ML053480157
| ML053480157 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/18/2005 |
| From: | Price J Dominion, Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 05-761 | |
| Download: ML053480157 (24) | |
Text
Dominion Nuclear Connecticut, Inc.
Millstone Power Station Rope Ferry Road
\\Vaterford, CT 06385 AtDominion-NOV 1 8 2005 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.
MPS Lic/MAE Docket No.
License No.05-761 RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT. INC.
MILLSTONE POWER STATION UNIT 3 CORE OPERATING LIMITS REPORT, CYCLE 11 In accordance with the Millstone Unit 3 Technical Specifications, Section 6.9.1.6.d, Dominion Nuclear Connecticut, Inc., hereby submits, as Enclosure 1, the Cycle 11 Core Operating Limits Report (COLR).
The Millstone Unit 3 COLR has been revised to incorporate changes for Cycle 11 operation, which include the Cycle 11 specific Relaxed Axial Offset Control w(z) function values.
The COLR has been incorporated into the Millstone Unit 3 Technical Requirements Manual.
If you have any questions or require additional information, please contact Mr. David W.
Dodson at (860) 447-1791, extension 2346.
Very truly yours, J
a~n Price jdVice President - Millstone 6bK~
Serial No.05-761 Core Operating Limits Report, Cycle 11 Page 2 of 2
Enclosures:
(1)
Commitments made in this letter: None.
cc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. G. F. Wunder Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08-B-1A Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station
Serial No.05-761 Docket No. 50-423 Core Operating Limits Report, Cycle 11 Millstone Power Station Unit 3 Dominion Nuclear Connecticut, Inc. (DNC)
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT MILLSTONE UNIT 3 CYCLE 11 I
CORE OPERATING LIMITS REPORT MILLSTONE - UNIT 3 TRM 8.1-1 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table of Contents Section Title Page 1.0 Core Operating Limits Report 8.1-4 2.0 Operating Limits 8.1-4 2.1 Limiting Safety System Settings (Specification 2.2.1) 8.1-4 2.2 Shutdown Margin-MODE I and 2 (Specification 3/4.1.1.1.1) 8.1-5 2.3 Shutdown Margin-MODE 3, 4 and 5 Loops Filled (Specification 3/4.1.1.1.2) 8.1-5 2.4 Shutdown Margin-MODE 5 Loops Not Filled (Specification 3/4.1.1.2) 8.1-6 2.5 Moderator Temperature Coefficient (Specification 3/4.1.1.3) 8.1-6 2.6 Shutdown Rod Insertion Limit (Specification 3/4.1.3.5) 8.1-6 2.7 Control Rod Insertion Limits (Specification 3/4.1.3.6) 8.1-6 2.8 Axial Flux Difference (Specification 3/4.2.1.1) 8.1-6 2.9 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3/4.2.2.1) 8.1-7 2.10 Heat Flux Hot Channel Factor Surveillance - FQ(Z)
(Specification 3/4.2.2.1.2) 8.1-7 2.11 Nuclear Enthalpy Rise Hot Channel Factor - FNAH (Specification 3/4.2.3.1) 8.1-8 2.12 DNB Parameters (Specification 3/4.2.5) 8.1-8 2.13 Shutdown Margin Monitor Alarm Setpoint (Specification 3/4.3.5) 8.1-9 2.14 Refueling Boron Concentration (Specification 3/4.9.1.1) 8.1-9 3.0 Analytical Methods 8.1-21 MILLSTONE - UNIT 3 TRM 8.1-2 LBDCR 05-MP3-008 September 22, 2005
Figure Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 Figure 6 Figure 7 TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT List of Figures Title Required Shutdown Margin for MODE 3 Required Shutdown Margin for MODE 4 Required Shutdown Margin for MODE 5 with RCS Loops Filled Required Shutdown Margin for MODE 5 with RCS Loops Not Filled Control Rod Bank Insertion Limits versus Thermal Power Axial Flux Difference Limits as a Function of Rated Thermal Power K(Z) - Normalized FQ(Z) as a Function of Core Height List of Tables Page 8.1-10 8.1-11 8.1-12 8.1-13 8.1-14 8.1-15 8.1-16 Table Title Table I RAOC W(Z) Function, Millstone Unit 3 - Cycle 11
-12/+9 AFD at 100% RTP Table 2 Base Load W(Z) Function, Millstone Unit 3 - Cycle 11 Page 8.1-17 l
8.1-19 MILLSTONE - UNIT 3 TRM 8.1-3 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Millstone Unit 3 Cycle 11 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) for Millstone Unit 3 Cycle II 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.
