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Tech. Spec. LCO SMM Alarm Ratio Setting Min. Count Rate (counts/sec) 3.3.5.a 1.50 1.0 1.25 0.6 3.3.5.b.1 1.50 0.50 1.25 0.35 3.3.5.b.2 1.50 0.35 1.25 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 rate is displayed on the SMM. | Tech. Spec. LCO SMM Alarm Ratio Setting Min. Count Rate (counts/sec) 3.3.5.a 1.50 1.0 1.25 0.6 3.3.5.b.1 1.50 0.50 1.25 0.35 3.3.5.b.2 1.50 0.35 1.25 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 rate is displayed on the SMM. | ||
2.15 Refueling Boron Concentration (Specification 3/4.9.1.1) 2.15.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling cavity shall be maintained at a boron concentration of greater than or equal to 2600 ppm. | 2.15 Refueling Boron Concentration (Specification 3/4.9.1.1) 2.15.1 The boron concentration of all filled portions 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. | 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) during the Cycle 12/13 refueling outage. | 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) during the Cycle 12/13 refueling outage. |
Latest revision as of 18:24, 12 March 2020
ML083300359 | |
Person / Time | |
---|---|
Site: | Millstone |
Issue date: | 11/14/2008 |
From: | Jordan A Dominion Nuclear Connecticut |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
08-0632 | |
Download: ML083300359 (28) | |
Text
Dominion Nuclear Connecticut, Inc.
Millstone Power Station Rope Ferry Road, Waterford, CT 06385 U.S. Nuclear Regulatory Commission Serial No. 08-0632 Attention: Document Control Desk NSS&L/MLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-65 DOMINION NUCLEAR CONNECTICUT. INC.
MILLSTONE POWER STATION UNIT 3 NOV 1 4 2008 CORE OPERATING LIMITS REPORT. CYCLE 13 In accordance with the Millstone Power Station Unit 3 (MPS3) Technical Specifications (TSs), Section 6.9.1.6.d, Dominion Nuclear Connecticut, Inc., hereby submits, as , the Cycle 13 Core Operating Limits Report (COLR).
The MPS3 COLR has been revised to incorporate the following:
- Changes specific to Cycle 13 operation
" Revisions to overtemperature AT parameters, overpower AT parameters, and reactor core safety limits.
- Changes in plant parameters and analytical methods references due to incorporation of License Amendment 242 for a Stretch Power Uprate
" Editorial changes The COLR has been incorporated into the MPS3 Technical Requirements Manual.
If you have any questions or require additional information, please contact Mr. William D.
Bartron at (860) 444-4301.
Sincerely, Site Vice President - Millstone
-4c)b(
WZK
Serial No. 08-0632 Docket No. 50-423 Core Operating Limits Report, Cycle 13 Page 2 of 2
Enclosures:
(1)
Commitments made in this letter: None.
cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 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
Serial No. 08-0632 Docket No. 50-423 ENCLOSURE 1 CORE OPERATING LIMITS REPORT, CYCLE 13 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT MILLSTONE UNIT 3 CYCLE 13 I CORE OPERATING LIMITS REPORT MILLSTONE - UNIT 3 TRM 8.1 -1 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table of Contents Section Title Page 1.0 Core Operating Limits Report 8.1-4 2.0 Operating Limits 8.1-4 2.1 Safety Limits (Specification 2.1.1) 8.1-4 2.2 Limiting Safety System Settings (Specification 2.2.1) 8.1-5 2.3 Shutdown Margin - MODE 1 and 2 (Specification 3/4.1.1.1.1) 8.1-6 2.4 Shutdown Margin - MODE 3, 4 and 5 Loops Filled (Specification 3/4.1.1.1.2) 8.1-6 2.5 Shutdown Margin - MODE 5 Loops Not Filled (Specification 3/4.1.1.2) 8.1-6 2.6 Moderator Temperature Coefficient (Specification 3/4.1.1.3) 8:1-6 2.7 Shutdown Rod Insertion Limit (Specification 3/4.1.3.5) 8.1-6 2.8 Control Rod Insertion Limits (Specification 3/4.1.3.6) 8.1-6 2.9 Axial Flux Difference (Specification 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 Channel Factor Surveillance - FQ(Z)
