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| number = ML15093A225 | | number = ML15093A225 | ||
| issue date = 03/25/2015 | | issue date = 03/25/2015 | ||
| title = | | title = Core Operating Limits Report, Cycle 17 | ||
| author name = Blakeney D | | author name = Blakeney D | ||
| author affiliation = Dominion Nuclear Connecticut, Inc | | author affiliation = Dominion Nuclear Connecticut, Inc | ||
| addressee name = | | addressee name = | ||
| Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:Dominion Nuclear Connecticut, Inc. | ||
P.O. Box | Rope Ferry Rd., Warerford, CT 06385 ~Dominion Mailing Address: P.O. Box 128 Waterford, CT 06385 MAR 2 5 206. | ||
Document Control | dorn.com U.S. Nuclear Regulatory Commission Serial No. 15-129 Attention: Document Control Desk NSS&L/MLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC. | ||
: 1) Editorial changes to increment the Cycle number from 16 to 17.2) The addition of a footnote to indicate that the SHUTDOWN MARGIN requirements in COLR Sections 2.4.and 2.5 are based on cycle specific analyses performed | MILLSTONE POWER STATION UNIT 3 CORE OPERATING LIMITS REPORT, CYCLE 17 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 Enclosure 1, the Cycle 17 Core Operating Limits Report (COLR). | ||
: 3) The revision to a footnote to indicate that the requirements in COLR Section 2. | The MPS3 COLR has been revised to incorporate the following: | ||
: 4) Cycle 17-specific changes to the W(Z) values.5) Cycle 17-specific changes to the burnup penalties for incore (FQ(Z)) surveillance. | : 1) Editorial changes to increment the Cycle number from 16 to 17. | ||
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. | : 2) The addition of a footnote to indicate that the SHUTDOWN MARGIN requirements in COLR Sections 2.4.and 2.5 are based on cycle specific analyses performed by Dominion. | ||
Sincerely, D. B. | : 3) The revision to a footnote to indicate that the requirements in COLR Section 2.14 are based on cycle specific analyses performed by Dominion. | ||
-Millstone | : 4) Cycle 17-specific changes to the W(Z) values. | ||
: 5) Cycle 17-specific changes to the burnup penalties for incore (FQ(Z)) surveillance. | |||
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, D. B. Blakeney Director, Nuclear Station Safety and Licensing - Millstone A cij | |||
Serial No. 15-129 Docket No. 50-423 Core Operating Limits Report, Cycle 17 Page 2 of 2 | |||
==Enclosures:== | ==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 Mohan C. Thadani NRC Senior Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08 B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station | |||
Serial No. 15-129 Docket No. 50-423 ENCLOSURE 1. | |||
CORE OPERATING LIMITS REPORT, CYCLE 17 DOMINION NUCLEAR CONNECTICUT, INC. | |||
MILLSTONE POWER STATION UNIT 3 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT MILLSTONE UNIT 3 CYCLE 17 CORE OPERATING LIMITS REPORT MILLSTONE - UNiT 3 TRM 8.1-1 LBDCR 14-MP3-010 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table of Contents Section Title Paqe 1.0 CORE OPERATING LIMITS REPORT ..................................................................... 8.1-4 2.0 O perating Lim its .......................................................................................................... 8.1-4 2.1 Safety 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) .... 8.1-8 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) ..................................... 8.1-10 3.0 Analytical Methods .................................................................................................... 8.1-26 MILLSTONE - UNIT 3 TRM 8.1-2 LBDCR 13-MP3-005 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT List of Figures Title Page Figure 1 Reactor Core Safety Lim it................................................................................... 8.1-11 Figure 2 Required SHUTDOWN MARGIN for MODE 3 .................................................... 8.1-12 Figure 3 Required SHUTDOW N MARGIN for MODE 4 .................................................... 8.1-13 Figure 4 Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Filled ............... 8.1-14 Figure 5 Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Not Filled ......... 8.1-15 Figure 6 Control Rod Bank Insertion Limits versus THERMAL POWER .......................... 8.1-16 Figure 7 AXIAL FLUX DIFFERENCE Limits as a Function of RATED THERMAL POWER8.1-17 Figure 8 K(Z) - Normalized FQ(Z) as a Function of Core Height ....................................... 8.1-18 List of Tables Table Title Page Table 1 RAOC W(Z) Function, Millstone Unit 3 - Cycle 17 -12/+9 AFD at 100% RTP.8.1-19 Table 2 Base Load W(Z) Function Millstone Unit 3 - Cycle 17 ................ 8.1-21 Table 3 Part Power (74% RTP, 150 MWD/MTU) RAOC W(Z) Function Millstone Unit 3 - | |||