I I
2.2.1 3/4.1.1.1.1 3/4.1.1.1.2 3/4.1.1.2 3/4.1.1.3 3/4.1.3.5 3/4.1.3.6 3/4.2.1.1 3/4.2.2.1 3/4.2.3.1 3/4.2.5 3/4.3.5 3/4.9.1.1 Limiting Safety System Settings Shutdown Margin - MODE I and 2 Shutdown Margin - MODES 3, 4 and 5 Loops Filled Shutdown Margin - MODE 5 Loops Not Filled Moderator Temperature Coefficient Shutdown Rod Insertion Limit Control Rod Insertion Limits Axial Flux Difference Heat Flux Hot Channel Factor Nuclear Enthalpy Rise Hot Channel Factor DNB Parameters Shutdown Margin Monitor Alarm Setpoint Refueling Boron Concentration 2.0 Operating Limits The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.9.1.6.b.
2.1 Limiting Safety System Settings (Specification 2.2.1)
- 2. 1.1 Overtemperature AT 2.1.1.1 K1< 1.20 2.1.1.2 K2 2>0.02456/ -F 2.1.1.3 K3 2 0.001311 /psi 2.1.1.4 Tr 2 8 seconds MILLSTONE - UNIT 3 TRM 8.1-4 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.1.1.5 T2 < 3 seconds 2.1.1.6 T4 > 20 seconds 2.1.1.7 T5
- 4 seconds 2.1.1.8 T' is loop specific indicated Tavg at RATED THERMAL POWER,
< 587.1 OF 2.1.1.9 P' is nominal pressurizer pressure, 2 2250 psia 2.1.1.10 f1(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 -26% and +3%, fl(Al) 20, where qt and qb are percent RATED THERMAL POWER in the upper and lower halves of the core, respectively, and q, + qb is the total THERMAL POWER in percent RATED THERMAL POWER; (2) For each percent that the magnitude of qt - qb exceeds -26%, the AT Trip Setpoint shall be automatically reduced by 2 3.55% of its value at RATED THERMAL POWER.
(3) For each percent that the magnitude of qt - qb exceeds +3%, the AT Trip Setpoint shall be automatically reduced by 2 1.98% of its value at RATED THERMAL POWER.
2.1.2 Overpower AT 2.1.2.1 K4
- 1.09 2.1.2.2 K5 > 0.02/ OF for increasing Tavg and K 5 *0 for decreasing Tavg 2.1.2.3 KY6 Ž 0.00180/ OF when T> T"and K6 < Of 0 F when T* T" 2.1.2.4 t, Ž 8 seconds 2.1.2.5
¶2
- 3 seconds 2.1.2.6
¶a7 Ž 10 seconds 2.1.2.7 T" is loop specific indicated Tavg at RATED THERMAL POWER,
- 587.1 0F 2.2 Shutdown Margin-MODE 1 and 2 (Specification 3/4.1.1.1.1) 2.2.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.3% Ak/k.
2.3 Shutdown Margin-MODE 3, 4 and 5 Loops Filled (Specification 3/4.1.1.1.2) 2.3.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 1, 2 and 3.
