equal to the limits shown in Figure '5 or the limits shown in 4 with the chemical and volume control system (CVCS) aligned to preclude reactor-coolant system boron -concentration reduction.
.2.5.1 The SHUTDOWN MARGIN shall be.greater than or,equal to the limits shown in Figure '5 or the limits shown in 4 with the chemical and volume control system (CVCS) aligned to preclude reactor-coolant system boron -concentration reduction.
 
2.6 Moderator Temperature Coefficient (Specification 3/4.1.1.3) 2.6.1 The BOL/ARO/0%  
===2.6 Moderator===
 
Temperature Coefficient (Specification 3/4.1.1.3) 2.6.1 The BOL/ARO/0%  
-70%'RTP'MTC shall be less positive than + 0.5 x 0-4 Ak/k/!F. Above 70% RTP, the'MTC limit is a linear ramp to 0 Ak/k/°F at S-100% RTP.2.6.2 The EOL/ARO/RTP MTC shall be less negative than -5.65 x 10-4 Ak/k/0 F.2.6,.3 The 300 ppm/ARO/RTP MTC 'should be less.negative than or equal to-4.9 x 10-4 Ak/k/°F, where: BOL stands for Beginning Of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Power EOL stands for End Of Cycle Life RTP stands for Rated Thermal Power.2.7 Shutdown Rod Insertion Limit (Specification 3/4.1.3:5) 2.7..1 The"shutdown rods'shall be at least220 Steps withdrawn (inclusive).
-70%'RTP'MTC shall be less positive than + 0.5 x 0-4 Ak/k/!F. Above 70% RTP, the'MTC limit is a linear ramp to 0 Ak/k/°F at S-100% RTP.2.6.2 The EOL/ARO/RTP MTC shall be less negative than -5.65 x 10-4 Ak/k/0 F.2.6,.3 The 300 ppm/ARO/RTP MTC 'should be less.negative than or equal to-4.9 x 10-4 Ak/k/°F, where: BOL stands for Beginning Of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Power EOL stands for End Of Cycle Life RTP stands for Rated Thermal Power.2.7 Shutdown Rod Insertion Limit (Specification 3/4.1.3:5) 2.7..1 The"shutdown rods'shall be at least220 Steps withdrawn (inclusive).
 
2.8 Control Rod Insertion Limits (Specification 3/4.1.3.6) 2.8.1 The control rod banks shall be limited in physical insertion as shown in 2Figure 6, and MILLSTONE  
===2.8 Control===
Rod Insertion Limits (Specification 3/4.1.3.6) 2.8.1 The control rod banks shall be limited in physical insertion as shown in 2Figure 6, and MILLSTONE  
-UNIT 3 TRM 8.1-6 LBDCR 08-MP3-029 October 22, 2008 TECHNICAL REOUIREMENTS  
-UNIT 3 TRM 8.1-6 LBDCR 08-MP3-029 October 22, 2008 TECHNICAL REOUIREMENTS  
ýMANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT-2.8:22 Control bank A shall be at.least,2-20'steps withdrawn.
ýMANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT-2.8:22 Control bank A shall be at.least,2-20'steps withdrawn.
 
2.9. Axial Flux Difference (Specification 3/4,2.1.1) 2.9.1 The Axial Flux Difference (AFD) limits are.provided in 'Figure 7-2.9.2 The AFD target band during base load operation is "5%.2.9.3 The minimum allowable (nuclear design) power level for base load operation (APLND) is '80% of Rated Thermal Power.1.10 Heat Flux Hot ChanneF Factor -FQ(Z) (Specffication 3/4.2.2.1)
===2.9. Axial===
Flux Difference (Specification 3/4,2.1.1) 2.9.1 The Axial Flux Difference (AFD) limits are.provided in 'Figure 7-2.9.2 The AFD target band during base load operation is "5%.2.9.3 The minimum allowable (nuclear design) power level for base load operation (APLND) is '80% of Rated Thermal Power.1.10 Heat Flux Hot ChanneF Factor -FQ(Z) (Specffication 3/4.2.2.1)
RTP FQ FQ(_):ý  xxK(Z) for P > 0.5'P FRTP FQ(Z) -x K(Z) for P-_ 0.5 where: p = THERMAL POWER RATED THERMAL POWER 2.30.1 FRTPQ = 2.60.2.10.2 K(Z) is provided in Figure 8.2.11 Heat Flux Hot Channel Factor Surveillance  
RTP FQ FQ(_):ý  xxK(Z) for P > 0.5'P FRTP FQ(Z) -x K(Z) for P-_ 0.5 where: p = THERMAL POWER RATED THERMAL POWER 2.30.1 FRTPQ = 2.60.2.10.2 K(Z) is provided in Figure 8.2.11 Heat Flux Hot Channel Factor Surveillance  
-'FQ(Z) (Specification 3/4.2.,2.1.2)
-'FQ(Z) (Specification 3/4.2.,2.1.2)
Line 80: Line 69:
>_ 2-204 psia e 2.14 'Shutdown Margin Monitor Alarm Setpoint (Specification 3/4.3.5)**
>_ 2-204 psia e 2.14 'Shutdown Margin Monitor Alarm Setpoint (Specification 3/4.3.5)**
2.14.1 The Shutdown Margin Monitor,(SMM) minimum countrate and Alarm Ratio Setting to meet.LIMITTING CONDITION FOR OPERATION (LCO)3.3.5 shall be as shown below.Tech. Spec. LCO SMM Alarm Ratio Setting Min. Count Rate (counts/sec) 3.3.5.a 1.750 1.0 1-22 5 0.6*3.3.5.b.1 1.50 0.50 1.25 0.35 3.3.5.b.2 1.50 0.35.12.5 0.25 The combination of the SMM Alarm Ratio setting and minimum count rate accounts for the time lag between the indicated and actual count rates, as well as other uncertainties.
2.14.1 The Shutdown Margin Monitor,(SMM) minimum countrate and Alarm Ratio Setting to meet.LIMITTING CONDITION FOR OPERATION (LCO)3.3.5 shall be as shown below.Tech. Spec. LCO SMM Alarm Ratio Setting Min. Count Rate (counts/sec) 3.3.5.a 1.750 1.0 1-22 5 0.6*3.3.5.b.1 1.50 0.50 1.25 0.35 3.3.5.b.2 1.50 0.35.12.5 0.25 The combination of the SMM Alarm Ratio setting and minimum count rate accounts for the time lag between the indicated and actual count rates, as well as other uncertainties.
The specified SMM Alarm Ratio setting ensures that the assumption that an alarm is generated at flux doubling in the Boron Dilution Event analysis remains valid. The count rateis displayed on the SMM.2.15 Refueling Boron Concentration (Specification 3/4.9.1.1) 2.15.1 The boron concentration of allfilledlportions of the Reactor Coolant System and the refueling  
The specified SMM Alarm Ratio setting ensures that the assumption that an alarm is generated at flux doubling in the Boron Dilution Event analysis remains valid. The count rateis displayed on the SMM.2.15 Refueling Boron Concentration (Specification 3/4.9.1.1) 2.15.1 The boron concentration of allfilledlportions of the Reactor Coolant System and the refueling
:cavity shall be maintained at a boron concentration of greater than or equal to 2600 ppm.Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER.** Section 2.14 was prepared by Dominion based on boron dilution analyses performed by Westinghouse.
:cavity shall be maintained at a boron concentration of greater than or equal to 2600 ppm.Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER.** Section 2.14 was prepared by Dominion based on boron dilution analyses performed by Westinghouse.
This boron concentration bounds the condition of keff< 0.95 (all rods in less the most reactive two rods) and subcriticality (keff< 1.0 with all rods out).I&#xfd; MILLSTONE  
This boron concentration bounds the condition of keff< 0.95 (all rods in less the most reactive two rods) and subcriticality (keff< 1.0 with all rods out).I&#xfd; MILLSTONE  