(Specification 3/4.2.2.1.2) 8.1-7 2.12 RCS Total Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor - FNAH (Specification 3/4.2.3.1) 8.1-8 2.13 DNB Parameters (Specification 3/4.2.5) 8.1-9 2.14 Shutdown Margin Monitor Alarm Setpoint (Specification 3/4.3.5) 8.1-9 2.15 Refueling Boron Concentration (Specification 3/4.9.1.1) 8.1-9 3.0 Analytical Methods 8.1-25 MILLSTONE - UNIT 3 TRM 8.1-2 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT List of Figures Figure Title Page Figure 1 Reactor Core Safety Limit 8.1-10 Figure 2 Required Shutdown Margin for MODE 3 8.1-11 Figure 3 Required Shutdown Margin for MODE 4 8.1-12 Figure 4 Required Shutdown Margin for MODE 5 with RCS Loops Filled 8.1-13 Figure 5 Required Shutdown Margin for MODE 5 with RCS Loops Not Filled 8.1-14 Figure 6 Control Rod Bank Insertion Limits versus Thermal Power 8.1-15 Figure 7 Axial Flux Difference Limits as a Function of Rated Thermal Power 8.1-16 Figure 8 K(Z) - Normalized FQ(Z) as a Function of Core Height 8.1-17 List of Tables Table Title Page Table 1 RAOC W(Z) Function, Millstone Unit 3 - Cycle 13 8.1-18
- 12/+9 AFD at 100% RTP Table 2 Base Load W(Z) Function, Millstone Unit 3 - Cycle 13 8.1-20 Table 3 Part Power (74% RTP, 150 MWD/MTU) RAOC W(Z) Function, Millstone Unit 3 - Cycle 13 8.1-22 Table 4 Burnup Penalty for Incore 8.1-24 MILLSTONE - UNIT 3 TRM 8.1-3 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Millstone Unit 3 Cycle 13 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) for Millstone Unit 3 Cycle 13 has been prepared in accordance with the requirements of Technical Specification 6.9.1.6.a. The Technical Specifications affected by this report are listed below.
2.1.1 Safety Limits 2.2.1 Limiting Safety System Settings 3/4.1.1.1.1 Shutdown Margin - MODE 1 and 2 3/4.1.1.1.2 Shutdown Margin- MODES 3, 4 and 5 Loops Filled 3/4.1.1.2 Shutdown Margin - MODE 5 Loops Not Filled 3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.3.5 Shutdown Rod Insertion Limit 3/4.1.3.6 Control Rod Insertion Limits 3/4.2.1.1 Axial Flux Difference 3/4.2.2.1 Heat Flux Hot Channel Factor 3/4.2.3.1 RCS Total Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor 3/4.2.5 DNB Parameters 3/4.3.5 Shutdown Margin Monitor Alarm Setpoint 3/4.9.1.1 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.
MILLSTONE - UNIT 3 TRM 8.1-4 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.2 Limiting Safety System Settings (Specification 2.2.1) 2.2.1 Overtemperature AT 2.2.1.1 K 1 *< 1.20 2.2.1.2 K2 >0.025 / °F 2.2.1.3 K3 Ž0.00113/psi 2.2.1.4 r1 > 8 seconds 2.2.1.5 "C 2 < 3 seconds 2.2.1.6 C4 Ž20 seconds 2.2.1.7 5 *4
-C seconds 2.2.1.8 T' is loop specific indicated Tvg at RATED THERMAL POWER,
<587.1°F 2.2.1.9 P' is nominal pressurizer pressure, > 2250 psia 2.2.1.10 fl (AI) 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:
(1) For qt - qb between -18% and +10%, fl(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 > 3.75% of its value at RATED THERMAL POWER.
(3) For each percent that the magnitude ofqt - 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 2.2.2.2 Deleted 2.2.2.3 K 6 Ž 0.00 15 / °F when T > T" and K 6 _<0 / OF when T*< T" 2.2.2.4 c1 _ 8 seconds 2.2.2.5 "r2 < 3 seconds MILLSTONE - UNIT 3 TRM 8.1-5 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.2.2.6 Deleted 2.2.2.7 T" is loop specific indicated Tavg at RATED THERMAL POWER,
_<587.1 0 F 2.3 Shutdown Margin - MODE 1 and 2 (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 3/4.1.1.1.2) 2.4.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 2, 3 and 4.