MILLSTONE - UNIT 3 TRM 8.1-5 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.4 Shutdown Margin-MODE 5 Loops Not Filled (Specification 3/4.1.1.2) 2.4.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figure 4 or the limits shown in Figure 3 with the chemical and volume control system (CVCS) aligned to preclude reactor coolant system boron concentration reduction.
2.5 Moderator Temperature Coefficient (Specification 3/4.1.1.3) 2.5.1 The BOL/ARO/0% - 70% RTP MTC shall be less positive than + 0.5 x 10-4 Ak/k/OF.
Above 70% RTP, the MTC limit is a linear ramp to 0 Ak/k/0F at 100% RTP.
2.5.2 The EOL/ARO/RTP MTC shall be less negative than - 5.65 x 10-4 Ak/k/0F.
2.5.3 The 300 ppm/ARO/RTP MTC should be less negative than or equal to - 4.9 x 10-4 Ak/k/0F, where:
BOL stands for Beginning Of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Power EOL stands for End Of Cycle Life RTP stands for Rated Thermal Power.
2.6 Shutdownm Rod Insertion Limit (Specification 3/4.1.3.5) 2.6.1 The shutdown rods shall be at least 220 steps withdrawn (inclusive).
2.7 Control Rod Insertion Limits (Specification 3/4.1.3.6) 2.7.1 The control rod banks shall be limited in physical insertion as shown in Figure 5, and 2.7.2 Control bank A shall be at least 220 steps withdrawn.
2.8 Axial Flux Difference (Specification 3/4.2.1.1) 2.8.1 The Axial Flux Difference (AFD) limits are provided in Figure 6.
2.8.2 The AFD target band during base load operation is + 5%.
2.8.3 The minimum allowable (nuclear design) power level for base load operation (APLND) is 80% of Rated Thermal Power.
MILLSTONE - UNIT 3
.TRM 8.1-6 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.9 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3/4.2.2.1)
FRTP FQ(Z)
- Q xK(Z)
P for P > 0.5 FRTP FQ(Z) < 0Q x K(Z) for P < 0.5 where:
THERMAL POWER RATED THERMAL POWER 2.9.1 FRTPQ = 2.60.
2.9.2 K(Z) is provided in Figure 7.
2.10 Beat Flux Hot Channel Factor Surveillance - FQ(Z) (Specification 3/4.2.2.1.2)
FRT x K(Z)
FQ(Z) < P W(Z) for P > 0.5 FRTP x K(Z)
FQ(Z) 0.5 x W(Z) forP <0.5 where:
p =
THERMAL POWER RATED THERMAL POWER 2.10.1 FRTPQ = 2.60.
2.10.2 K(Z) is provided in Figure 7.
MILLSTONE - UNIT 3 TRM 8.1-7 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.10.3 W(Z) values for RAOC operation are provided in Table 1. Note that the W(Z) values at Axial Mesh I are at the top of the core. The Cycle 11 burnup dependent RAOC W(Z) values are valid over the range of burnup from 0 to 20,500 MWD/MTU.
2.10.4 W(Z) values for Base Load (BL) operation are provided in Table 2. Note that the W(Z) values at Axial Mesh I are at the top of the core. The Cycle 11 bumup dependent BL W(Z) values are valid over the range of burnup from 0 to 20,500 MWD/MTU.
- 2.10.5 A 2% factor shall be used for surveillance requirements 4.2.2.1.2 and 4.2.2.1.4.*
2.11 Nuclear Entlialpy Rise Hot Channel Factor - Fr4AH (Specification 3/4.2.3.1)
FNAHt
- FRTPAH X (I + PFAI1 x [I - P])
I I
where:
p =
THERMAL POWER RATED THERMAL POWER 2.11.1 FRTphH = 1.58 for Robust Fuel Assemblies (RFA) and (RFA-2)
FRTPAH = 1.51 for NGF Lead Test Assemblies 2.11.2 PFAH = 0.3 for P < 1.0.