Revision as of 23:05, 30 April 2019

Correction to Previously Submitted Correspondence for Cycle 14 Core Operating Limits Report
ML102240069
Person / Time
Site: Millstone Dominion icon.png
Issue date: 07/29/2010
From: Jordan A J
Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
10-287A, FOIA/PA-2011-0115
Download: ML102240069 (28)
v • d • e


Text

Dominion Nuclear Connecticut, Inc.Do ion Millstone Power Station Rope Ferry Road Waterford, CT 06385'JUL 2 9 2010 U.S. Nuclear Regulatory Commission Serial No. 10-287A Attention:

Document Control Desk NSS&LIMLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 CORRECTION TO PREVIOUSLY SUBMITTED CORRESPONDANCE FOR CYCLE 14 CORE OPERATING LIMITS REPORT The-purpose of this letter is to correct an error that was inadvertently introduced to the docket for Millstone"Power Station Unit 3 (MPS3). On May 6, 2010, Dominion Nuclear...Connecticut, Inc. (DNC),submitted the Core Operating Limits Report (COLR) for MPS3 Cycle 14. On June 22, 2010, while referencing the electronic version of the MPS3 Technical Requirements Manual (TRM), DNC discovered that Figure 7 of the COLR (Page 8.1-16) contained a duplicatecopy of the graph contained in Figure 8 (Page 8.1-17). This error was introduced during electronic publishing of the TRM change for the Cycle 14 COLR, which has since been corrected.

Controlled hard copies of the TRM, including control room copies, were not affected by this error. -Enclosure I contains the corrected version of the MPS3 Cycle 14 COLR.We apologize for any inconvenience this may have caused.-If you have any questions or require additional information, please contact Mr. William D.-Bartron at (860) 444-4301.Sincerely, S e rden SiteV~ ne Peident;-

M~illstone-Serial No. 10-287A'Docket No. 50-423 , ,Correction to Cycle 14.COLR Page 2 of 2 Epdloures:

(1)Commitmebts Made in this letter: 'None.,cc: U.S. Nuc'learRegulatory-Comhrission Region I 475 Allendale Road ,King of Prussia, PA 194,06-J 4 15 Ms. C., J.-Sanders NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail'Stop 8B3 11555 Rockville Pike Rockville, MD .20852:2738 NRC Senior Resident Inspector'Millstone Power-Station SSeral.No. 287A Doc-ket'No.

50-423 ENCLOSURE 1 CORE OPERATING LIMITS REPORT, CYCLE 14 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 TECHNICAL REQUIREMENTS MANUAL ,APPENDIX 8.1::,,CORE OPERATINGJLIMITS'REPORT

)'MILLSTONE MNIT.3 CYCLE 14ýCORE OPERATING LIMITS REPORT: 1: D,-I MILLSTONE

-UNIT3.TRM 81-1..LBDCR-10-MP3-009 April 13, 2010 TECHNICAL REOUIREMENTS MANUAL APPENDIX .8.1.CORE OPERATING LIMITS.REPORT Table of Contents Section Title -Page 1.0 .Core Operating Limits Report 8.1-4 Q,.0 Operating Limits 8.1-4 2.1 Safety Limits (Sperification 2.,i ..) 8.1-4.Limiting Safety.System Settings (SOpification 2.2.1) 8.1-5-,2.3 'Shutdown Mar-gin -MODE I and .(Specification 3/4. 1.13.1.1) 8.1-6-2.4 Shutdown Margin -MODE,3,4-andP5 Loops-Filled (Specification 3/4.1.1.1.:2) 8.1-6-2.-5 -Shutdown'Margin

