ML13148A274
| ML13148A274 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/13/2013 |
| From: | Macmanus R Dominion, Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML13148A274 (29) | |
Text
Dominion Nuclear Connecticut, Inc. D Rope Ferry Road, Waterford, CT 06385 DominEoN Web Address: www.dom.com my 13 26D U.S. Nuclear Regulatory Commission Serial No.13-294 Attention: Document Control Desk NSS&L/MAE RD Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT. INC.
MILLSTONE POWER STATION UNIT 3 CORE OPERATING LIMITS REPORT, CYCLE 16 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 16 Core Operating Limits Report (COLR).
The MPS3 COLR has been revised to incorporate the following:
- 1) Editorial changes to increment the Cycle number from 15 to 16.
- 2) Editorial changes to cite the applicable Technical Specifications in the list of Analytical Methods (note: there were no additions, deletions or changes to the Analytical Methods).
- 3) Changes are made in the burnup range of applicability for W(Z) values in COLR Sections 2.11.3 and 2.11.4 to be consistent with the expected end of Cycle 16 burnup value of 21,600 MWD/MTU.
- 4) Cycle16-specific changes to the W(Z) values in Tables 1 through 3.
The COLR has been incorporated into the MPS3 Technical Requirements Manual.
If you have any questions or require additional information, please contact William D.
Bartron at (860) 444-4301.
Sincerely, R. K. MacManus Director, Nuclear Station Safety and Licensing - Millstone
Serial No.13-294 Docket No. 50-423 Core Operating Limits Report, Cycle 16 Page 2 of 2
Enclosures:
(1)
Commitments made in this letter: None.
cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 Nadiyah S. Morgan Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 0-8C2A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No.13-294 Docket No. 50-423 ENCLOSURE 1 CORE OPERATING LIMITS REPORT, CYCLE 16 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT MILLSTONE UNIT 3 CYCLE 16 I CORE OPERATING LIMITS REPORT MILLSTONE - UNIT 3 TRM 8.1-1 LBDCR 13-MP3-005
TECHMCAL 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 O pe rating Lim its ......................................................................................................... 8 .1-4 2.1 S afety Lim its (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) ......................................... 8.1-7 2.8 Control Rod Insertion Limits (Specification 3/4.1.3.6) ............................................ 8.1-7 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 (S pecification 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 TRMVI 8.1-2 LBIDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT List of Figures Figure Title Paqe Figure 1 R eactor C ore Safety Lim it................................................................................... 8.1-10 Figure 2 Required SHUTDOWN MARGIN for MODE 3 ...................... 8.1-11 Figure 3 Required SHUTDOW N 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 POWER8.1-16 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 16 -12/+9 AFD at 100% RTP.8.1-18 Table 2 Base Load W(Z) Function Millstone Unit 3 - Cycle 16 ..................................... 8.1-20 Table 3 Part Power (74% RTP, 150 MWD/MTU) RAOC W(Z) Function Millstone Unit 3 -
C yc le 16 ................................................................................... ...................... 8 .1-2 2 Table 4 Burnup Penalty for Incore Millstone Unit 3 - Cycle 16 ..................................... 8.1-24 MILLSTONE - UNIT 3 TRM 8.1-3 LBDCR 13-MP3-005
TECBNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Millstone Unit 3 Cycle 16 CORE OPERATING LIMITS REPORT 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Millstone Unit 3 Cycle 16 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 13-MP3-005
TECHMCAL 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 _0.0251/F 2.2.1.3 K3 Ž0.00113/psi 2.2.1.4 1, _ 8 seconds 2.2.1.5 "22 < 3 seconds 2.2.1.6 -C4 > 20 seconds 2.2.1.7 5 :*4 seconds 2.2.1.8 T' is loop specific indicated Tavg at RATED THERMAL POWER, <587.10 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 qt + 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 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 1K4 1.10 2.2.2.2 Deleted MILLSTONE - UNIT 3 TRM 8.1-5 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.2.2.3 K6 _ 0.0015 I 0F when T> T" and K6 *0 / °F when T* T" 2.2.2.4 1 Ž-8 seconds 2.2.2.5 a -*-3 seconds 2
2.2.2.6 Deleted 2.2.2.7 T" is loop specific indicated Tavg at RATED THERMAL POWER, < 587.10 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/°RF.
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.
MILLSTONE - UNIT 3 TRM 8.1-6 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 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 2.8.2 Control bank A shall be at least 220 steps withdrawn.