2.5 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 Figure 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 10-4 Ak/k/°F. Above 70% RTP, the MTC limit is a linear ramp to 0 Ak/k/°F at 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/0 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 least 220 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 Figure 6, and MILLSTONE - UNIT 3 TRM 8.1-6 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.8.2 Control bank A shall be at least 220 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 (APL ND) is 80% of Rated Thermal Power.
2.10 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3/4.2.2.1)
F RTP Q
FQ(Z) < PQ x K(Z) for P > 0.5 F RTP Q
FQ(Z) -0.5Q x K(Z) for P < 0.5 where: p = THERMAL POWER RATED THERMAL POWER 2.10.1 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)
FRTP x K(Z)
FQ(Z)* PWZ for P > 0.5 RIP F Q x K(Z)
FQ(Z), < -0.5 0 x w(z) for P*< 0.5 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 in Figure 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 13 burnup dependent RAOC W(Z) values are valid over the range of burnup from 0 to 21,350 MWD/MTU.
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 I are at the top of the core. The Cycle 13 bumup dependent BL W(Z) values are valid over the range of burnup from 0 to 21,350 MWD/MTU.
2.11.5 W(Z) values for Part Power operation are provided in Table 3. Note that the W(Z) values at Axial Mesh 1 are at the top of the core. The Cycle 13 burnup dependent Part Power W(Z) values are valid over the range of burnup from 0 to 150 MWD/MTU.
2.11.6 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 be used outside of the bumup range shown in Table 4.
2.12 RCS Total Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor - F NAH (Specification 3/4.2.3.1) 2.12.1 The RCS Total Flow Rate shall be greater than or equal to 379,200 gpm.
2.12.2 FNAH _<FRTPAH X (1 + PFAH x [1 - P])
where: p = THERMAL POWER RATED THERMAL POWER 2.12.2.1 FRTPAH = 1.587 for Robust Fuel Assemblies (RFA) and (RFA-2) 2.12.2.2 PFAH 0.3 for P < 1.0.
I MILLSTONE - UNIT 3 TRM 8.1-8 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.13 DNB Parameters (Specification 3/4.2.5) 2.13.1 Indicated Reactor Coolant System Tavg shall be maintained _<593.5'F.
2.13.2 Indicated Pressurizer Pressure shall be maintained Ž 2204 psia *.
2.14 Shutdown Margin Monitor Alarm Setpoint (Specification 3/4.3.5)**
2.14.1 The Shutdown Margin Monitor (SMM) minimum count rate and Alarm Ratio Setting to meet LIMITING 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 1.50 1.0 1.25 0.6 3.3.5.b.1 1.50 0.50 1.25 0.35 3.3.5.b.2 1.50 0.35 1.25 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 rate is displayed on the SMM.
2.15 Refueling Boron Concentration (Specification 3/4.9.1.1) 2.15.1 The boron concentration of all filled portions 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) during the Cycle 12/13 refueling outage.