-MODE5 LoopsýNot Filled (Specification 3/4.1.1 .2) -8.1-6 S26 MOderator Temperature Coeff~ent (Specification 3/4.1.1.3)

ý8.1-6 2.7 Shutdown Rod Insertion Limit.(Specification 3/4.1.35) 8.1-6-2.8 Control Rod Insertion Limits (Specifficatiorn3/4.1.3.6) 8.1-6 A2.9 xial Flux Differenee:(Specificition 3/4-2.1 .1) 8.1-7.2.10 'Heat Flux Hot Channel Factor -,'FQ(Z) (Specification 3/4.2;2.1) 8.1-7 2.11 Heat Flux Hot ChannelFactor Suryeillance

-FQ(Z),(Specification 3/4.2.2.1.2) 8.1-7 2.12 RCS Total'Flow Rate and Nuclear Enthalpy'kise Hot Channel Factor -FN AH (Specifitcation 3/4.2.3.1I) 8.1-8 2.13 DNB Parameters (Specification 3/4.2.5) 8.1-9 2..14. ShutdownMargin Monitor Alarm Setpoint.(Specification3/4.35) 8.1-9 2.115 RefuelingBoron Concentration-(Speci'fication 3/4.9. .1) 8.1-9 3.0 Analytical Methods 8.1-25 MILLSTONE

-UNIT 3 :TRM 8.1-2 LBDCR,08-MP3-029 October 22, 2008

.J Figure Figure 1 Tigure 2 Figure 3 Figure 4 Figure~5 Figure 6 Figure 7 Figure 8 TECHNICAL REOUIREMENTS-MANUAL APPENDIX 8.1 CORE OPERATING LIMITS.REPORT List of Figures Title Reactor Core Safety Limit Required Shutdown'Margin for MODE 3 RequiredShutdown Margin for MODE-4 Required Shutdown Margin for MODE5 "with RCS Loops Filled Required Shutdown Margin for MODE5 withRCS Loops.Not Filled Control.Rod Bank InsertionLimits versus Thermal Power.Axial Flux Difference Limits as a Function of Rated Thermal Power K(Z) -'Normalized FQ(Z) as a Function-of.Core Heright List of Tables Page 8.1-10 8.1-42 8.1-13 8.1-:14'8.1-15 8.1-16:8.1-17 y.)Table 'Title Table I RAOC'W(Z)

Function, Millstone Unit 3 -Cycle 14-12/+9 AFD at 100,oRTP Table 2 Base Load W(Z) Function, Millstone Unit 3 -Cycle 14 Table 3 Part Power (74% RTP, 150'MWD/MTU)

RAOC W(Z) Function, Millstone Unit.3 -Cycle 14 Table 4 Burnup Penalty for Incore Page 8.1-18 I 8.1-20 8.1--22 8.1-24 I Qi)MILLSTONE

-UNIT 3.TRM 8.1-3 LBDCR 10`MP3M09." April 13, 2010 TECHNICAL REOLUIREMENTS

ýMANUAL APPENDIX 8.1 CORE OPERATING.

LIMITS REPORT*1 Millstone Unit 3 Cycle 14 Core Operating Limits Report I 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR)for Millstone Unit 3 Cycle 14 has beenprepared in accordance with therequirements of Technicai Specification 6.9.1.6.a.

The Technical'Specifications affected by this report are listed below.I-2.1.1 2.2.1 3/4.1.1.1.1 314.1.1.1492 3/4.1.1.2.

3./4.1.1.3 3/4.1.3:5 3/4.1.3.6 3/14.2.1.1 3/4.2.2.1 3/4.2.3.1 3/4.2.5 3/4.3.5 3/.4.9.1.1 SafetyLimits Limiting Safety System Settings Shutdown.Margin

-MODE 1 and 2 Shutdown Margin -MODES 3,4 and5 Loops Filled ShutdownMargin

-MODE-5 LoopsNot Filled Moderator Temperature Coefficient Shutdown Rod Insertion Limit ControlRod Insertion Limits Axial Flux Difference Heat Flux Hot Channel Factor RCS Total Flow Rate and'NuclearEnthalpy Rise Hot Channel Factor DNB Parameters Shutdown Margin Monitor Alarm Setpoint Refueling Boron Concentration 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 6.9.1.6.b.

2.1 Safety-Limits (Specification 2.1.1)2.1.1 Reactor Core The combination of THERMAL POWER, Reactor Coolant System highest loop average temperature, and pressurizer pressure shall not exceed the limits shown in..Figure .1.0 MILLSTONE

-UNIT 3 TRM 8.1-4 LBDCR !0-MP3-009 April 13, 2010 TECHNICAL REOQUIREMENTS MAýNUAL APPENDIX 8.1 CORE OPERATING LIMITS:REPORT 2.,2 Limiting Safety System-Settings (Specificationg.2.2.1) 22.1 Overtemperature-AT

-2,2.1.1 K 1_< 1.20 2.2.1.2 K 2 > 0.0251/OF 212.1.3 K 3 >-0.00113/psi

.2.2.1.4 z: 8-seconds.2.2.1.5 f2 3 seconds.2.2.1.6 .4 >20 seconds 2.2.1.7 -< 4 seconds.2.2.1.8 T' is loop specific indicatedjTavn at RATED THERMAL POWER,._587.1 0 F ,.2.2.1.9 P' is nominal pressurizer pressure,.'