2.9 AXIAL FLUX DIFFERENCE (Specification 314.2.1.1) 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.
2.10 Heat Flux Hot Channel Factor - FQ(Z) (Specification 314.2.2.1)
) <QFRTP FQ(Z)-_ p x K(Z) for P > 0.5 FRTP FQ(Z)<ý. 5 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)
F,.'P XK(Z)
FQ(Z) -PQXw(Z) for P > 0.5 MILLSTONE - UNIT 3 TRM 8.1-7 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT FQRTP x K(Z)
FQ(Z) < for P 5 0.5 0.5 x W(Z) where: p = THERMAL POWER RATED THERMAL POWER 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 16 burnup dependent RAOC W(Z) values'are valid over the range of burnup from 0 to 21,600 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 1 are at the top of the core.
The Cycle 16 burnup dependent BL W(Z) values are valid over the range of burnup from 0 to 21,600 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 16 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 burnup range shown in Table 4.
2.12 RCS Total Flow Rate and Nuclear Enthalpy 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.
2.12.2 FNAH < FRTPAH X(1 + PFAH x [1 - P])
where: p = THERMAL POWER RATED THERMAL POWER 2.12.2.1 FRTPAH = 1.586 for Robust Fuel Assemblies (RFA) and (RFA-2) 2.12.2.2 PFAH = 0.3 for.P < 1.0.
MILLSTONE - UNIT 3 TRM 8.1-8 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.13 DNB Parameters (Specification 314.2.5) 2.13.1 Indicated Reactor Coolant System Tavg shall be maintained <
593.50 F.
2.13.2 Indicated Pressurizer Pressure shall be maintained > 2204 psia .
2.14 Shutdown Margin Monitor Alarm Setpoint (Specification 3/4.3.5)2 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 3
concentration of greater than or equal to 2600 ppm.
1 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.
2 Section 2.14 was prepared by Dominion based on boron dilution analyses performed by Westinghouse.
3 This boron concentration bounds the condition of keff < 0.95 (all rods in less the most
)reactive two rods) and subcriticality (keff:<l1.0 with all rods out).
MILLSTONE - UNIT 3 TRM 8.1-9 LBDCR 13-MP3-005
TECEMCAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT N)
Figure 1 Reactor Core Safety Limit 680 660 640 LL d
d 620 F--
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 13-MP3-005
J z Figure 2 Required SHUTDOWN MARGIN for MODE 3 4.0 3.5 3.0 2.5 o-%
2.0 1.5 1.0 0.5 0.0 0 500 1000 1500 2000 2500 RCS CRITICAL BORON CONCENTRATION (ppm)
TRM 8.1-11 MILLSTONE - UNIT 3 LBDCR 13-MP3-005
- 1 Figure 3 Required SHUTDOWN MARGIN for MODE 4 6.0 5.5 5.0 4.5 4.0 z
S3.0 z
- 2.5 0
2.0 1.5 1.0 0.5 0.0 0 500 1000 1500 2000 2500 RCS CRITICAL BORON CONCENTRATION (ppm)
TRM 8.1-12 MILLSTONE - UNIT 3 LBDCR 13-MP3-005
Figure 4 Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Filled 6.5 5.0 4.5 4.0 z
2 2
z 2 ,0 1,5 G,5 0 1000 15*0 2:000 2600 RCSCRMCAL BORON CQNCENTATIO (PPM)
TRM 8.1-13 MILLSTONE - UNIT 3 LBDCR 13-MP3-005
Figure 5 Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Not Filled 7.0 (2200, 6.150) 6.5 6.0 (1252, 5.523) '-(2500, 6.150) 5.5
' 5.0 4.5 z
(9 4.0 S3.5 z
- 3.0 0
oI-- 2.5
" 2.0 (0, 1.300) 1.5 1.0 (355, 1.300) 0.5 0.0 0 500 1000 1500 2000 2500 RCS CRITICAL BORON CONCENTRATION (ppm)
TRM 8.1-14 MILLSTONE - UNIT 3 LBDCR 13-MP3-005
TECHMCAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 6 Control Rod Bank Insertion Limits versus THERMAL POWER 240 220 200 180 160 140 120
)
z 0
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 13-MP3-005
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 80 0Il 0~
60 E-
) VI.