MILLSTONE - UNIT 3 TRM 8.1-9 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 1 Reactor Core Safety Limit 680 660 640 LL 6
UI 620 C-)
(I) 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 22, 2008
r--- 4.0 0
z 1 3.5 C
z
,3.000 P7 ,3.O00 Io 3.0 -]
C n 2.5 -
2.5 Z >
00 >
wz r-00O 0.5 CD C 0.0 S0 500 1000 1500 2000 2500 oo (.oRCS CRITICAL BORON CONCENTRATION (ppm)
6.0 0
z 5.5 m
C z 5.0 4.5 9 0
4.0 H4 0 z 9
,3.5 Cf2 3.0 z z 0
z 0
i 9
f25 2.0 0
U) 9 0
1.5 0 H I- 1.0 00 0.5 CD Co 0.0 1-1 1 roDZ 0 500 1000 1500 2000 2500 RCS CRITICAL BORON CONCENTRATION (ppm)
6.0 On z 5.5 m
C 5.0 z
2.0 4.4.50070 [ .5070 4.5 4.0 coo
-4z CL 3.5 >
00 V ot-500 5 0.300 O E; 0.5 0
0DCc 0.50 OP H OOj*2 0 500 1000 1500 2000 2500 CD 0 RCS CRITICAL BORON CONCENTRATION (ppm)
CD ca
r-W 7.0 (2200, 6.150) 0 6.5 z
m
-'-q CA 6.0 z
5.5 (1252 5.523 (2500, 6.150) 5.0 H z 4.0 z) 3.5 z
3.0 0 00 Cz 0
2.5 2.0 0
1.5 1.0 (355, 1.300) r-00 0.5 0" 0 CD Co 0.0
'-I I 0 500 1000 1500 2000 2500 00 RCS CRITICAL BORON CONCENTRATION (ppm) or"D
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 6 Control Rod Bank Insertion Limits versus Thermal Power 240 220 200 180 160 140 zI 120 z
1 00 0
aý 80 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 REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 7 Axial Flux Difference Limits as a Function of Rated Thermal Power 120 100 _ 1-12, 1001 9,100 1 80 0
E 60 L-41 40 20 0
-60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 Flux Difference, % Delta-I MILLSTONE - UNIT 3 TRM 8.1-16 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 8 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.2 1.1 1.0 0.9 V
IU--
M 0.7 H
"l-"
0.P1 L0 n,_"7 0.5 (03 0.4 0.3 0.2 0.1 0.0 1 2 3 4 5 6 7 8 9 10 11 12 Core Elevation, (feet)
MILLSTONE - UNIT 3 TRM 8.1-17 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 1 RAOC W(Z) Function, Millstone Unit 3 - Cycle 13
-12/+9 AFD at 100% RTP Burnup Step (MWil/MU)
Mesh No. Height
- 150 6000 12000 18000 1 12.0000 1.0000 1.0000 1.0000 1.0000 2 11.8333 1.0000 1.0000 1.0000 1.0000 3 11.6667 1.0000 1.0000 1.0000 1.0000 4 11.5000 1.0000 1.0000 1.0000 1.0000 5 11.3333 1.0000 1.0000 1.0000 1.0000 6 11.1667 1.0000 1.0000 1.0000 1.0000 7 11.0000 1.0000 1.0000 1.0000 1.0000 8 10.8333 1.0000 1.0000 1.0000 1.0000 9 10.6667 1.0000 1.0000 1.0000 1.0000 10 10.5000 1.3936 1.4312 1.3316 1.2860 11 10.3333 1.3683 1.4075 1.3111 1.2697 12 10.1667 1.3430 1.3830 1.2894 1.2523 13 10.0000 1.3162 1.3571 1.2671 1.2339 14 9.8333 1.2893 1.3301 1.2432 1.2188 15 9.6667 1.2603 1.3013 1.2230 1.2149 16 9.5000 1.2295 1.2710 1.2177 1.2108 17 9.3333 1.2112 1.2479 1.2112 1.2053 18 9.1667 1.2030 1.2345 1.2037 1.1999 19 9.0000 1.1943 1.2217 1.1964 1.1983 20 8.8333 1.1929 1.2124 1.1941 1.2009 21 8.6667 1.1946 1.2064 1.1939 1.2025 22 8.5000 1.1950 1.2010 1.1958 1.2059 23 8.3333 1.1939 1. 1947 1.1971 1.2105 24 8.1667 1. 1925 1.1887 1.1977 1.2156 25 8.0000 1.1915 1.1855 1.1984 1.2208 26 7.8333 1. 