C ycle 17 .......................................................................................................... 8 .1-2 3 Table 4 Burnup Penalty for Incore Millstone Unit 3 - Cycle 17 ..................................... 8.1-25 MILLSTONE - UNIT 3 TRMV 8.1-3 LBDCR 14-MP3-010 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Millstone Unit 3 Cycle 17 CORE OPERATING LIMITS REPORT 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Millstone Unit 3 Cycle 17 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 14-MP3-010 | |||
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/ 0 F 2.2.1.3 K3 0.00113/ psi 2.2.1.4 c Ž8 seconds 2.2.1.5 "C2 | |||
* 3 seconds 2.2.1.6 r4 Ž> 20 seconds 2.2.1.7 r5 *4 seconds 2.2.1.8 T' is loop specific indicated Tavg 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%, f, (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 K4 <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/ 0F when T > T" and <010/°F when T* T" 2.2.2.4 cl > 8 seconds 2.2.2.5 t2 < 3 seconds 2.2.2.6 Deleted 2.2.2.7 T" is loop specific indicated Tavg at RATED THERMAL POWER, _ 587.1OF 2.3 SHUTDOWN MARGIN - MODE I 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 314.1.1.1.2) 2.4.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 2, 3 and 4.1 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. 1 2.6 Moderator Temperature Coefficient, (Specification 314.1.1.3) 2.6.1 The BOL/AROI0%.- 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/kI0 F at 100% RTP. | |||
2.6.2 The EOLIARO/RTP MTC shall be less negative than - 5.65 x 10-4 Ak/k/i.0 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 | |||
'The SHUTDOWN MARGIN requirements in Figures 2, 3, 4 and 5 are based on cycle-specific boron dilu-tion analyses performed by Dominion. | |||
MILLSTONE - UNIT 3 TRM 8.1-6 LBDCR 14-MP3-010 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 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 314.1.3.5) 2.7.1 The shutdown rods shall be at least 220 steps withdrawn (inclusive). | |||
2.8 Control Rod Insertion Limits (Specification 314.1.3.6) 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 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. | |||
2.10 Heat Flux Hot Channel Factor =FQ(Z) (Specification 3/4.2.2.1) | |||
SR TP FQ(Z)*< Q x K(Z) for P > 0.5 | |||
/P FQ(Z) < -0.5--. 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. | |||
MILLSTONE - UNIT 3 TRM 8.1-7 LBDCR 13-MP3-005 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.11 Heat Flux Hot Channel Factor Surveillance - FQ(Z) (Specification 3/ | |||
4.2.2.1.2) iPX K(Z) | |||
F(Z) xW(Z) for P > 0.5 F RTPK(Z) | |||
FQ(Z) Q 0.xfor P 0.5 0.5 xW(Z) where: p - THERMAL POWER RATED THERMAL POWER 2.11.1 FRTPQ = 2 .6 0 . | |||
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 17 burnup dependent RAOC W(Z) values are valid over the range of burnup from 0 to 21,600 MWDIMTU. | |||
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 17 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 17 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 - | |||
FN AH (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]) | |||
MILLSTONE - UNIT 3 TRM 8.1-8 LBDCR 14-MP3-010 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 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. | |||
2.13 DNB Parameters (Specification 314.2.5) 2.13.1 Indicated Reactor Coolant System Tavg shall be maintained < | |||
593.5°F. | |||
2.13.2 Indicated Pressurizer Pressure shall be maintained _>2204 psia 2. | |||
2.14 Shutdown Margin Monitor Alarm Setpoint (Specification 314.3.5)3 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 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. | |||
3 Section 2.14 is based on cycle-specific boron dilution analyses performed by Dominion. | |||
MILLSTONE - UNIT 3 TRM 8.1-9 LBDCR 14-MP3-010 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.15 Refueling Boron Concentration (Specification 314.9.1.1) 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 4 | |||
concentration of greater than or equal to 2600 ppm. | |||
4 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). | |||
MILLSTONE - UNIT 3 TRM 8.1 -10 LBDCR 13-MP3-005 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure I Reactor Core Safety Limit 680 660 640 d | |||
w 0 | |||
6 620 I-Cl) 0 600 580 560 0 0.2 0.4 0.6 0.8 1 1.2 FRACTION OF RATED THERMAL POWER MILLSTONE - UNIT 3 TRM 8.1-11 LBDCR 13-MP3-005 | |||
Figure 2 Required SHUTDOWN MARGIN for MODE 3 4.0 3.5 3.0 2.5 z | |||
2.0 0 1.5 3: | |||
U) 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 3 Required SHUTDOWN MARGIN for MODE 4 6.0 5.5 5.0 4.5 S4.0 zi53.5 S3.0 z | |||
S2.5 0 | |||
'2.0 | |||
:=: | |||
.j _ | |||
1.5 1.0 0.5 0.0 0 500 1000 1500 2000 2500 RCS CRITICAL BORON CONCENTRATION (ppm) | |||
TRM 8.1-13 MILLSTONE - UNIT 3 LBDCR 13-MP3-005 | |||
Figure 4 Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Filled 5.5 4.5 4.0, z3. | |||
3.0 2.5 012. | |||
0 1000 115,00 2000 2500 RCSCRITICAL BORON ,CONCENTRATION (ppm) | |||
TRM 8.1-14 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 (15,5.523) ,,*- (2500, 6.150) 5.5 S5.0 4.5 z | |||
(D 4.0 | |||
_ 3.5 R3.0 0 | |||