>,2 50 psia-2.2.1.10 fl(Al) is a function -of the indicated difference between top and bottom detectors of the power range neutron ion chambers; with nominal-gains to be selected based on measured instrument response.during plant-startup tests calibrations-such that: (l) For q, -qb between.-18%

and +10%, f 1 (AI) > 0, where qt and qb are percent RATED THERMAL'POWER in the upper and lower halves of the core, respectively, and q, + qb is the total THERMAL POWER'in percent RATED THERMAL POWER;(2) For each percent that the-magnitude of qt -qb exceeds -18%, the AT Trip Setpoint shall be automatically reduced by 2! 3.75% of its value at RATED THERMAL POWER.(3) For each per-cent that the magnitude of qt -qb.exceeds

+/-10%, the AT Trip Setpoint.shall be automatically reduced by. 2.14% of its value at RATED THERMAL POWER..2.2.2 Overpower AT 2.2.2.1 K4< 1.10-222.2 Deleted 22.2.3 K6 > 0.001O5/°F when T > T" and.K61(_

0 / 0 F'when'T<_

T".2.22.4 -1 8 -seconds 2.2.5 t- 3 'seconds MILLSTONE

-UNIT 3 TRM 8.1-5 LBDCR 08-MP3-029.October 22,2008 I TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERAT!NG LIMITS REPORT.2.2.2.6 Deleted 2.2.2.7 T" is loop-specific indicated Tayg atRATED THERMAL POWER,< 587.1W°.2.3 Shutdown Margin -MODE 1 and2 :(Specification 3/4.1.1.1.1)

..2.3.1 The SHUTDOWN MARGIN-shall be.,greater than or equal to 1.3% Ak/k.2.4 'Shutdown Margin -MODE 3, 4 and'5 Loops Filled (Specification 3/4.11.1.2)

.2.4.1 The SHUTDOWN MARGIN shall bergreater than orequal to the limits shown inFigures 2, 3 and 4.235 Shutdown Margin -MODE 5 Loops Not Filled (Specification 3/4.1.1.2)

.2.5.1 The SHUTDOWN MARGIN shall be.greater than or,equal to the limits shown in Figure '5 or the limits shown in 4 with the chemical and volume control system (CVCS) aligned to preclude reactor-coolant system boron -concentration reduction.

2.6 Moderator Temperature Coefficient (Specification 3/4.1.1.3) 2.6.1 The BOL/ARO/0%

-70%'RTP'MTC shall be less positive than + 0.5 x 0-4 Ak/k/!F. Above 70% RTP, the'MTC limit is a linear ramp to 0 Ak/k/°F at S-100% RTP.2.6.2 The EOL/ARO/RTP MTC shall be less negative than -5.65 x 10-4 Ak/k/0 F.2.6,.3 The 300 ppm/ARO/RTP MTC 'should be less.negative than or equal to-4.9 x 10-4 Ak/k/°F, where: BOL stands for Beginning Of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Power EOL stands for End Of Cycle Life RTP stands for Rated Thermal Power.2.7 Shutdown Rod Insertion Limit (Specification 3/4.1.3:5) 2.7..1 The"shutdown rods'shall be at least220 Steps withdrawn (inclusive).

2.8 Control Rod Insertion Limits (Specification 3/4.1.3.6) 2.8.1 The control rod banks shall be limited in physical insertion as shown in 2Figure 6, and MILLSTONE

-UNIT 3 TRM 8.1-6 LBDCR 08-MP3-029 October 22, 2008 TECHNICAL REOUIREMENTS

ýMANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT-2.8:22 Control bank A shall be at.least,2-20'steps withdrawn.

2.9. Axial Flux Difference (Specification 3/4,2.1.1) 2.9.1 The Axial Flux Difference (AFD) limits are.provided in 'Figure 7-2.9.2 The AFD target band during base load operation is "5%.2.9.3 The minimum allowable (nuclear design) power level for base load operation (APLND) is '80% of Rated Thermal Power.1.10 Heat Flux Hot ChanneF Factor -FQ(Z) (Specffication 3/4.2.2.1)

RTP FQ FQ(_):ý xxK(Z) for P > 0.5'P FRTP FQ(Z) -x K(Z) for P-_ 0.5 where: p = THERMAL POWER RATED THERMAL POWER 2.30.1 FRTPQ = 2.60.2.10.2 K(Z) is provided in Figure 8.2.11 Heat Flux Hot Channel Factor Surveillance

-'FQ(Z) (Specification 3/4.2.,2.1.2)

RTP F x K(Z)FQ(Z)_< Q forP>0.5 P.XW(4Z)RTP FQFQZ) forP <0.5 F -(Z) 0.5 x W(Z)where: -p THERMAL POWER RATED THERMAL POWER MILLSTONE

-UNIT 3 TRM 8.1-7 LBDCR 08-MP3-029 October 22,2008 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.11.1 FRTPQ = 2.60..2.11.2 K(Z) is provided inFigure 8..2.11.3 W(Z) values .for RAOC operation are provided in Table 1. Note that-the W(Z) values at Axial Mesh 1 are at the top of the core. The Cycle 14 burnup dependent RAOC W(Z) values are valid over therange of bumup from 0 to 21,900IMWDIMTU.

.2.11.4 W(Z) values for Base Load (BL) operation are provided in Table.2. Note that the W(Z) values at Axial*.Mesh 1 are at the top of the core.*The Cycle 14 bumup dependent BL'W(Z) values are valid overfthe range of burnup from 0 to .21,900 2.11.5 W(Z) values for-Part Power operation are provided in Table 3. Note that the W(Z) values, at Axial'Mesh I are at the top of the core. The Cycle ,14 burnup dependent Part Power W(Z) values are valid over the range of burnup from 0 to .150 MWD/MTU.-2.1,1.6 --The factors in Table 4.shall be used for surveillance requirements 4.2.2.1.2 and 4.2.2.1.4.