2.12 DNB Parameters (Specification 3/4.2.5) 2.12.1 Indicated Reactor Coolant System Tavg shall be maintained < 591.1 OF.
2.12.2 Indicated Pressurizer Pressure shall be maintained > 2218 psia **.
Sections 2.10.3 through 2.10.5 are prepared by Dominion.
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.
MILLSTONE - UNIT 3 TRM 8.1-8 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.13 Shutdown Margin Monitor Alarm Setpoint (Specification 3/4.3.5)*
2.13.1 The Shutdown Margin Monitor (SMM) minimum count rate and Alarmn 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 Alarrn 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.
2.14 Refueling Boron Concentration (Specification 3/4.9.1.1) 2.14.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling cavity shall be maintained at a boron concentration of greater than or equal to 2600 ppm.
Section 2.13 was prepared by Dominion based on boron dilution analyses performed by Westinghouse.
This boron concentration bounds the condition of keff*< 0.95 (all rods in less the most reactive two rods) and subcriticality (keff < 1.0 with all rods out) during the Cycle 10/11 refueling out-age.
I MILLSTONE - UNIT 3 TRM 8.1-9 LBDCR 05-MP3-008 September 22, 2005
4.0, Z
35
_2 5003495l (2503495) z
~3.0 2.5 o
20 m
CO o
I-(0,1.300)
(700,1.300) c CD 0
I 0
0 cr0.0
.I CD0 500 1000 1500 2000 2500 0 CD RCS CRITICAL BORON CONCENTRATION (ppm) 00a 010co
CD65 (2075,5.866) 1=
zm r
(1324,5.268) 55.0,5/.8 o
z
--I
%I i
I /
5.0 4 4 POt.O j*
t
-I
~z tlD
((,1 350 1.000
.5i
.0 O
500 1000 1500 2000 2500 M @
~~RCS CRITI CAL BORON CON CEN-TRAT ION ( ppm)
CD00
-0 co
I-0 rn o'°'
1(2200,5.650)
I 0
5.5 -
z m
a.(1441,5.163)
I (25OOi5.650)
X
<^~~Y 4.5 -
j.M C
5.0 zz
=10
-4.0
/'___
-_;__0_
.35 -
o 2 0-0 1.5 1.0 c
(390,1.300) is 0.0_C CDWU) 0.0 ucu r
0 500 1000 1500 2000 2500 ROS CRITICAL BORON CONCENTRATION (ppm) 00 C) CD
I-
- 7nv 07, r_
(2200.6.150) 1T 0
6.563/40 c
° (1252,5.523)
(2500,6.150) 5.5 [
C,,
Q 0 2i
-I 04.01 IO S
I z'1 f1) 1.5 v
o M E o
so 1o00 (355,1.300)0 cn c C.)0 CD~
0500 1000 1500 2000 2500
-~
RCS CRITICAL BORON CONCENTRATION (ppm) 00 C
- mcro,
TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 5 Control Rod Bank Insertion Limits versis Thermal Powver 240 220 200 180 i
160 g 140 0n
> 120 0
o 100 8
80 so 0
40 40 20 0
0 1 0 20 30 40 50 60 70 80 90 100 RATED THERMAL POWER (%)
MILLSTONE - UNIT 3 TRM 8.1-14 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 6 Axial Flux Difference Limits as a Function of Rated Thermal Power 120 100 I-e as 0
Q-at it 80 60 40 20 0
-60
-50
-40
-30
-20
-10 0
10 20 30 40 50 60 Flux Difference, % Delta-l MILLSTONE - UNIT 3 TRM 8.1-15 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 7 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.2 1.1 1.0 0.9 L.