2.5 2.0 (0, 1.300) 1.5 Af 1.0 (355, 1.300) 0.5 0.0 0 500 1000 1500 2000 2500 RCS CRITICAL BORON CONCENTRATION (ppm) | |||
TRM 8.1-15 MILLSTONE - UNIT 3 LBDCR 13-MP3-005 | |||
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 | |||
( 120 o 100 c" 80 0 | |||
60 40 20 0 | |||
0 10 20 30 40 50 60 70 80 90 100 RATED THERMAL POWER (%) | |||
MILLSTONE - UNIT 3 TRM 8.1-16 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 0 | |||
E 60 5! | |||
40 20 0 | |||
50 -40 -30 -20 -10 0 10 20 30 40 50 60 Flux Difference, % Delta-I MILLSTONE - UNIT 3 TRM 8.1-17 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 LL C) 0.6 03 (D | |||
0.5 0.4 0 | |||
_2) Ele-a n 0.3 1D 0.0 Ft In 6.0 Ft 0.M5 12J. Ft -I 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 8.1-18 LBDCR 13-MP3-005 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table I RAOC W(Z) Function, Millstone Unit 3 - Cycle 17 | |||
-121+9 AFD at 100% RTP Burnup Step (MWDIMTU) | |||
Mesh No. Height* 150 2000 10000 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 1.2946 1.3691 1.4103 1.3092 8 10.9036 1.2917 1.3622 1.4065 1.3060 9 10.7359 1.2839 1.3502 1.4071 1.2996 10 10.5681 1.2680 1.3322 1.3955 1.2900 11 10.4004 1.2473 1.3107 1.3747 1.2780 12 10.2326 1.2266 1.2883 1.3542 1.2646 13 10.0649 1.2093 1.2651 1.3338 1.2501 14 9.8971 1.1928 1.2392 1.3107 1.2399 15 9.7294 1.1746 1.2122 1.2874 1.2345 16 9.5616 1.1577 1.1936 1.2664 1.2318 17 9.3939 1.1446 1.1806 1.2499 1.2290 18 9.2261 1.1354 1.1677 1.2378 1.2225 19 9.0584 1.1270 1.1563 1.2276 1.2133 20 8.8906 1.1239 1.1503 1.2199 1.2024 21 8.7229 1.1260 1.1491 1.2159 1.2033 22 8.5551 1.1301 1.1492 1.2135 1.2082 23 8.3874 1.1331 1.1483 1.2106 1.2137 24 8.2196 1.1352 1.1465 1.2068 1.2181 25 8.0519 1.1369 1.1481 1.2062 1.2213 26 7.8841 1.1378 1.1510 1.2060 1.2234 27 7.7164 1.1378 1.1518 1.2038 1.2242 28 7.5487 1.1368 1.1515 1.2002 1.2235 29 7.3809 1.1352 1.1503 1.1953 1.2215 30 7.2131 1.1327 1.1479 1.1891 1.2180 31 7.0454 1.1288 1.1447 1.1817 1.2134 32 6.8777 1.1263 1.1403 1.1732 1.2072 33 6.7099 1.1260 1.1350 1.1635 1.1999 34 6.5422 1.1257 1.1310 1.1529 1.1928 35 6.3744 1.1249 1.1282 1.1416 1.1859 36 6.2067 1.1235 1.1255 1.1296 1.1782 37 6.0389 1.1207 1.1214 1.1169 1.1693 38 5.8712 1.1195 1.1192 1.1072 1.1597 | |||
* Distance from bottom of active core (feet) | |||
Note: Surveillance exclusion zone is 8% top, 8% bottom. | |||
MILLSTONE - UNIT 3 TRM 8.1-19 LBDCR 15-MP3-001 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table I (Continued) | |||
RAOC W(Z) Function, Millstone Unit 3 - Cycle 17 | |||
-121+9 AFD at 100% RTP Burnup Step (MWDIMTU) | |||
Mesh No. | |||
39 Height* | |||
5.7034 150 1.1208 2000 1.1214 10000 1.1036 18000 1.1517 I | |||
40 5.5357 1.1277 1.1279 1.1045 1.1499 41 5.3679 1.1365 1.1350 1.1066 1.1495 42 5.2002 1.1440 1.1412 1.1077 1.1493 43 5.0324 1.1510 1.1469 1.1080 1.1482 44 4.8647 1.1576 1.1521 1.1089 1.1465 45 4.6969 1.1637 1.1570 1.1111 1.1439 46 4.5292 1.1694 1.1633 1.1135 1.1409 47 4.3614 1.1746 1.1701 1.1156 1.1369 48 4.1937 1.1794 1.1762 1.1175 1.1325 49 4.0259 1.1838 1.1818 1.1192 1.1301 50 3.8582 1.1877 1.1871 1.1207 1.1301 51 3.6905 1.1914 1.1919 1.1232 1.1316 52 3.5227 1.1946 1.1967 1.1278 1.1329 53 3.3550 1.1977 1.2002 1.1321 1.1336 54 3.1872 1.2027 1.2044 1.1361 1.1343 55 3.0195 1.2145 1.2142 1.1399 1.1362 56 2.8517 1.2301 1.2320 1.1451 1.1442 57 2.6840 1.2450 1.2536 1.1532 1.1550 58 2.5162 1.2601 1.2755 1.1634 1.1659 59 2.3485 1.2749 1.2971 1.1742 1.1765 60 2.1807 1.2894 1.3186 1.1847 1.1872 61 2.0130 1.3056 1.3397 1.1950 1.1977 62 1.8452 1.3229 1.3602 1.2051 1.2079 63 1.6775 1.3397 1.3797 1,2146 1.2176 64 1.5097 1.3554 1.3978 1.2233 1.2267 65 1.3420 1.3698 1.4145 1.2312 1.2350 66 1.1742 1.3822 .1.4291 1.2389 1.2421 67 1.0065 1.3917 1.4404 1.2445 1.2468 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 8.1-20 LBDCR 15-MP3-001 | |||
TECHMCAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 2 Base Load W(Z) Function Millstone Unit 3 - Cycle 17 Burnup Step (MWDIMTU) | |||
Mesh No. Height* 150 2000 10000 18000 I I 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 1.1567 1.1739 1.2102 1.1645 8 10.9036 1.1552 1.1768 1.2169 1.1615 9 10.7359 1.1519 1.1802 1.2246 1.1586 10 10.5681 1.1476 1.1800 1.2215 1.1544 11 10.4004 1.1425 1.1741 1.2107 1.1515 12 10.2326 1.1368 1.1691 1.2012 1.1517 13 10.0649 1.1325 1.1632 .1.1953 1.1524 14 9.8971 1.1268 1.1554 1.1881 1.1523 15 9.7294 1.1201 1.1466 1.1782 1.1506 16 9.5616 1.1144 1.1376 1.1684 1.1485 17 9.3939 1.1090 1.1287 1.1570 1.1452 18 9.2261 1.1034 1.1218 1.1423 1.1392 19 9.0584 1.0981 1.1145 1.1286 1.1312 20 8.8906 1.0968 1.1115 1.1163 1.1215 21 8.7229 1.1011 1.1136 1.1128 1.1124 22 8.5551 1.1062 1.1177 1.1167 1.1078 23 8.3874 1.1109 1.1216 1.1207 1.1103 24 8.2196 1.1156 1.1252 1.1244 1.1175 25 8.0519 1.1198 1.1281 1..1273 1.1270 26 7.8841 1.1232 1.1301 1.1295 1.1374 27 7.7164 1.1257 1.1313 1.1309 1.1459 28 7.5487 1.1273 .1.1316 1.1314 1.1530 29 7.3809 1.1281 1.1311 1.1311 1.1590 30 7.2131 1.1281 1.1298 1.1299 1.1637 31 7.0454 1.1270 1.1274 1.1281 1.1671 32 6.8777 1.1260 1.1253 1.1253 1.1692 33 6.7099 1.1259 1.1244 1.1218 1.1700 34 6.5422 1.1257 1.1231 1.1195 1.1696 35 6.3744 1.1249 1.1211 1.1177 1.1681 36 6.2067 1.1234 1.1183 1.1152 1.1655 37 6.0389 1.1210 1.1147 1.1120 1.1621 38 5.8712 1.1184 1.1111 1.1078 1.1573 | |||