A .2%,factor shall b1 used outside of the burnup range shown in Table 4.2.12 RCS Total Flow Rate and.NuclearEnthalpy'Rise Hot Channel Factor -FNAH" ( ... (Specification 3/4.2.3.1) 2.12.1 The RCS Total Flow Rate shall be greater than or equal to 379,200 gpm.VN T.2.12.2 F AH "< FRAH x (1 + PFAHX [1 -P1)where: p = THERMAL POWER RATED THERMAL POWER 2.12.2.1 FR7PAH = 1.586 for Robust FuelAssemblies (RFA).and (RFA-2)

PFAH = 0.3 for P < 1.0.MILLSTONE

-UNIT 3 TRM 8.1-8 LBDCR 10-'MP3-009 April.13, 2010 TECHNICAL REQUIREMMNTS MANUAL APPENDIX 8.1 CORE OPERATING:LWS REPORT/2.13 DN`B Parameters (Specification 3/4.2-5),2.13.1 Indicated Reactor Coolant System Tag shall be maintained

< 593'5-EF 2.13.2 Indicated Pressurizer Pressure -shall bermaintained

>_ 2-204 psia e 2.14 'Shutdown Margin Monitor Alarm Setpoint (Specification 3/4.3.5)**

2.14.1 The Shutdown Margin Monitor,(SMM) minimum countrate and Alarm Ratio Setting to meet.LIMITTING CONDITION FOR OPERATION (LCO)3.3.5 shall be as shown below.Tech. Spec. LCO SMM Alarm Ratio Setting Min. Count Rate (counts/sec) 3.3.5.a 1.750 1.0 1-22 5 0.6*3.3.5.b.1 1.50 0.50 1.25 0.35 3.3.5.b.2 1.50 0.35.12.5 0.25 The combination of the SMM Alarm Ratio setting and minimum count rate accounts for the time lag between the indicated and actual count rates, as well as other uncertainties.

The specified SMM Alarm Ratio setting ensures that the assumption that an alarm is generated at flux doubling in the Boron Dilution Event analysis remains valid. The count rateis displayed on the SMM.2.15 Refueling Boron Concentration (Specification 3/4.9.1.1) 2.15.1 The boron concentration of allfilledlportions of the Reactor Coolant System and the refueling

cavity shall be maintained at a boron concentration of greater than or equal to 2600 ppm.Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER.** Section 2.14 was prepared by Dominion based on boron dilution analyses performed by Westinghouse.

This boron concentration bounds the condition of keff< 0.95 (all rods in less the most reactive two rods) and subcriticality (keff< 1.0 with all rods out).Iý MILLSTONE

-UNIT 3 TRM 8.1-9 LBDCR 10-MP3--009 April 13, 2010 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 1 Reactor Core Safety Limit 680-660.640@k *UL 0 orf2 600"580 560 0 0.2 0.4. 0.6 0.8 1 1.2-FRACTION OF RATED THERMAL POWER MILLSTONE

-UNIT 3 TRM 8.1-10 ,LBDCR 08-MP3-029 October 2.2,2008 TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 2 Required Shutdown Mafrgin for MODE 3 C)o c::o C-E 00 0 0 C3, 0/.U)tr)(Ni U, _=('tv o/) Nie9tvI/w NmocanfHs 0 MILLSTONE

-UNIT 3 TRM 8.1-11 ,LBDCR 08-MP3-029 October2-2, 2008 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 3 Required Shutdown Margin for MODE 4 C:1 C'4 j-ý0 0 0 CD, U')0 tf) U C)ý Uo C) t C)ý t? W) to Co c)to to tO 3- 'T () CI), CI C~J~ C) C:)(MjV %) NIOUiVLI~

NMAOOfLnHS MILL'STONE

-UNIT 3 TRM 8.1-12 LBDCR 08-MP3-029 October 22, 2008 TECHNICAL REQUIREMENTSMANUAL APPENDIX 8.1 CORE OPERATING LIMITS-REPORT Figure 4 Required Shutdown Mairgin for MODE5 With RCS Loops Filled C=)C: ( N.. .",, C>, Ca-a-C 0 0 0 0 0 y-.0 0 C--0 un (D LL3 U'CD (AV ?/) NPDSýVUIA NMOtJLn.Hs 0 MILLSTONE

-UNIT 3 TRM 8.1-13 LBDCR 08-MP3-029 October,22, 2008 TECHNICAL REQUIREMENTS MANUAL'APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure'5 Required Shutdown Margin for MODE 5 with RCS .Loops"Not Filled C,4 C>C>0-CD c~ U) C: u) = f C:ý u) Cý LQ Cý u) C)ý u) C?to Lo (I ) C13 Cc J ( --C -CZ)(M'V %)'NIOUVWj' NmoaiIOHs MILLSTONE

-UNIT 3 TRM 8.1 14.. -LBDCR 08-MP3-029 October.22, 2008 TECHNICAL REOUIREMENTS MANUAL ,AP?ENDIX 8.1 CORE OPERATING LIMITS -REPORT Figure 6 Control Rod B3ank Insertion Limits versus Thermal Power-240 220-200 a14 0o LI-o 100 C.z M 80 00 60 40 20 0 0 10 20, 30 40 '50 60 70 :80 -90 100 RATED THERMAL POWER (%)MILLSTONE

-UNIT 3 TRM 8.1-15 LBDCR 08-MP3-029 October 22, 2008 TECHNICAL.REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 7 Axial Flux Difference Limits as a Function of Rated Thermal Power 1 2__0 100 .I o.o L a, 0 0~a, 9-I-41).4-.PS 80 (K. )40.2O-60 40 20 -10 0 10 20 30 40 -50 60 Fliqx Difference, % D~elta-I MILLSTONE

-UNIT 3 TRM 8.1-16 LBDCR 08-MP3-029 October,22, 2008

,TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT'Figure 8 K(Z) -NormaliZed FQ(Z) as a Function of Core Height"2 12 1 .1 in.(:0,i A3.7'0,5 S0.3 10.2 12).0 0.2 0.1.0_0 Sno 1D 6.0Ft O.M5 I2D Ft I__ ____ .... ____ _ ___" _8 9 0 1 2 3 4 15 B6 7 Core Elevation, (feet)10 11 1.2 C)MILLSTONE