IL a.)
ax Ng To M
0.8 0.7 0.5 0.5 0.4 I=
=I
=--
II =
VP ElefatonI ID 0.0F F ID 0.0 Ft
__0 12__ Ft I
I I '
I iI-==-
0.3 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 8.1-16 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 1 RAOC W(Z) Function, Millstone Unit 3 - Cyclc 11
-12/+9 AFD at 100% RTP I
Mesh No.
1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 Axial* Height 12.0000 11.8333 11.6667 11.5000 11.3333 11.1667 11.0000 10.8333 10.6667 10.5000 10.3333 10.1667 10.0000 9.8333 9.6667 9.5000 9.3333 9.1667 9.0000 8.8333 8.6667 8.5000 8.3333 8.1667 8.0000 7.8333 7.6667 7.5000 7.3333 7.1667 7.0000 6.8333 6.6667 6.5000 6.3333 6.1667 6.0000 5.8333 5.6667 Burnup 150 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3420 1.3227 1.3040 1.2825 1.2571 1.2329 1.2172 1.2075 1.2008 1.1948 1.1876 1.1799 1.1737 1.1684 1.1644 1.1627 1.1607 1.1572 1.1530 1.1482 1.1424 1.1357 1.1299 1.1247 1.1186 1.1156 1.1144 1.1143 1.1138 1.1132 Burnup 4000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3595 1.3427 1.3291 1.3168 1.3025 1.2875 1.2742 1.2589 1.2418 1.2266 1.2156 1.2082 1.2020 1.1950 1.1882 1.1842 1.1799 1.1739 1.1670 1.1592 1.1505 1.1412 1.1304 1.1200 1.1139 1.1118 1.1115 1.1102 1.1083 1.1066 Burnup 10000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3528 1.3319 1.3120 1.2972 1.2831 1.2669 1.2499 1.2383 1.2340 1.2341 1.2328 1.2293 1.2263 1.2213 1.2151 1.2108 1.2057 1.2001 1.1967 1.1927 1.1866 1.1793 1.1707 1.1611 1.1504 1.1384 1.1261 1.1165 1.1133 1.1130 Burnup 17000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3776 1.3650 1.3491 1.3302 1.3105 1.2902 1.2688 1.2490 1.2350 1.2289 1.2205 1.2123 1.2123 1.2136 1.2145 1.2189 1.2226 1.2238 1.2235 1.2219 1.2189 1.2143 1.2085 1.2013 1.1927 1.1836 1.1742 1.1643 1.1552 1.1495 I
- Distance from bottom of active core (feet)
MILLSTONE - UNIT 3 TRM 8.1-17 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 1 (Continued)
RAOC W(Z) Function, Millstone Unit 3 - Cycle 11
-12/+9 AFD at 100% RTP I
Mesh No.
40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 Axial* Height 5.5000 5.3333 5.1667 5.0000 4.8333 4.6667 4.5000 4.3333 4.1667 4.0000 3.8333 3.6667 3.5000 3.3333 3.1667 3.0000 2.8333 2.6667 2.5000 2.3333 2.1667 2.0000 1.8333 1.6667 1.5000 1.3333 1.1667 1.0000 0.8333 0.6667 0.5000 0.3333 0.1667 0.0000 Burnup 150 MWD/MTU 1.1160 1.1212 1.1272 1.1327 1.1377 1.1424 1.1468 1.1507 1.1543 1.1576 1.1606 1.1632 1.1654 1.1680 1.1730 1.1833 1.1965 1.2099 1.2234 1.2366 1.2496 1.2628 1.2769 1.2916 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Burnup 4000 MWD/MTU 1.1088 1.1117 1.1135 1.1150 1.1159 1.1167 1.1196 1.1236 1.1277 1.1314 1.1348 1.1379 1.1406 1.1432 1.1455 1.1475 1.1552 1.1707 1.1871 1.2033 1.2197 1.2358 1.2513 1.2661 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Burnup 10000 MWD/MTU 1.1134 1.1148 1.1176 1.1199 1.1218 1.1233 1.1245 1.1254 1.1260 1.1263 1.1266 1.1276 1.1312 1.1354 1.1389 1.1425 1.1447 1.1475 1.1577 1.1711 1.1834 1.1954 1.2072 1.2182 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Burnup 17000 MWD/MTU 1.1500 1.1515 1.1510 1.1498 1.1485 1.1472 1.1452 1.1428 1.1397 1.1359 1.1326 1.1309 1.1310 1.1307 1.1302 1.1358 1.1466 1.1591 1.1715 1.1837 1.1958 1.2076 1.2190 1.2298 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 I
- Distance from bottom of active core (feet)
MILLSTONE - UNIT 3 TRM 8.1-18 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Mesh No.