* Distance from bottom of active core (feet) | |||
Note: Surveillance exclusion zone is 8% top, 8% bottom. | |||
MILLSTONE - UNIT 3 TRM 8.1-21 LBDCR 15-MP3-001 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 2 (Continued) | |||
Base Load W(Z) Function Millstone Unit 3 - Cycle 17 Burnup Step (MWDIMTU) | |||
Mesh No. | |||
39 Height* | |||
5.7034 150 1.1163 2000 1.1081 10000 1.1031 18000 1.1516 I 40 5.5357 1.1140 1.1063 1.1012 1.1477 41 5.3679 1.1120 1.1049 1.1007 1.1452 42 5.2002 1.1109 1.1030 1.0995 1.1424 43 5.0324 1.1094 1.1007 1.0978 1.1387 44 4.8647 1.1073 1.0980 1.0959 1.1343 45 4.6969 1.1050 1.0951 1.0936 1.1293 46 4.5292 1.1023 1.0917 1.0911 1.1236 47 4.3614 1.0994 1.0890 1.0884 1.1174 48 4.1937 1.0962 1.0891 1.0856 1.1108 49 4.0259. 1.0928 1.0896 1.0829 1.1038 | |||
: 50. 3.8582 1.0893 1.0904 1.0798 1.0967 51 3.6905 1.0856 1.0914 1.0775 1.0894 52 3.5227 1.0825 1.0920 1.0787 1.0822 53 3.3550 1.0805 1.0925 1.0799 1.0806 54 3.1872 1.0802 1.0928 1.0811 1.0792 55 3.0195 1.0850 1.0930 1.0816 1.0806 56 2.8517 1.0951 1.1031 1.0884 1.0861 57 2.6840 1.1062 1.1178 1.0992 1.0953 58 2.5162 1.1176 1.1331 1.1104 1.1048 59 2.3485 1.1292 1.1481 1.1215 1.1141 60 2.1807 1.1409 1.1634 1.1328 1.1236 61 2.0130 1.1524 1.1785 1.1439 1.1331 62 1.8452 1.1637 1.1932 1.1548 1.1424 63 1.6775 1A1746 1.2074 1.1653 1.1515 64 1.5097 1.1848 1.2206 1.1750 1.1599 65 1.3420 1.1940 1.2328 1.1838 1.1677 66 1.1742 1.2019 1.2433 1.1913 1.1744 67 1.0065 1.2077 1.2513 1.1964 1.1787 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 8.1-22 LBDCR 15-MP3-001 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 3 Part Power (74% RTP, 150 MWD/IMTU) RAOC W(Z) Function Millstone Unit 3 - Cycle 17 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 1.1491 8 10.9036 1.1446 9 10.7359 1.1366 10 10.5681 1.1228 11 10.4004 1.1065 12 10.2326 1.0907 13 10.0649 1.0784 14 9.8971 1.0673 15 9.7294 1.0557 16 9.5616 1.0456 17 9.3939 1.0416 18 9.2261 1.0385 19 9.0584 1.0353 20 8.8906 1.0373 21 8.7229 1.0442 22 8.5551 1.0527 23 8.3874 1.0602 24 8.2196 1.0671 25 8.0519 1.0735 26 7.8841 1.0789 27 7.7164 1.0836 28 7.5487 1.0874 29 7.3809 1.0906 30 7.2132 1.0928 31 7.0454 1.0935 32 6.8777 1.0954 33 6.7099 1.0993 34 6.5422 1.1033 35 6.3744 1.1067 36 6.2067 1.1097 37 6.0389 1.1116 38 5.8712 1.1150 39 5.7034 1.1210 | |||
* Distance from bottom of active core (feet) | |||
Note: Surveillance exclusion zone is 8% top, 8% bottom. | |||
MILLSTONE - UNIT 3 TRM 8.1-23 LBDCR 14-MP3-010 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 3 (Continued) | |||
Part Power (74% RTP, 150 MWD/iMTU) RAOC W(Z) Function Millstone Unit 3 - Cycle 17 Mesh No Height (ft)* W(z) 40 5.5357 1.1327 41 5.3679 1.1461 42 5.2002 1.1584 43 5.0324 1.1702 44 4.8647 1.1818 45 4.6969 1.1927 46 4.5292 1.2029 47 4.3614 1.2126 48 4.1937 1.2218 49 4.0259 1.2307 50 3.8582 1.2394 51 3.6905 1.2475 52 3.5227 1.2551 53 3.3550 1.2626 54 3.1872 1.2719 55 3.0195 1.2883 56 2.8517 1.3087 57 2.6840 1.3283 58 2.5162 1.3484 59 2.3485 1.3685 60 2.1807 1.3882 61 2.0130 1.4094 62 1.8452 1.4316 63 1.6775 1.4536 64 1.5097 1.4744 65 1.3420 1.4940 66 1.1742 1.5118 67 1.0065 1.5262 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 8.1-24 LBDCR 14-MP3-010 | |||
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 4 Burnup Penalty for Incore Millstone Unit 3 - Cycle 17 I Burnup (MWDIMTU) Penalty 1597 1.021 1919 1.025 2080 1.027 3045 1.037 3206 1.036 3366 1.036 4010 1.033 4171 1.030 4975 1.021 | |||
*Note: A Penalty of 1.02 shall be used outside of the burnup range shown in Table 4. | |||
MILLSTONE - UNIT 3 TRMV 8.1-25 LBDCR 14-MP3-010 | |||
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-R1A, "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 8.1-26 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," | |||
Loss-of Coolant Transient Analysis," | |||
June 1974 (Westinghouse Proprietary). | June 1974 (Westinghouse Proprietary). | ||
3.10 WCAP-10054-P-A, Addendum 2, Revision 1, "Addendum to | 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 | 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.) | ||
September 1986(Westinghouse Proprietary). | 3.12 WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO-m," July 2006 (Westinghouse Proprietary). (Methodology for Specification 3.2.2-Heat Flux Hot Channel Factor.) | ||
(Methodology for Specifications 2.1.1 | MILLSTONE - UNIT 3 TRM 8.1-27 LBDCR 13-MP3-005}} | ||
& CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO-m," | |||
July 2006 (Westinghouse Proprietary). | |||
(Methodology | |||
-UNIT | |||
Latest revision as of 13:24, 31 October 2019
| ML15093A225 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/25/2015 |
| From: | Blakeney D Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 15-129 | |
| Download: ML15093A225 (30) | |
Text
Dominion Nuclear Connecticut, Inc.