1910 1.1819 1.1979 1.2244 27 7.6667 1.1903 1.1765 1.1962 1.2263 28 7.5000 1.1881 1.1704 1.1943 1.2274 29 7.3333 1.1844 1.1655 1.1912 1.2270 30 7.1667 1.1797 1. 1590 1.1864 1.2246 31 7.0000 1. 1737 1.1515 1.1803 1.2205 32 6.8333 1.1668 1.1431 1.1730 1.2149 33 6.6667 1. 1589 1.1336 1.1644 1.2077 34 6.5000 1.1509 1.1231 1.1546 1.1991 35 6.3333 1.1444 1.1161 1.1442 1.1893 36 6.1667 1.1400 1.1143 1.1324 1.1781 37 6.0000 1.1361 1.1114 1.1208 1.1665 38 5.8333 1.1320 1.1081 1.1158 1.1579 39 5.6667 1.1285 1.1053 1.1138 1.1519 40 5.5000 1.1272 1.1051 1.1170 1.1532
- Distance from bottom of active core (feet)
MILLSTONE - UNIT 3 TRM 8.1-18 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 1 (Continued)
RAOC W(Z) Function, Millstone Unit 3 - Cycle 13
-12/+9 AFD at 100% RTP Burnup Step (MWD/MTU)
Mesh No. Height* 150 6000 12000 18000 41 5.3333 1.1281 1.1070 1.1209 1.1572 42 5.1667 1.1320 1.1104 1.1235 1.1602 43 5.0000 1.1371 1.1142 1.1258 1.1624 44 4.8333 1. 1422 1.1179 1.1277 1.1639 45 4.6667 1. 1467 1.1212 1.1310 1.1646 46 4.5000 1. 1508 1.1243 1.1343 1.1645 47 4.3333 1.1546 1.1277 1.1375 1.1639 48 4.1667 1.1581 1.1314 1.1402 1.1626 49 4.0000 1. 1612 1.1348 1.1423 1.1610 50 3.8333 1.1641 1.1379 1.1455 1.1592 51 3.6667 1.1667 1.1410 1.1507 1.1571 52 3.5000 1.1691 1.1441 1.1562 1.1549 53 3.3333 1.1715 1.1475 1.1615 1.1523 54 3.1667 1.1765 1.1510 1.1664 1.1498 55 3.0000 1.1890 1.1580 1.1714 1.1524 56 2.8333 1.2053 1.1706 1.1824 1.1635 57 2.6667 1.2214 1.1848 1.1965 1.1759 58 2.5000 1.2377 1.1997 1.2106 1.1881 59 2.3333 1.2540 1.2147 1.2245 1.2001 60 2.1667 1.2700 1.2302 1.2382 1.2120 61 2.0000 1.2857 1.2465 1.2514 1.2235 62 1.8333 1.3008 1.2624 1.2641 1.2345 63 1.6667 1.3150 1.2775 1.2759 1.2448 64 1.5000 1.0000 1.0000 1.0000 1.0000 65 1.3333 1.0000 1.0000 1.0000 1.0000 66 1.1667 1.0000 1.0000 1.0000 1.0000 67 1.0000 1.0000 1.0000 1.0000 1.0000 68 0.8333 1.0000 1.0000 1.0000 1.0000 69 0.6667 1.0000 1.0000 1.0000 1.0000 70 0.5000 1.0000 1.0000 1.0000 1.0000 71 0.3333 1.0000 1.0000 1.0000'1 1.0000 72 0.1667 1.0000 1.0000 1.0000 1.0000 73 0.0000 1.0000 1.0000 1.0000 1.0000
- Distance from bottom of active core (feet)
MILLSTONE - UNIT 3 TRM 8.1-19 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 2 Base Load W(Z) Function Millstone Unit 3 - Cycle 13 Burnup Step (MWD.MTU)
Mesh No. Height
- 150 6000 12000 18000 1 12.0000 1.0000 1.0000 1.0000 1.0000 2 11.8333 1.0000 1.0000 1.0000 1.0000 3 11.6667 1.0000 1.0000 1.0000 1.0000 4 11.5000 1.0000 1.0000 1.0000 1.0000 5 11.3333 1.0000 1.0000 1.0000 1.0000 6 11.1667 1.0000 1.0000 1.0000 1.0000 7 11.0000 1.0000 1.0000 1.0000 1.0000 8 10.8333 1.0000 1.0000 1.0000 1.0000 9 10.6667 1.0000 1.0000 1.0000 1.0000 10 10.5000 1.1682 1.1965 1.1633 1.1477 11 10.3333 1.1650 1.1896 1.1560 1.1437 12 10.1667 1.1624 1.1826 1.1483 1.1390 13 10.0000 1.1566 1.1755 1.1400 1.1339 14 9.8333 1.1498 1.1682 1.1317 1.1284 15 9.6667 1.1436 1.1613 1.1236 1.1227 16 9.5000 1.1381 1.1549 1.1152 1.1168 17 9.3333 1.1317 1.1465 1.1087 1.1108 18 