40 20 0
50 -40 -30 -20 -10 0 10 20 30 40 50 60 Flux Difference, % Delta-I
)
MILLSTONE - UNIT 3 TRM 8.1-16 .LBDCR 13-MP3-005
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 0.8 0
0.7 C3 03 0)
.co 0.6 (03
) 0 (D
L4 0.5 M
E L-0.4 0
K) Elefabon 0.3 ID 0.0 Ft
-B 13.0 Ft 0.M5 12.0 Ft 0.2 0.1 0.0 0 1 2 3 4 5 6 7 8 9 10 11 12 Core Elevation, (feet)
)
MILLSTONE - UNIT 3 TRM 8.1-17 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT N~)
Table 1 RAOC W(Z) Function, Millstone Unit 3 - Cycle 16 I
-12/+9 AFD at 100% RTP Burnup Step (MWDIMTU)
Mesh No. Height* 150 3000 9000 18000 1 12.0778 1.0000 1.0000 1.0000 1.0000 2 11.9101 1.0000. 1.0000 1.0000 1.0000 3 11.7423 1.0000 1.0000 1.0000 1.0000 4 11.5746 1.0000 1.0000 1.0000 1.0000 5 11.4068 1.0000 1.0000 1.0000 1.0000 6 11.2391 1.0000 1.0000 1.0000 1.0000 7 11.0714 1.3772 1.4366 1.4030 1.3314 8 10.9036 1.3716 1.4234 1.3934 1.3277 9 10.7359 1.3550 1.4041 1.3862. 1.3209 10 10.5681 1.3424 1.3740 1.3766 1.3119 11 10.4004 1.3256 1.3569 1.3617 1.3013 12 10.2326 1.3025 1.3424 1.3444 1.2888 13 10.0649 1.2777 1.3237 1.3245 1.2743 14 9.8971 1.2534 1.3023 1.3011 1.2610 15 9.7294 1.2314 1.2797 1.2791 1.2524 16 9.5616 1.2082 1.2558 1.2651 1.2428 17 9.3939 1.1870 1.2338 1.2520 1.2348
) 18 19 9.2261 9.0584 1.1709 1.1592 1.2155 1.1969 1.2359.
1.2210 1.2287 1.2196 20 8.8906 1.1537 1.1810 1.2099 1.2078 21 8.7229 1.1546 1.1713 1.2032 1.1962 22 8.5551 1.1577 1.1695 1.1991 1.1874 23 8.3874 1.1596 1.1690 1.1949 1.1827 24 8.2196 1.1606 1.1673 1.1901 1.1859 25 8.0519 1.1609 1.1649 1.1895 1.1921 26 7.8841 1.1604 1.1620 1.1895 1.1992 27 7.7164 1.1589 1.1583 1.1876 .1.2039 28 7.5487 1.1564 1.1539 1.1843 1.2070 29 7.3809 1.1531 1.1487 1.1800 1.2087 30 7.2131 1.1489 1.1431 1.1744 1.2088 31 7.0454 1.1436 1.1383 1.1678 1.2075 32 6.8777 1.1383 1.1344 1.1600 1.2047 33 6.7099 1.1339 1.1312 1.1512 1.2004 34 6.5422 1.1294 1.1278 1.1416 1.1947 35 6.3744 1.1246 1.1238 1.1313 1.1879 36 6.2067 1.1203 1.1191 1.1203 1.1801 37 6.0389 1.1179 1.1130 1.1094 1.1706 38 5.8712 1.1155 1.1090 1.1032 1.1618
- Distance from bottom of active core (feet)
Note: Surveillance exclusion zone is 8%top, 8%bottom.