Rope Ferry Rd., Warerford, CT 06385 ~Dominion Mailing Address: P.O. Box 128 Waterford, CT 06385 MAR 2 5 206.
dorn.com U.S. Nuclear Regulatory Commission Serial No.15-129 Attention: Document Control Desk NSS&L/MLC RO 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 17 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 Enclosure 1, the Cycle 17 Core Operating Limits Report (COLR).
The MPS3 COLR has been revised to incorporate the following:
- 1) Editorial changes to increment the Cycle number from 16 to 17.
- 2) The addition of a footnote to indicate that the SHUTDOWN MARGIN requirements in COLR Sections 2.4.and 2.5 are based on cycle specific analyses performed by Dominion.
- 3) The revision to a footnote to indicate that the requirements in COLR Section 2.14 are based on cycle specific analyses performed by Dominion.
- 4) Cycle 17-specific changes to the W(Z) values.
- 5) Cycle 17-specific changes to the burnup penalties for incore (FQ(Z)) surveillance.
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, D. B. Blakeney Director, Nuclear Station Safety and Licensing - Millstone A cij
Serial No.15-129 Docket No. 50-423 Core Operating Limits Report, Cycle 17 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 Mohan C. Thadani NRC Senior Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08 B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No.15-129 Docket No. 50-423 ENCLOSURE 1.
CORE OPERATING LIMITS REPORT, CYCLE 17 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT MILLSTONE UNIT 3 CYCLE 17 CORE OPERATING LIMITS REPORT MILLSTONE - UNiT 3 TRM 8.1-1 LBDCR 14-MP3-010
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table of Contents Section Title Paqe 1.0 CORE OPERATING LIMITS REPORT ..................................................................... 8.1-4 2.0 O perating Lim its .......................................................................................................... 8.1-4 2.1 Safety 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) .... 8.1-8 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) ..................................... 8.1-10 3.0 Analytical Methods .................................................................................................... 8.1-26 MILLSTONE - UNIT 3 TRM 8.1-2 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT List of Figures Title Page Figure 1 Reactor Core Safety Lim it................................................................................... 8.1-11 Figure 2 Required SHUTDOWN MARGIN for MODE 3 .................................................... 8.1-12 Figure 3 Required SHUTDOW N MARGIN for MODE 4 .................................................... 8.1-13 Figure 4 Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Filled ............... 8.1-14 Figure 5 Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Not Filled ......... 8.1-15 Figure 6 Control Rod Bank Insertion Limits versus THERMAL POWER .......................... 8.1-16 Figure 7 AXIAL FLUX DIFFERENCE Limits as a Function of RATED THERMAL POWER8.1-17 Figure 8 K(Z) - Normalized FQ(Z) as a Function of Core Height ....................................... 8.1-18 List of Tables Table Title Page Table 1 RAOC W(Z) Function, Millstone Unit 3 - Cycle 17 -12/+9 AFD at 100% RTP.8.1-19 Table 2 Base Load W(Z) Function Millstone Unit 3 - Cycle 17 ................ 8.1-21 Table 3 Part Power (74% RTP, 150 MWD/MTU) RAOC W(Z) Function Millstone Unit 3 -
C ycle 17 .......................................................................................................... 8 .1-2 3 Table 4 Burnup Penalty for Incore Millstone Unit 3 - Cycle 17 ..................................... 8.1-25 MILLSTONE - UNIT 3 TRMV 8.1-3 LBDCR 14-MP3-010
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Millstone Unit 3 Cycle 17 CORE OPERATING LIMITS REPORT 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Millstone Unit 3 Cycle 17 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 14-MP3-010
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/ 0 F 2.2.1.3 K3 0.00113/ psi 2.2.1.4 c Ž8 seconds 2.2.1.5 "C2
- 3 seconds 2.2.1.6 r4 Ž> 20 seconds 2.2.1.7 r5 *4 seconds 2.2.1.8 T' is loop specific indicated Tavg 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%, f, (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 K4 <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/ 0F when T > T" and <010/°F when T* T" 2.2.2.4 cl > 8 seconds 2.2.2.5 t2 < 3 seconds 2.2.2.6 Deleted 2.2.2.7 T" is loop specific indicated Tavg at RATED THERMAL POWER, _ 587.1OF 2.3 SHUTDOWN MARGIN - MODE I 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 314.1.1.1.2) 2.4.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 2, 3 and 4.1 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. 1 2.6 Moderator Temperature Coefficient, (Specification 314.1.1.3) 2.6.1 The BOL/AROI0%.- 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/kI0 F at 100% RTP.