9.1667 1.1257 1.1377 1.1086 1.1110 19 9.0000 1.1233 1.1329 1.1120 1.1171 20 8.8333 1.1241 1.1312 1.1159 1.1212 21 8.6667 1.1297 1.1304 1.1203 1.1262 22 8.5000 1.1355 1.1289 1.1250 1.1347 23 8.3333 1.1403 1.1297 1.1289 1.1431 24 8.1667 1.1439 1.1326 1.1318 1.1499 25 8.0000 1.1465 1.1344 1.1338 1.1557 26 7.8333 1.1514 1.1353 1.1349 1.1606 27 7.6667 1.1544 1.1354 1.1352 1.1642 28 7.5000 1.1562 1.1346 1.1352 1.1668 29 7.3333 1.1569 1.1330 1.1364 1.1683 30 7.1667 1.1564 1.1306 1.1366 1.1688 31 7.0000 1.1547 1.1274 1.1357 1.1709 32 6.8333 1.1522 1.1241 1.1340 1.1717 33 6.6667 1.1490 1.1212 1.1313 1.1714 34 6.5000 1.1456 1.1184 1. 1277 1.1700 35 6.3333 1.1425 1.1163 1. 1238 1.1671 36 6.1667 1.1399 1.1143 1.1199 1.1636 37 6.0000 1.1362 1.1114 1.1156 1.1607 38 5.8333 1.1320 1.1080 1.1125 1.1567 39 5.6667 1.1285 1.1053 1.1111 1.1519 40 5.5000 1.1267 1.1045 1.1106 1.1496
- Distance from bottom of active core (feet)
MILLSTONE - UNIT 3 TRM 8.1-20 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 2 (Continued)
Base Load W(Z) Function Millstone Unit 3 - Cycle 13 I Burnup Step (MWD.MTU)
Mesh No. Height
- 150 6000 12000 18000 41 5.3333 1.1248 1.1039 1.1098 1.1484 42 5.1667 1.1220 1.1024 1.1086 1.1464 43 5.0000 1.1187 1.1016 1.1069 1.1436 44 4.8333 1.1149 1.1005 1.1048 1.1400 45 4.6667 1.1107 1.0990 1.1024 1.1358 46 4.5000 1.1063 1.0973 1.1002 1.1310 47 4.3333 1.1025 1.0953 1.0978 1.1256 48 4.1667 1.0985 1.0931 1.0953 1.1197 49 4.0000 1.0942 1.0909 1.0928 1.1134 50 3.8333 1.0898 1.0883 1.0900 1.1070 51 3.6667 1.0864 1.0868 1.0898 1.1003 52 3.5000 1.0855 1.0883 1.0908 1.0928 53 3.3333 1.0855 1.0889 1.0915 1.0892 54 3.1667 1.0863 1.0899 1.0923 1.0888 55 3.0000 1.0926 1.0945 1.0953 1.0913 56 2.8333 1.1027 1.1044 1.1026 1.0977 57 2.6667 1.1143 1.1186 1.1139 1.1058 58 2.5000 1.1261 1.1330 1.1255 1.1144 59 2.3333 1.1383 1.1471 1.1367 1.1227 60 2.1667 1.1503 1.1615 1.1480 1.1311 61 2.0000 1.1623 1.1756 1.1591 1.1395 62 1.8333 1.1738 1.1893 1.1698 1.1474 63 1.6667 1.1847 1.2022 1.1798 1.1550 64 1.5000 1.0000 1.0000 1.0000 1.0000 65 1.3333 1.0000 1.0000 1.0000 1.0000 66 1.1667 1.0000 1.0000 1.0000 1.0000 67 1.0000 1.0000 1.0000 1.0000 1.0000 68 0.8333 1.0000 1.0000 1.0000 1.0000 69 0.6667 1.0000 1.0000 1.0000 1.0000 70 0.5000 1.0000 1.0000 1.0000 1.0000 71 0.3333 1.0000 1.0000 1.0000 1.0000 72 0.1667 1.0000 1.0000 1.0000 1.0000 73 0.0000 1.0000 1.0000 1.0000 1.0000
- Distance from bottom of active core (feet)
MILLSTONE - UNIT 3 TRM 8.1-21 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 3 Part Power (74% RTP, 150 MWD/MTU) RAOC W(Z) Function Millstone Unit 3 - Cycle 13 Mesh No. Height (fi) W(z) 1 12.0000 1.0000 2 11.8333 1.0000 3 11.6667 1.0000 4 11.5000 1.0000 5 11.3333 1.0000 6 11.1667 1.0000 7 11.0000 1.0000 8 10.8333 1.0000 9 10.6667 1.0000 10 10.5000 1.2384 11 10.3333 1.2175 12 10.1667 1. 1983 13 10.0000 1.1789 14 9.8333 1. 1592 15 9.6667 1.1370 16 9.5000 1.1129 17 9.3333 1. 