)
MILLSTONE - UNIT 3 TRM 8.1 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 1 (Continued)
RAOC W(Z) Function, Millstone Unit 3 - Cycle 16
-121+9 AFD at 100% RTP Burnup Step (MWD/MTU)
Mesh No. Height* 150 Burnup Step 3000 9000 - 18000 39 5.7034 1.1132 1.1088 1.1021. 1.1562 40 5.5357 1.1167 1.1133 1.1024 1.1531 41 5.3679 1.1245 1.1208 1.1048 1.1530 42 5.2002 1.1305 1.1271 1.1095 1.1556 43 5.0324 1.1359 1.1331 1.1140 1.1575 44 4.8647 1.1412 1.1387 1.1177 1.1581 45 4.6969 1.1460 1.1438 1.1212 1.1582 46 4.5292 1.1503 1.1484 1.1244 1.1575 47 4.3614 1.1543 1.1527 1.1274 1.1562 48 4.1937 1.1579 1.1565 1.1301 1.1543 49 4.0259 1.1612 1.1599 1.1339 1.1520 50 3.8582 1.1641 1.1630 1.1398 1.1491 51 3.6905 1.1668 1.1658 1.1460 1.1459 52 3.5227 1.1690 1.1679 1.1519 1.1470 53 3.3550 1.1715 1.1706 1.1572 1.1501 54 3.1872 1.1771 1.1791 1.1621 1.1531 55 3.0195 1.1918 1.1896 1.1682 1.1585
) 56 2.8517 1.2112 1.2007 1.1756 1.1680 57 2.6840 1.2294 1.2115 1.1902 1.1815 58 2.5162 1.2478 1.2273 1.2057 1.1957 59 2.3485 1.2665 1.2478 1.2209 1.2099 60 2.1807 1.2849 1.2674 1.2361 1.2239 61 2.0130 1.3031 1.2867 1.2510 1.2376 62 1.8452 1.3208 1.3057 1.2653 1.2509 63 1.6775 1.3377 1.3239 1.2789 1.2636 64 1.5097 1.3536 1.3409 1.2915 1.2755 65 1.3420 1.3681 1.3565 1.3029 1.2864 66 1.1742 1.3808 1.3703 1.3127 1.2958 67 1.0065 1.3905 1.3809 1.3197 1.3024 68 0.8387 1.0000 1.0000 1.0000 1.0000 69 0.6710 1.0000 1.0000 1.0000 1.0000 70 0.5032 1.0000 1.0000 1.0000 1.0000 71 0.3355 1.0000 1,0000 1.0000 1.0000 72 0.1678 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)
Note: Surveillance exclusion zone is 8% top, 8% bottom.
)
MILLSTONE - UNIT 3 TRM 8.1-19 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT N)
Table 2 Base Load W(Z) Function Millstone Unit 3 - Cycle 16 Burnup Step (MWDIMTU)
Mesh No. Height* 150 3000 9000 18000 1 12.0778 1.0000 1.0000 1.00 00 1.0000 2 11.9101 1.0000 1.0000 1.0000 1.0000 3 11.7423 1.0000 1.0000 1.0000 1.0000 4 11.5746 1.0000 1.0000 1.0000 1.0000 5 11.4068 1.0000 1.0000 1.0000 1.0000 6 11.2391 1.0000 1.0000 1.0000 1.0000 7 11.0714 1.2140 1.2006 1.2076 1.1821 8 10.9036 1.2174 1.1974 1.2106 1.1769 9 10.7359 1.2131 1.1914 1.2120 1.1738 10 10.5681 1.2111 1.1774 1.2113 1.1703 11 10.4004 1.2050 1.1766 1.2078 1.1653 12 10.2326 1.1949 1.1773 1.2033 1.1599 13 10.0649 1.1853 1.1779 1.1985 1.1577 14 9.8971 1.1753 1.1754 1.1911 1.1573 15 9.7294 1.1657 1.1692 1.1821 1.1566 16 9.5616 1.1568 1.1630 1.1723 1.1555 17 9.3939 1.1471 1.1537 1.1642 1.1527 1.1394 1.1533
) 18 19 9.2261 9.0584 1.1356 1.1272 1.1282 1.1448 1.1467 1.1380 20 8.8906 1.1243 1.1219 1.1394 1.1276 21 8.7229 1.1253 1.1198 1.1358 1.1175 22 8.5551 1.1279 1.1199 1.1340 1.1116 23 8.3874 1.1301 1.1212 1.1316 1.1136 24 8.2196 1.1316 1.1231 1.1286 1.1203 25 8.0519 1.1352 1.1263 1.1311 1.1299 26 7.8841 1.1394 1.1300 1.1358 1.1408 27 7.7164 1.1418 1.1334 1.1382 1.1496 28 7.5487 1.1430 1.1357 1.1394 1.1571 29 7.3809 1.1432 1.1368 1.1397 1.1633 30 7.2131 1.1423 1.1368 1.1389 1.1682 31 7.0454 1.1404 1.1359 1.1370 1.1718 32 6.8777 1.1376 1.1340 1.1342 1.1741 33 6.7099 1.1338 1.1312 1.1305 1.1750 34 6.5422 1.1294 1.1278 1.1259 1.1747 35 6.3744 1.1246 1.1238 1.1204 1.1732 36 6.2067 1.1204 1.1191 1.1142 1.1706 37 6.0389 1.1176 1.1133 1.1073 1.1671 38 5.8712 1.1155 1.1078 1.1028 1.1623