l 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 Axial* Height 12.0000 11.8333 11.6667 11.5000 11.3333 11.1667 11.0000 10.8333 10.6667 10.5000 10.3333 10.1667 10.0000 9.8333 9.6667 9.5000 9.3333 9.1667 9.0000 8.8333 8.6667 8.5000 8.3333 8.1667 8.0000 7.8333 7.6667 7.5000 7.3333 7.1667 7.0000 6.8333 6.6667 6.5000 6.3333 6.1667 6.0000 5.8333 5.6667 Table 2 Base Load W(Z) Function Millstone Unit 3 - Cycle 11.
Burnup 150 Bumup 1000 Burnup 4000 MWD/MTU MWD/MTU MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2260 1.2446 1.2693 1.2188 1.2369 1.2603 1.2129 1.2297 1.2498 1.2053 1.2212 1.2393 1.1965 1.2112 1.2270 1.1873 1.2006 1.2143 1.1771 1.1899 1.2033 1.1632 1.1760 1.1902 1.1475 1.1603 1.1760 1.1351 1.1477 1.1652 1.1292 1.1411 1.1581 1.1282 1.1391 1.1538 1.1276 1.1377 1.1509 1.1261 1.1355 1.1472 1.1248 1.1335 1.1439 1.1255 1.1337 1.1432 1.1260 1.1337 1.1423 1.1263 1.1331 1.1398 1.1280 1.1334 1.1365 1.1292 1.1330 1.1325 1.1288 1.1313 1.1275 1.1275 1.1286 1.1214 1.1254 1.1258 1.1167 1.1223 1.1231 1.1142 1.1180 1.1199 1.1128 1.1151 1.1180 1.1121 1.1144 1.1176 1.1115 1.1142 1.1173 1.1101 1.1137 1.1163 1.1081 1.1132 1.1155 1.1066 Burnup 10000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2415 1.2315 1.2210 1.2110 1.2025 1.1961 1.1911 1.1832 1.1774 1.1794 1.1801 1.1775 1.1773 1.1762 1.1748 1.1762 1.1771 1.1760 1.1738 1.1704 1.1659 1.1603 1.1537 1.1462 1.1376 1.1291 1.1214 1.1151 1.1129 1.1125 Burnup 17000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2163 1.2174 1.2165 1.2118 1.2048 1.1973 1.1911 1.1905 1.1941 1.1969 1.1971 1.1966 1.1980 1.1980 1.1972 1.1990 1.1999 1.2004 1.2033 1.2055 1.2053 1.2036 1.2004 1.1958 1.1898 1.1827 1.1742 1.1644 1.1552 1.1490
- Distance from bottom of active core (feet)
MILLSTONE - UNIT 3 TRM 8.1-19 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Mesh No.