1004 18 9.1667 1.0974 19 9.0000 1.0942 20 8.8333 1.0980 21 8.6667 1.1041 22 8.5000 1.1090 23 8.3333 1.1132 24 8.1667 1.1178 25 8.0000 1.1212 26 7.8333 1.1241 27 7.6667 1.1284 28 7.5000 1.1313 29 7.3333 1.1329 30 7.1667 1.1331 31 7.0000 1.1317 32 6.8333 1.1291 33 6.6667 1.1261 34 6.5000 1.1229 35 6.3333 1.1209 36 6.1667 1.1202 37 6.0000 1.1202 38 5.8333 1.1207 39 5.6667 1.1229 40 5.5000 1.1263 MILLSTONE - UNIT 3 TRM 8.1-22 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 3 (Continued)
Part Power (74% RTP, 150 MWD/MTU) RAOC W(Z) Function Millstone Unit 3 - Cycle 13 Mesh No. Height (ft) W(z) 41 5.3333 1.1312 42 5.1667 1.1376 43 5.0000 1.1459 44, 4.8333 1.1545 45 4.6667 1.1623 46 4.5000 1.1707 47 4.3333 1.1792 48 4.1667 1.1875 49 4.0000 1.1949 50 3.8333 1.2020 51 3.6667 1.2085 52 3.5000 1.2148 53 3.3333 1.2223 54 3.1667 1.2327 55 3.0000 1.2454 56 2.8333 1.2594 57 2.6667 1.2736 58 2.5000 1.2883 59 2.3333 1.3099 60 2.1667 1.3313 61 2.0000 1.3525 62 1.8333 1.3737 63 1.6667 1.3941 64 1.5000 1.0000 65 1.3333 1.0000 66 1.1667 1.0000 67 1.0000 1.0000 68 0.8333 1.0000 69 0.6667 1.0000 70 0.5000 1.0000 71 0.3333 1.0000 72 0.1667 1.0000 73 0.0000 1.0000 MILLSTONE - UNIT 3 TRM 8.1-23 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 4 Burnup Penalty for Incore
- Burnup Penalty i
3691 1.020 3852 1.022 4013 1.023 4174 1.024 4335 1.025 4496 1.027 4818 1.029 5461 1.029 5783 1.027 5944 1.025 6105 1.024 6427 1.020
- Note: A penalty of 1.02 shall be used outside of the burnup range shown in Table 4.
MILLSTONE - UNIT 3 TRM 8.1-24 LBDCR 08-MP3-029 October 22, 2008
TECHNICAL REQUIREMENTS 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 previously reviewed and approved by the NRC, specifically those described in the following documents.
3.1 WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (W Proprietary).
3.2 WCAP-10216-P-A-R1A, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION," Rev. 1, February 1994 (W Proprietary).
3.3 WCAP-12945-P-A, Volume 1 (Revision 2) and Volumes 2 through 5 (Revision 1), "Code Qualification Document for Best Estimate LOCA Analysis," March 1998 (W Proprietary).
3.4 WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," January 2005 (W Proprietary).
3.5 WCAP- 11946, "Safety Evaluation Supporting a More Negative EOL Moderator Temperature Coefficient Technical Specification for the Millstone Nuclear Power Station Unit 3," September 1988 (W Proprietary).
3.6 WCAP-10054-P-A, "WESTINGHOUSE SMALL BREAK ECCS EVALUATION MODEL 17 USING THE NOTRUMP CODE," August 1985 (W Proprietary).
3.7 WCAP-10079-P-A, "NOTRUMP - A NODAL TRANSIENT SMALL BREAK AND GENERAL NETWORK CODE," August 1985 (W Proprietary).
3.8 WCAP-126 10-P-A, "VANTAGE+ Fuel Assembly Report," April 1995
()W Proprietary).
3.9 WCAP-8301, "LOCTA-IV Program: Loss-of-Coolant Transient Analysis," June 1974 (W Proprietary).
3.10 WCAP-10054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model," July 1997 (W Proprietary).
3.11 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