- Distance from bottom of active core (feet)
)
Note: Surveillance exclusion zone is 8% top, 8% bottom. I MILLSTONE - UNIT 3 TRM 8.1-20 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 2 (Continued)
Base Load W(Z) Function Millstone Unit 3 - Cycle 16 Burnup Step (MWDIMTU)
Mesh No. Height* 150 3000 9000 18000 39 5.7034 1.1131 1.1035 1.1019 1.1564 40 5.5357 1.1111 1.0998 1.1007 1.1523 41 5.3679 1.1092 1.0969 1.0983 1.1494 42 5.2002 1.1066 1.0950 1.0958 1.1464 43 5.0324 1.1036 1.0931 1.0929 1.1425 44 4.8647 1.1002 1.0908 1.0896 1.1378 45 4.6969 1.0965 1.0882 1.0860 1.1324 46 4.5292 1.0939 1.0873 1.0829 1.1264 47 4.3614 1.0918 1.0872 1.0811 1.1198 48 4.1937 1.0896 1.0873 1.0804 1.1128 49 4.0259 1.0876 1.0872 1.0809 1.1054 50 3.8582 1.0887 1.0869 1.0828 1.0977 51 3.6905 1.0892 1.0875 1.0846 1.0899 52 3.5227 1.0896 1.0883 1.0861 1.0835 53 3.3550 1.0898 1.0891 1.0875 1.0816 54 3.1872 1.0898 1.0896 1.0887 1.0798 55 3.0195 1.0907 1.0900 1.0898 1.0804 56 2.8517 1.0969 1.0969 1.0927 1.0854 57 2.6840 1.1101 1.1119 1.0990 1.0947 58 2.5162 1.1238 1.1275 1.1072 1.1043 59 2.3485 1.1368 1.1428 1.1159 1.1136 60 2.1807 1.1502 1.1584 1.1245 1.1231 61 2.0130 1.1635 1.1740 1.1330 1.1327 62 1.8452 1.1765 1.1893 1.1413 1.1420 63 1.6775 1.1891 1.2040 1.1492 1.1511 64 1.5097 1.2008 1.2178 1.1584 1.1596 65 1.3420 1.2116 1.2305 1.1674 1.1675 66 1.1742 1.2208 1.2416 1.1750 1.1741 67 1.0065 1.2277 1.2501 1.1804 1.1785 68 0.8387 1.0000 1.0000 1.0000 1.0000 69 0.6710 1.0000 1.0000 1.0000 1.0000 70 0.5032 1.0000 1.0000 1.0000 1.0000 71 0.3355 1.0000 1.0000 1.0000 1.0000 72 0.1678 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)
Note: Surveillance exclusion zone is 8% top, 8% bottom.
.)
MILLSTONE - UNIT 3 TRM 8.1-21 LBDCR 13-MP3-005
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 16 Mesh No Height (ft)* W(z) 1 12.0778 1.0000 2 11.9101 1.0000 3 11.7423 1.0000 4 11.5746 1.0000 5 11.4068 1.0000 6 11.2391 1.0000 7 11.0714 1.2444 8 10.9036 1.2364 9 10.7359 1.2267 10 10.5681 1.2135 11 10.4004 1.1987 12 10.2326 1.1830 13 10.0649 1.1674 14 9.8971 1.1514 15 9.7294 1.1363 16 9.5616 1.1226 17 9.3939 1.1102 18 9.2261 1.0983 19 9.0584 1.0848 20 8:8906 1.0756 21 8.7229 1.0750 22 8.5551 1.0780 23 8.3874 1.0817 24 8.2196 1.0847 25 8.0519 1.0868 26 7.8841 1.0883 27 7.7164 1.0893 28 7.5487 1.0901 29 7.3809 1.0906 30 7.2132 1.0907 31 7.0454 1.0902 32 6.8777 1.0897 33 6.7099 1.0888 34 6.5422 1.0861 35 6.3744 1.0877 36 6.2067 1.0947 37 6.0389 1.1020 38 5.8712 1.1091 39 5.7034 1.1181
- Distance from bottom of active core (feet)
Note: Surveillance exclusion zone is 8% top, 8% bottom.