-UNIT 3 TRM 8.1-17 LBDCR 08-MP3-029 October .22, 2008 ITECtNICAL REQUIREMENTS MANUAL APPENDIX 8.1-,CORE OPERATING LIMITS REPORT Table.1 RAOC W(Z) Function, Millstone Unit 3 ,Cycle 14-12/+9 AFD-at 100%.RTP!I lBurnup *t Mesh N 1 2 3 4 6 7.8:9 10 11 12.13 14 15 16 17:18 19 ,20 21 22-23 24-25-26 27:-28 29.30 31 32 33 34-35 36 37 38 39 40.Height*12.0000 11.8333 11'6667 11.5000 11.3333 11.1667 11.0000 10.8333 10.6667 10-5000 10.3333-10.1667 110.0000 9.8333 9.6667 9.5000 9.3333 9.1667 9.0000-8.8333-.8.6667 8.5000 8.3333.8.1667 8.0000 7.8333 7.6667ý7.5000 7.3333 7.1667 7.0000 6.8333 6;6667 6.5000 6.3333 6.1667 6.0000 5.8333 5.6667 5.5000 150 1.0000 1.0000 1.0000 1.0000 1.0000.1.0000 1.4306 1.4028 1.3828 1.3605 1.3349 1.3083 1.2833 1.2585 i.2320 1.2080 1.1972 1.1850 1.1733 1.1717 1.1738 1.1765 1,1779 1.1783 1.1775, 1.1757 1.1728 1.1715.1.1691 1.1656 1.1610 1.1554 1.1490 1.1420 1.1350 1.1285 1.1242 1.1216 1.1198 1.1205 tep (MWD/MTU)5000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.4942 1.4769 1.4604 1.4399 1.4181 1.3944 1.3671 1.3390 1.3109 12830 1.2619 1.2472 1.23.15 1.2189 1.2102 1.2025 1.1935 1.1854.1.1816 1.1778 1.1719 1.1653 1.1577 1.1494 1.1403 1.1,297 1.1196 1.1141 1.1i16 1.1097 1.1078 1.1057 1.1038 1.1036 11000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.4136 1.4043 1.3919 1.3760 113595 1.3432 1.3266 1.3093 1.2901 1.2734 1.2629 1.2505 1.2387 1.2304 1.2253 1.2210 1.2145 1.2072 1.2024 1.1968 1.1911 1.1886 1.1857 1.1806 1.1743 1.1668 1.1582.1.1484 1.1381 1.1263 1.1128 1.1083 1.1089 1.1105 18600 1.0000 1.0000 1.0000 1.0000 1.0000 10000.1.3761 1.3722 1.3646 1.3536 1.3403 132_54 1.3093 1.2920 1.2732 12530 1.2351 1.2233 1.21-81 1.2093 1.2085 1.2145 1.2195 1,2228 1.2248 1.2254 1.2246 1.2224 1.2189 1.2143 1.2112 1.2067 1.2008 1.1936 1.1854 1.1766 1.1677.1.1589 1.1'524 1.1526 Distance from bottom of active core (feet): MILLSTONE -L UNIT 3 TRM 8.1-18 LBDCR 10-MP3-009 April 13, 2010 TECHNICAL REQUIREMENTS MANUAL-APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 1 (Continued)

RAOC'W(Z)

Function, Millstone Unit 3 -Cycle 14-12/+9 AFD at 10Y0% RTP I Burnup- Step (MWPIMTU)Mesh No.41 42 43 44 45 46 47 48 49 50 51 52'53'54 55'56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 Height*5.3333 5.1667 5.0000 4.8333 4.6667 4.5000 4.3333 4.1667 4.0000 3.8333 3.6667 315000%3.3333 3.1667 3.0000 2.8333.2.6667.2.5000.2.3333 2.1667 2.0000 1.8333 1.6667 1.5000 1.3333 1.1667 1.0000 0.8333 0.6667 0.50X)0.3333 0.1667 0.0000 150 1.1248 1.1315 1.1378 1.1434 1.1488 1.1538 1.1'584 1.1626 1.1665 1.1701 1.1733 1.1765 1.1811 1.1882 1.1970 1.2052 1.2136 1.2278 1.2445 1.2601 1.2753 1.2901.1.3039 1.3166 1.3284 1.3390 1..3478 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5000 1 .,1 052 1.1105 1.1190.1.1-228 1.1-26.1 1.11293 1.1321 1.1343 1.1-377 1.1426 1.1472 1.1516 1. 1i569 1.1639 J1.1709 1.1778 1,.1.906 J1.2044 1.2194 1.2356 1.2511 1.2660 1.2798 1.2925 1.3040 1.3139 1.0000 1.0000.1.0000 1.0000 1.0000 1.0000 11000 1.1135 1.11[80 1.1219 1.1257 1.1298 1.1336 1.1371 1.1402 1.1432 1.1455 1.1480 1.1526 1.1574 1.1618 1.1675 1.1734 1.1799 1.1925 1.2047 1.2169 1.2287 1.2399 1.2504 1.2600 1.2686 1.2759 1.28015 1.0000 1.0000 1.0000 1.6000 1.0000 1.0000 18600 1.1'554 1.1582 1.1603 1.1617 1.1622 1.1,621 1.1614 1.1,600 1.1582 1.1560 1. 1'534 1.1506 1.1479 1.1460.1.1490 1.1597 1.1715 1.1831 1.1946 1,2059 1.2169 1.2275 1.2373 1.2464 1.2547 1.2617 1.2670 1.0000 1.0000 1.0000 1.0o000 1.0000 1.0000.( )* 'Distance from bottom of active core (feet).MILLSTONE