2.6.2 The EOLIARO/RTP MTC shall be less negative than - 5.65 x 10-4 Ak/k/i.0 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
'The SHUTDOWN MARGIN requirements in Figures 2, 3, 4 and 5 are based on cycle-specific boron dilu-tion analyses performed by Dominion.
MILLSTONE - UNIT 3 TRM 8.1-6 LBDCR 14-MP3-010
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 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 314.1.3.5) 2.7.1 The shutdown rods shall be at least 220 steps withdrawn (inclusive).
2.8 Control Rod Insertion Limits (Specification 314.1.3.6) 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 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.
2.10 Heat Flux Hot Channel Factor =FQ(Z) (Specification 3/4.2.2.1)
SR TP FQ(Z)*< Q x K(Z) for P > 0.5
/P FQ(Z) < -0.5--. 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.
MILLSTONE - UNIT 3 TRM 8.1-7 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.11 Heat Flux Hot Channel Factor Surveillance - FQ(Z) (Specification 3/
4.2.2.1.2) iPX K(Z)
F(Z) xW(Z) for P > 0.5 F RTPK(Z)
FQ(Z) Q 0.xfor P 0.5 0.5 xW(Z) where: p - THERMAL POWER RATED THERMAL POWER 2.11.1 FRTPQ = 2 .6 0 .
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 17 burnup dependent RAOC W(Z) values are valid over the range of burnup from 0 to 21,600 MWDIMTU.
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 17 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 17 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 -
FN AH (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])
MILLSTONE - UNIT 3 TRM 8.1-8 LBDCR 14-MP3-010
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 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.
2.13 DNB Parameters (Specification 314.2.5) 2.13.1 Indicated Reactor Coolant System Tavg shall be maintained <
593.5°F.
2.13.2 Indicated Pressurizer Pressure shall be maintained _>2204 psia 2.
2.14 Shutdown Margin Monitor Alarm Setpoint (Specification 314.3.5)3 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 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.
3 Section 2.14 is based on cycle-specific boron dilution analyses performed by Dominion.
MILLSTONE - UNIT 3 TRM 8.1-9 LBDCR 14-MP3-010
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.15 Refueling Boron Concentration (Specification 314.9.1.1) 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 4
concentration of greater than or equal to 2600 ppm.
4 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).
MILLSTONE - UNIT 3 TRM 8.1 -10 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure I Reactor Core Safety Limit 680 660 640 d
w 0
6 620 I-Cl) 0 600 580 560 0 0.2 0.4 0.6 0.8 1 1.2 FRACTION OF RATED THERMAL POWER MILLSTONE - UNIT 3 TRM 8.1-11 LBDCR 13-MP3-005
Figure 2 Required SHUTDOWN MARGIN for MODE 3 4.0 3.5 3.0 2.5 z
2.0 0 1.5 3:
U) 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 3 Required SHUTDOWN MARGIN for MODE 4 6.0 5.5 5.0 4.5 S4.0 zi53.5 S3.0 z
S2.5 0
'2.0
- =:
.j _
1.5 1.0 0.5 0.0 0 500 1000 1500 2000 2500 RCS CRITICAL BORON CONCENTRATION (ppm)
TRM 8.1-13 MILLSTONE - UNIT 3 LBDCR 13-MP3-005
Figure 4 Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Filled 5.5 4.5 4.0, z3.
3.0 2.5 012.
0 1000 115,00 2000 2500 RCSCRITICAL BORON ,CONCENTRATION (ppm)
TRM 8.1-14 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 (15,5.523) ,,*- (2500, 6.150) 5.5 S5.0 4.5 z
(D 4.0
_ 3.5 R3.0 0
2.5 2.0 (0, 1.300) 1.5 Af 1.0 (355, 1.300) 0.5 0.0 0 500 1000 1500 2000 2500 RCS CRITICAL BORON CONCENTRATION (ppm)
TRM 8.1-15 MILLSTONE - UNIT 3 LBDCR 13-MP3-005
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
( 120 o 100 c" 80 0
60 40 20 0
0 10 20 30 40 50 60 70 80 90 100 RATED THERMAL POWER (%)
MILLSTONE - UNIT 3 TRM 8.1-16 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 0
E 60 5!