40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 Axial* Height 5.5000 5.3333 5.1667 5.0000 4.8333 4.6667 4.5000 4.3333 4.1667 4.0000 3.8333 3.6667 3.5000 3.3333 3.1667 3.0000 2.8333 2.6667 2.5000 2.3333 2.1667 2.0000 1.8333 1.6667 1.5000 1.3333 1.1667 1.0000 0.8333 0.6667 0.5000 0.3333 0.1667 0.0000 Table 2 (Continued)
Base Load W(Z) Function Millstone Unit 3 - Cycle 11 Burnup 150 Bumnup 1000 Bumup 4000 MWD/MTU MWD/MTU MWD/MTU 1.1134 1.1159 1.1071 1.1146 1.1170 1.1078 1.1160 1.1180 1.1077 1.1169 1.1186 1.1072 1.1174 1.1188 1.1063 1.1175 1.1187 1.1052 1.1173 1.1182 1.1037 1.1168 1.1174 1.1019 1.1160 1.1164 1.1002 1.1157 1.1161 1.0998 1.1157 1.1164 1.1001 1.1160 1.1174 1.1024 1.1185 1.1198 1.1043 1.1203 1.1216 1.1057 1.1224 1.1235 1.1070 1.1314 1.1304 1.1089 1.1449 1.1412 1.1133 1.1595 1.1539 1.1216 1.1743 1.1680 1.1336 1.1892 1.1829 1.1479 1.2039 1.1981 1.1631 1.2185 1.2130 1.1781 1.2325 1.2274 1.1926 1.2458 1.2410 1.2064 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Bumnup 10000 MWD/MTU 1.1116 1.1099 1.1079 1.1055 1.1026 1.0994 1.0958 1.0925 1.0897 1.0867 1.0839 1.0822 1.0827 1.0834 1.0839
.1.0872 1.0947 1.1054 1.1162 1.1268 1.1376 1.1483 1.1585 1.1682 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Bumup 17000 MWDIMTU 1.1471 1.1456 1.1425 1.1386 1.1348 1.1310 1.1266 1.1216 1.1161 1.1101 1.1045 1.1003 1.0978 1.0949 1.0922 1.0937 1.1003 1.1105 1.1207 1.1305 1.1405 1.1503 1.1599 1.1689 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
- Distance from bottom of active core (feet)
MILLSTONE - UNIT 3 TRM 8.1-20 LBDCR 05-MP3-008 September 22, 2005
TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 3.0 Analytical Methods The analytical methods used to determine the core operating lifiits 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 (E Proprietary).
3.2 WCAP-10216-P-A-RIA, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION," Rev. 1, February 1994 (E Proprietary).
3.3 WCAP-956i-P-A, ADD. 3, Rev. 1, "BART A-l: A COMPUTER CODE FOR THE BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS-SPECIAL REPORT: THIMBLE MODELING W ECCS EVALUATION MODEL," July 1986 (W Proprietary).
3.4 WCAP-10266-P-A, Addendum 1, Rev. 2-P-A, "THE 1981 VERSION OF THE WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE," March 1987 (E Proprietary).
3.5 WCAP-1 1946, "Safety Evaluation Supporting a More Negative EOL Moderator Temperature Coefficient Technical Specification for the Millstone Nuclear Power Station Unit 3," September 1988 (W Proprietary).
3.6 WCAP-10054-P-A, "WESTINGHOUSE SMALL BREAK ECCS EVALUATION MODEL 17 USING THE NOTRUMP CODE," August 1985 (E Proprietary).
3.7 WCAP-1 0079-P-A, "NOTRUMP - A NODAL TRANSIENT SMALL BREAK AND GENERAL NETWORK CODE," August 1985 (W Proprietary).
3.8 WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Report," April 1995
'X Proprietary).
3.9 WCAP-8301, "LOCTA-IV Program: Loss-of-Coolant Transient Analysis," June 1974 (a Proprietary).
3.10 WCAP-10054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model," July 1997 (W Proprietary).
3.11 WCAP-8745-P-A, "DESIGN BASES FOR THE THERMAL OVERPOWER AT AND THERMAL OVERTEMPERATURE AT TRIP FUNCTIONS," September 1986 (W Proprietary).
MILLSTONE - UNIT 3 TRM 8.1-21 LBDCR 05-MP3-008 September 22, 2005