-.UNIT 3 TRM 8.1-19 LBDCR 10,MP3-009 Aprl 13, 2010 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATINMG LI1ITS REPORT Table 2 Base Load W(Z),Function Millstone Unit 3 -CycleJ14 I@Burnup Step Mesh No. Height* 150 1 12.0000 1.0000 11.8333 1.0000 3 11.6667 1.0000 4 1175000 1.0000 5 11.3333 1.0000.6 11.1667 1.0000 7 11.0000 1.1905 8 10.8333 1.1811 9 10.6667 1.1750 10 10.5000 1.1686 11 10.3333 1.1.6.16 12 10.1667 1.1541 13 10.0000 1.1461 14 9.8333 1.1378 15 -9.6667 1.1339 16 9.5000 1.1305 17 9.3333 1.1248 18 9.1667 1.1188 19 9.0000 1.11.65 20 8.8333 1.1169 21 8.6667 1.1212 22 8.5000 1.1258 23 8.3333 1.1304 24 8.1667 1.1329 25 8.0000 1.1360 26 7.8333 1.1380 27 7.6667 1..1393 28 7.5000 1.1418 29 7.3333 1.1435 30 7.1667 1.1437 31 7.0000 .1427 32 -6.8333 1.14'%4 33 6.6667 1.1373 34 6.5000 1.1340 35 6.3333 1.1291 36 6.1667 1.1270 37 6.0000 1.1243 38 5.8333 1.1218 39 5.6667 1.1199 40 5.5000 1.1191 Distance from bottom of active core (feet)(MWD/MTU)5000 1.0600 1.0000 1.0000 1.0000 1.0000 1.0000 1,.2185 1.2131 1.2081 1.2029 1.1975 1.1963 1,1893 1.1793 1.1704 1.1670 1.1611 1.1537 1.1491 1.1465 1.1442 1.1405 1.1338 1.1282 1.1286 1.1301 1.1299 1.1291 1.1276 1.1252.A221 11190 1.1163 1.1138 1.1117 1.1097 1.1078 1.1057 1.1038 1.1024 11000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1860 1.1837 1.1806 1.1763 1.1728 1.1710 1.1703 1.1696 1.1689 1.1680 1.1635 1.1564 1.1506 1.1490 1.1487 1.1476 1.1443 1.1409 1.1399 1.1383 1.1368 1.1387 1.1402 1.1397 1.1383 1.1359 1.1324 1.1279 1.1227 1.1166 1.1094 1..1036 1.1028 1.1014 18600 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1518 1.1505 1.1465 1.1424 1.1378 1.1360 1.1381 1.1383 1.1375 1.1.372 1.1345 1.1310 1.1290 1.1-235 1.1300 1.1388 1.1473 1.1541 1.1599 1.1647 1.1683 1.1708 1.1722 1.1732 1.1750 1.1754 1.1747 1.1728 1.1695 1.1656 1.1622 1.1576 1.1524 1.1498 MILLSTONE

--UNIT 3 TRM 8.1-20 LBDCR 10-MP3-009 April 13, 2010 TECHNICAL REOUMWMENTS MANUAL..APPE IX 8.1 CORE OPERATING LP.MTS REPORT Table 2 (Continued).Base Load W(Z) Function Millstone Unit.3 -Cycle 14 Burnup Step Mesh No. Height* 150 41 5.3333 1.1185 42 5.1667 1.1172 43 5.0000 1.1154 44 4.8333 1.1132 45 4.6667 1.1106 46 4.5000 1.1076 47 4.3333 1.1043 48 4.1667 1.1007 49 4.0000 1.0969 50 3.8333 1.0929 51 3.6667 1.0888 52 3.5000 1.0874'53 3.3333 1.0877-54 3.1667 1.0887 55 3.0000 1.0896 56 2.8333 1.0920 57 2.6667 1.1027 58 2.5000 1.1148 59 2.3333 1.1267 60 2.1667 1.1389 61 2.0000 1.1509 62 1.8333 1.1625 63 1.6667 1.1735 64 1.5000 1.1838 65 1.3333 1.1934 66 1.1667 1.2020 67 1.0000 1.2090'68 0.8333 1.0000 69 0.6667 11.0000 70 0.5000 1L0000 71 0.3333 1.0000 72 0.11567 L.c,0 73 0.0000 1.0030 Distance from bottom of active core (feet)'15000 1.3008 1.0991 1.0976 1.0957 1.0938 1.0925 1.0911 1.0895 1.0876 1*0871 1.0874 1.0879 1.0880 1.0880 1.0904 1.0999 1.1143 1.1288 1.1435 1.1586 1.1736 1.1881 1.2018 1.2147 1.2264 112369 1.2457 1.0000 1.0000 1.0000 1.co00 1.0000 1.0000 LO00 1.0993 1.0970 1.0943 1.0916 1.0896 1.0873 1.0849 1.0823 1.0792 1.0782 1.0798 1.0811 1.0817 1.0826 1.0861 1.0938 1.1049 1.1162 1.1272 1.1383 1.1493 1.1599 1.1698 1.1790 1.1872 1.1943 1.1998 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 18600 1.1479 1.1452 1.1417 1.1374 1.1325 1.1270 1.1.210 1.1145 1.1077 1.1008 1.0936 1.0862.1.0812 1.0790 1.0861 1.0937 1.1017.1.1099 1.1180 1.1261 1.1341 1.1418 1.1491 1.1558 1.1618 1.1670 1.1706 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 (k _-')MILLSTONE

-UNIT 3 TRM 8.1-21 LBDCR 10-MP3-009 April 13,2010 TECHNICAL REQUIREMENTS MANUAL APPENJnIX 8.1.COREOPERATING LIMITTS REPORT Table 3 Part.Power (74% RTP, 1'50 MWD/MTU) RAOC W(Z).Function