40 20 0
50 -40 -30 -20 -10 0 10 20 30 40 50 60 Flux Difference, % Delta-I MILLSTONE - UNIT 3 TRM 8.1-17 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 LL C) 0.6 03 (D
0.5 0.4 0
_2) Ele-a n 0.3 1D 0.0 Ft In 6.0 Ft 0.M5 12J. Ft -I 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 8.1-18 LBDCR 13-MP3-005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table I RAOC W(Z) Function, Millstone Unit 3 - Cycle 17
-121+9 AFD at 100% RTP Burnup Step (MWDIMTU)
Mesh No. Height* 150 2000 10000 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 1.2946 1.3691 1.4103 1.3092 8 10.9036 1.2917 1.3622 1.4065 1.3060 9 10.7359 1.2839 1.3502 1.4071 1.2996 10 10.5681 1.2680 1.3322 1.3955 1.2900 11 10.4004 1.2473 1.3107 1.3747 1.2780 12 10.2326 1.2266 1.2883 1.3542 1.2646 13 10.0649 1.2093 1.2651 1.3338 1.2501 14 9.8971 1.1928 1.2392 1.3107 1.2399 15 9.7294 1.1746 1.2122 1.2874 1.2345 16 9.5616 1.1577 1.1936 1.2664 1.2318 17 9.3939 1.1446 1.1806 1.2499 1.2290 18 9.2261 1.1354 1.1677 1.2378 1.2225 19 9.0584 1.1270 1.1563 1.2276 1.2133 20 8.8906 1.1239 1.1503 1.2199 1.2024 21 8.7229 1.1260 1.1491 1.2159 1.2033 22 8.5551 1.1301 1.1492 1.2135 1.2082 23 8.3874 1.1331 1.1483 1.2106 1.2137 24 8.2196 1.1352 1.1465 1.2068 1.2181 25 8.0519 1.1369 1.1481 1.2062 1.2213 26 7.8841 1.1378 1.1510 1.2060 1.2234 27 7.7164 1.1378 1.1518 1.2038 1.2242 28 7.5487 1.1368 1.1515 1.2002 1.2235 29 7.3809 1.1352 1.1503 1.1953 1.2215 30 7.2131 1.1327 1.1479 1.1891 1.2180 31 7.0454 1.1288 1.1447 1.1817 1.2134 32 6.8777 1.1263 1.1403 1.1732 1.2072 33 6.7099 1.1260 1.1350 1.1635 1.1999 34 6.5422 1.1257 1.1310 1.1529 1.1928 35 6.3744 1.1249 1.1282 1.1416 1.1859 36 6.2067 1.1235 1.1255 1.1296 1.1782 37 6.0389 1.1207 1.1214 1.1169 1.1693 38 5.8712 1.1195 1.1192 1.1072 1.1597
- Distance from bottom of active core (feet)
Note: Surveillance exclusion zone is 8% top, 8% bottom.
MILLSTONE - UNIT 3 TRM 8.1-19 LBDCR 15-MP3-001
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table I (Continued)
RAOC W(Z) Function, Millstone Unit 3 - Cycle 17
-121+9 AFD at 100% RTP Burnup Step (MWDIMTU)
Mesh No.
39 Height*
5.7034 150 1.1208 2000 1.1214 10000 1.1036 18000 1.1517 I
40 5.5357 1.1277 1.1279 1.1045 1.1499 41 5.3679 1.1365 1.1350 1.1066 1.1495 42 5.2002 1.1440 1.1412 1.1077 1.1493 43 5.0324 1.1510 1.1469 1.1080 1.1482 44 4.8647 1.1576 1.1521 1.1089 1.1465 45 4.6969 1.1637 1.1570 1.1111 1.1439 46 4.5292 1.1694 1.1633 1.1135 1.1409 47 4.3614 1.1746 1.1701 1.1156 1.1369 48 4.1937 1.1794 1.1762 1.1175 1.1325 49 4.0259 1.1838 1.1818 1.1192 1.1301 50 3.8582 1.1877 1.1871 1.1207 1.1301 51 3.6905 1.1914 1.1919 1.1232 1.1316 52 3.5227 1.1946 1.1967 1.1278 1.1329 53 3.3550 1.1977 1.2002 1.1321 1.1336 54 3.1872 1.2027 1.2044 1.1361 1.1343 55 3.0195 1.2145 1.2142 1.1399 1.1362 56 2.8517 1.2301 1.2320 1.1451 1.1442 57 2.6840 1.2450 1.2536 1.1532 1.1550 58 2.5162 1.2601 1.2755 1.1634 1.1659 59 2.3485 1.2749 1.2971 1.1742 1.1765 60 2.1807 1.2894 1.3186 1.1847 1.1872 61 2.0130 1.3056 1.3397 1.1950 1.1977 62 1.8452 1.3229 1.3602 1.2051 1.2079 63 1.6775 1.3397 1.3797 1,2146 1.2176 64 1.5097 1.3554 1.3978 1.2233 1.2267 65 1.3420 1.3698 1.4145 1.2312 1.2350 66 1.1742 1.3822 .1.4291 1.2389 1.2421 67 1.0065 1.3917 1.4404 1.2445 1.2468 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 8.1-20 LBDCR 15-MP3-001
TECHMCAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 2 Base Load W(Z) Function Millstone Unit 3 - Cycle 17 Burnup Step (MWDIMTU)
Mesh No. Height* 150 2000 10000 18000 I I 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 1.1567 1.1739 1.2102 1.1645 8 10.9036 1.1552 1.1768 1.2169 1.1615 9 10.7359 1.1519 1.1802 1.2246 1.1586 10 10.5681 1.1476 1.1800 1.2215 1.1544 11 10.4004 1.1425 1.1741 1.2107 1.1515 12 10.2326 1.1368 1.1691 1.2012 1.1517 13 10.0649 1.1325 1.1632 .1.1953 1.1524 14 9.8971 1.1268 1.1554 1.1881 1.1523 15 9.7294 1.1201 1.1466 1.1782 1.1506 16 9.5616 1.1144 1.1376 1.1684 1.1485 17 9.3939 1.1090 1.1287 1.1570 1.1452 18 9.2261 1.1034 1.1218 1.1423 1.1392 19 9.0584 1.0981 1.1145 1.1286 1.1312 20 8.8906 1.0968 1.1115 1.1163 1.1215 21 8.7229 1.1011 1.1136 1.1128 1.1124 22 8.5551 1.1062 1.1177 1.1167 1.1078 23 8.3874 1.1109 1.1216 1.1207 1.1103 24 8.2196 1.1156 1.1252 1.1244 1.1175 25 8.0519 1.1198 1.1281 1..1273 1.1270 26 7.8841 1.1232 1.1301 1.1295 1.1374 27 7.7164 1.1257 1.1313 1.1309 1.1459 28 7.5487 1.1273 .1.1316 1.1314 1.1530 29 7.3809 1.1281 1.1311 1.1311 1.1590 30 7.2131 1.1281 1.1298 1.1299 1.1637 31 7.0454 1.1270 1.1274 1.1281 1.1671 32 6.8777 1.1260 1.1253 1.1253 1.1692 33 6.7099 1.1259 1.1244 1.1218 1.1700 34 6.5422 1.1257 1.1231 1.1195 1.1696 35 6.3744 1.1249 1.1211 1.1177 1.1681 36 6.2067 1.1234 1.1183 1.1152 1.1655 37 6.0389 1.1210 1.1147 1.1120 1.1621 38 5.8712 1.1184 1.1111 1.1078 1.1573
- Distance from bottom of active core (feet)
Note: Surveillance exclusion zone is 8% top, 8% bottom.