MILLSTONE - UNIT 3 TRM 8.1-22 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 3 (Continued)
Part Power (74% RTP, 150 MWDIMTU) RAOC W(Z) Function Millstone Unit 3 - Cycle 16 Mesh No Height (ft)* W(z) 40 5.5357 1.1274 41 5.3679 1.1368 42 5,2002 1.1460 43 5.0324 1.1561 44 4.8647 1.1670 45 4.6969 1.1768 46 4.5292 1.1854 47 4.3614 1.1929 48 4.1937 1.1996 49 4.0259 1.2057 50 3.8582 1.2109 51 3.6905 1.2150 52 3.5227 1.2175 53 3.3550 1.2187 54 3.1872 1.2223 55 3.0195 1.2323 56 2.8517 1.2505 57 2.6840 1.2726
) 58 2.5162 1.2997 59 2.3485 1.3290 60 2.1807 1.3572 61 2,0130 1.3853 62 1.8452 1.4136 63 1.6775 1.4415 64 1.5097 1.4673 65 1.3420 1.4931 66 1.1742 1.5174 67 1.0065 1.5295 68 0.8387 1.0000 69 0.6710 1.0000 70 0;5032 1.0000 71 0.3355 1.0000 72 0.1678 1.0000 73 0.0000 1.0000
- Distance from bottom of active core (feet)
Note: Surveillance exclusion zone is 8% top, 8% bottom.
MILLSTONE - UNIT 3 TRM 8.1-23 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 4 Burnup Penalty for Incore Millstone Unit 3 - Cycle 16 I Burnup Penalty All Burnups 1.02
)
MILLSTONE - UNIT 3 TRM 8.1-24 LBDCR 13-MP3-005
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 (Westinghouse Proprietary). (Methodology for Specifications 2.1.1.1-Departure from Nucleate Boiling Ratio, 2.1.1.2-Peak Fuel Centerline Temperature, 3.1.1.3-Moderator Temperature Coefficient, 3.1.3.5-Shutdown Bank Insertion Limit, 3.1.3.6-Control Bank Insertion Limits, 3.2.1-AXIAL FLUX DIFFERENCE, 3.2.2-Heat Flux Hot Channel Factor, 3.2.3-Nuclear Enthalpy Rise Hot Channel Factor, 3.1.1.1.1, 3.1.1.1.2, 3.1.1.2-SHUTDOWN MARGIN, 3.9.1.1-Boron Concentration.)
3.2 WCAP-10216-P-A-RJA, "Relaxation of Constant Axial Offset Control FQ Surveillance Technical Specification," Rev. 1, February 1994 (Westinghouse Proprietary). (Methodology for Specifications 3.2.1-AXIAL FLUX DIFFERENCE [Relaxed Axial Offset Control] and 3.2.2-Heat Flux Hot Channel Factor [W(Z) surveillance requirements for FQ Methodology].)
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 (Westinghouse Proprietary. (Methodology for Specifications 3.2.2-Heat Flux Hot Channel Factor.)
3.4 WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," January 2005 (Westinghouse Proprietary). (Methodology for Specifications 3.2.2-Heat Flux Hot Channel Factor.)
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 (Westinghouse Proprietary).
3.6 WCAP-1 0054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985 (Westinghouse Proprietary).
(Methodology for Specification 3.2.2-Heat Flux Hot Channel Factor.)
3.7 WCAP-10079-P-A, "NOTRUMP - A Nodal Transient Small Break and General Network Code," August 1985 (Westinghouse Proprietary).
(Methodology for Specification 3.2.2-Heat Flux Hot Channel Factor.)
3.8 WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Report," April 1995 (Westinghouse Proprietary). (Methodology for Specification 3.2.2-Heat Flux Hot Channel Factor.)
MILLSTONE - UNIT 3 TRM 8.1-25 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 3.9
-, WCAP-8301, "LOCTA-IV Program: Loss-of Coolant Transient Analysis,"
June 1974 (Westinghouse 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 (Westinghouse Proprietary).
3.11 WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," September 1986 (Westinghouse Proprietary). (Methodology for Specifications 2.1.1 and 2.2.1.)
3.12 WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO TM," July 2006 (Westinghouse Proprietary). (Methodology for Specification 3.2.2-Heat Flux Hot Channel Factor.)
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