'Millstone Unit 3 -cycle 14 I K ..),Mesh No 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26ý27 28.29 30*3 I 32 33 34 35 36 37 38 39 40 Distance from bottom of active core (feet)Height (ft)*12.0000 1U1.8333 11.6667 11.5000 11.3333 11.1667 11.0000 10.8333 10.6667 10"5000 10.3333 10.1667 10.0000 9.8333 9.6667 95000 9.3333 9.1667 9.0000 8.8333 8.6667 8.5000 8.3333 8.1667 8.0000 7.8333 7.6667 7.5000 7.3333 7.1667 7.0000 6.8333 6.6667 6.5000 6.3333 6.1667 6.0000 5.8333 5.6667 5.5000 W(z)1.O00 1.0000 1.0000 J.10000 1.0000 1.0000 1.2696 1.2504 1.2353 12.202 1.2019 1.1820 1.1635 1.1441 1.1205 1.1099 1.1043 1.0972 1.0908 1.0937 1.0991.1*1047 1.1088 1.1116 1.1131.1.1133 1.1142 1.1149 1.1156 1.1168 1.1173 1.1168 1.1 155*11133 1,11111 1.1093 1. 1083 1.1086 1.1103 1.1146 MILLSTONE

-UNIT 3 TRM 8.1-22 LBDCR 10-MP3-009 April 13,-2010

.TECHNICAL REQUIREMENTS MANUAL.APPENDIX 8..1 CORE OPERATING LMIITS REPORT TableW3 (Continued)

Part Power (74% RTP, 150 MWD/MTU).RAOCW(Z)TFunction Millstone Unit 3 -Cycle 14 I Mesh No 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71;72 73 Distance from bottom of active core (feet)Height (ft)*5.3333 5.1667 ,5.0000 4.8333 4.6667 4.5000 4.3333 4.1667 4.0000 3.8333 3.6667 3'5000 3.33 3.1667 3.0000 2.8333 2.6667 2.5000 2.3333 2.1667 2.0000 1.8333 1.6667 1.5000 1.3333 1.1667 1.0000 0.8333 0.66671 0.5000 0.3333 0.1667: 0.0000'W(z)1.1.216 1.1321 1.1418 1.1508 1.1r597 1.1681.1.1759 1.1835 1.1922 1,2009 1.2093 1L2169 1.2247 1.2328 1.2425 1.2578 1.2793 1.3003 1.3208 1.3414 1.3613 1.3797 1.3969 1.4148 1.4327 1.4488 1.46925 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0)i/ "0 MILLSTONE

-UNIT 3 TRM 8.1-23 LBDCR .10-MP3-009 April 13, 2010

.TECHNICAL REQUIREMENTS&MANUAL

..APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 4 ,Burnup Penalty for Incore*Bumup'Ponalty 4659 1.020 4820 1.022 4981 1.022 5142 1. 022 5303 1.022.5465 1:022"5626 1.021* '787 .1.021'5948 1.020 Note: A penalty of 1.02 shall be used outside of the bumup;range sho~wn in Table 4.*(MILLSTONE

-UNIT 3 TRM 8.1-24 LBDCR 10-MP3-009 April 13, 2010

'~V........................

TECHNICAL.REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 3.0 Analytical Methods The analytical methods used to determine the core operating limits shall be those p7r-eviously

reviewed and approved by the'NRC, specifically those described in the 6followixig documents.

.3.1 WCAP--9272-P-A, "WESTINGHOUSE RELOADISA-FETYý-EVALUATION METHODOLOGY,".July 1985 (WProprietary).

3.2 'WCAP-10216-P-A-RIA, "RELAXATION OF CONSTANfT-AXIAL OFFSET ,CONTROL FQ SURVEILLANCE TECHNICAL 1, February 1994 &W Proprietary).

3.3 WCAP-12945-P-A, Yolume l(Revision,2) and Volumes.2 through 5 (Revision 1), "Code-Qualification Document for Best -Estimate LOCA Analysis,"lMarch 1998 (W Proprietary).

3.4 WCAP-16009-P-A, "Realistic Large-Break LOCAEvaluation Methodolggy Using the Automated Statistical Treatment of Uncertainty'Method (ASTRUM)," January-,2005

(&W Proprietary). 5 WCAP-11 946, "SafetyfEvaluation Supporting a MoreN-egative EOL Moderator Temperature Coefficient Technical Specification for the.Millstone Nuclear Power Station Unit 3," September 19'88 (W Proprietary).

3.6, WCAP-10054-P-A, "WESTINGHOUSE"SMALL BREAK ECCS EVALUATION MODEL 17 USING THE NOTRUMP CODE," August 1985 (W Proprietary).

337 WCAP-10079-P-A, "NOTRUMP -A NODAL TRANSIENT SMALL BREAK AND GENERA L NETWORK CODE," August 1985 ()W Proprietary).

3.8 WCAP-12610-P-A, "VANTAGE+

Fuel Assembly'Report," April 1.995 (W Proprietary).

3.9 WCAP-8301, "LOCTA-IV Program: Loss-of-Coolant Transient Analysis," June 1974 (&W Proprietary).

3.110 WCAP-10054-P-A, Addendum 2,'Revision 1, "Addendum to the Westinghouse"Small Break ECCS'Evaluation Model Using the NOTRUMP Code: SafetyInjection into the Broken Loop and COSI Condensation Model," July 1997 (W Proprietary).

3.1.1 WCAP-8745-P-A, '-DESIGN BASES FOR THE THERMAL OVERPOWER AT AND THERMAL OVERTEMPERATURE AT TRIP FUNCTIONS," September 1986 (W Proprietary).

MILLSTONE

-UNIT 3 TRM 8.1-25 LBDCR 08-MP3-029 October 22,2008

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