MILLSTONE - UNIT 3 TRM 8.1-21 LBDCR 15-MP3-001
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 2 (Continued)
Base Load W(Z) Function Millstone Unit 3 - Cycle 17 Burnup Step (MWDIMTU)
Mesh No.
39 Height*
5.7034 150 1.1163 2000 1.1081 10000 1.1031 18000 1.1516 I 40 5.5357 1.1140 1.1063 1.1012 1.1477 41 5.3679 1.1120 1.1049 1.1007 1.1452 42 5.2002 1.1109 1.1030 1.0995 1.1424 43 5.0324 1.1094 1.1007 1.0978 1.1387 44 4.8647 1.1073 1.0980 1.0959 1.1343 45 4.6969 1.1050 1.0951 1.0936 1.1293 46 4.5292 1.1023 1.0917 1.0911 1.1236 47 4.3614 1.0994 1.0890 1.0884 1.1174 48 4.1937 1.0962 1.0891 1.0856 1.1108 49 4.0259. 1.0928 1.0896 1.0829 1.1038
- 50. 3.8582 1.0893 1.0904 1.0798 1.0967 51 3.6905 1.0856 1.0914 1.0775 1.0894 52 3.5227 1.0825 1.0920 1.0787 1.0822 53 3.3550 1.0805 1.0925 1.0799 1.0806 54 3.1872 1.0802 1.0928 1.0811 1.0792 55 3.0195 1.0850 1.0930 1.0816 1.0806 56 2.8517 1.0951 1.1031 1.0884 1.0861 57 2.6840 1.1062 1.1178 1.0992 1.0953 58 2.5162 1.1176 1.1331 1.1104 1.1048 59 2.3485 1.1292 1.1481 1.1215 1.1141 60 2.1807 1.1409 1.1634 1.1328 1.1236 61 2.0130 1.1524 1.1785 1.1439 1.1331 62 1.8452 1.1637 1.1932 1.1548 1.1424 63 1.6775 1A1746 1.2074 1.1653 1.1515 64 1.5097 1.1848 1.2206 1.1750 1.1599 65 1.3420 1.1940 1.2328 1.1838 1.1677 66 1.1742 1.2019 1.2433 1.1913 1.1744 67 1.0065 1.2077 1.2513 1.1964 1.1787 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 8.1-22 LBDCR 15-MP3-001
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 3 Part Power (74% RTP, 150 MWD/IMTU) RAOC W(Z) Function Millstone Unit 3 - Cycle 17 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 1.1491 8 10.9036 1.1446 9 10.7359 1.1366 10 10.5681 1.1228 11 10.4004 1.1065 12 10.2326 1.0907 13 10.0649 1.0784 14 9.8971 1.0673 15 9.7294 1.0557 16 9.5616 1.0456 17 9.3939 1.0416 18 9.2261 1.0385 19 9.0584 1.0353 20 8.8906 1.0373 21 8.7229 1.0442 22 8.5551 1.0527 23 8.3874 1.0602 24 8.2196 1.0671 25 8.0519 1.0735 26 7.8841 1.0789 27 7.7164 1.0836 28 7.5487 1.0874 29 7.3809 1.0906 30 7.2132 1.0928 31 7.0454 1.0935 32 6.8777 1.0954 33 6.7099 1.0993 34 6.5422 1.1033 35 6.3744 1.1067 36 6.2067 1.1097 37 6.0389 1.1116 38 5.8712 1.1150 39 5.7034 1.1210
- Distance from bottom of active core (feet)
Note: Surveillance exclusion zone is 8% top, 8% bottom.
MILLSTONE - UNIT 3 TRM 8.1-23 LBDCR 14-MP3-010
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 3 (Continued)
Part Power (74% RTP, 150 MWD/iMTU) RAOC W(Z) Function Millstone Unit 3 - Cycle 17 Mesh No Height (ft)* W(z) 40 5.5357 1.1327 41 5.3679 1.1461 42 5.2002 1.1584 43 5.0324 1.1702 44 4.8647 1.1818 45 4.6969 1.1927 46 4.5292 1.2029 47 4.3614 1.2126 48 4.1937 1.2218 49 4.0259 1.2307 50 3.8582 1.2394 51 3.6905 1.2475 52 3.5227 1.2551 53 3.3550 1.2626 54 3.1872 1.2719 55 3.0195 1.2883 56 2.8517 1.3087 57 2.6840 1.3283 58 2.5162 1.3484 59 2.3485 1.3685 60 2.1807 1.3882 61 2.0130 1.4094 62 1.8452 1.4316 63 1.6775 1.4536 64 1.5097 1.4744 65 1.3420 1.4940 66 1.1742 1.5118 67 1.0065 1.5262 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 8.1-24 LBDCR 14-MP3-010
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 4 Burnup Penalty for Incore Millstone Unit 3 - Cycle 17 I Burnup (MWDIMTU) Penalty 1597 1.021 1919 1.025 2080 1.027 3045 1.037 3206 1.036 3366 1.036 4010 1.033 4171 1.030 4975 1.021
- Note: A Penalty of 1.02 shall be used outside of the burnup range shown in Table 4.
MILLSTONE - UNIT 3 TRMV 8.1-25 LBDCR 14-MP3-010
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-R1A, "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 8.1-26 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-m," July 2006 (Westinghouse Proprietary). (Methodology for Specification 3.2.2-Heat Flux Hot Channel Factor.)