ML18145A196
| ML18145A196 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 05/24/2018 |
| From: | Simmons P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18145A196 (27) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 May 24, 2018 10 CFR 50.4 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390
Subject:
REVISION O OF THE CYCLE 14 and 15 CORE OPERATING LIMITS REPORT (COLR)
Pursuant to Watts Bar Nuclear Plant Technical Specifications Section 5.9.5.d, Tennessee Valley Authority (TVA) has enclosed Revision O of the Unit 1 Cycle 14 and Revision O of the Unit 1 Cycle 15 COLR. The analytical methods used to determine the core operating limits were previously reviewed and approved by the NRC. A review determined that these documents have not been previously submitted as required. This issue has been entered into the corrective action program .
There are no regulatory commitments contained in this letter or the enclosure. Should you have questions regarding this submittal, please contact Kim Hulvey at (423) 365-7720.
~ly, Paul Simmons Site Vice President Watts Bar Nuclear Plant
Enclosures:
Watts Bar Nuclear Plant, Unit 1, Cycle 14 Core Operating Limits Report Revision 0, September 2015 Watts Bar Nuclear Plant, Unit 1, Cycle 15 Core Operating Limits Report Revision 0 March 2017
U.S. Nuclear Regulatory Commission Page 2 May 24, 2018 cc (Enclosure):
NRC Regional Administrator- Region II NRR Project Manager - Watts Bar Nuclear Plant NRC Senior Resident Inspector - Watts Bar Nuclear Plant
ENCL0SURE1 Watts Bar Nuclear Plant, Unit 1, Cycle 14 Core Operating Limits Report Revision 0 September 2015
QA Record L36 150908 802 VV!ffTS BAR ~~UCLEAR PLANT, UNIT 1, CYCLE 14 CORE OPERAT ING LIMITS REPORT Revision 0 September 2015 Prepared by:
Brian Ft Elder, PWR Fuel Engineering Verified by:
Mark D. Porter, PWR Fuel Engineering Date
. Cunn ingham , Manager. PWR Fuel Engineering Kimberly D. 'issorn , Manager, Reactor Engineering App roved by:
Date Date of PORC PORC Affected Revis ion A 0
Unit '1 Cycle 14 Watts Bar Page 1 of 10 Revision 0
1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Watts Bar Unit 1 Cycle 14 has been prepared in accordance with the requirements of the Technical Specifications 5.9.5.
The Technical Specifications affected by this report are listed below:
3 .1.4 Moderator Temperature Coefficient (MTC) 3.1.6 Shutdown Bank Insertion Limits 3.1.7 Control Bank Inse1iion Limits 3.2.1 Heat Flux Hot Channel Factor (F 0 (Z))
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F 111/ )
3.2.3 Axial Flux Difference (AFD) 3.5. l Accumulators 3.5.4 Refueling Water Storage Tank (RWST)
- 3. 9 . 1 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 the Technical Specifications Section 5.9.5.
The following abbreviations are used in this section:
BOL Beginning of Cycle Life ARO All Rods Out HZP Hot Zero Thermal Power EOL End of Cycle Life R TP Rated Thermal Power Unit 1 Cycle 14 WATTS BAR Page 2 of 10 Revision 0
2.1 MODERATOR TEMPERATURE COEFFICIENT- MTC (LCO 3.1.4) 2.1.1 The MIC limits are:
The ARO/HZP - MIC shall be less positive than or equal to OAk/k/°F (upper hmit).
With the measured BOLiARO/HZP - MIC more positive than -1.09 x 10-5 Ak/k/°F (as-measured MTC limit), establish control rod withdrmval limits to ensure the MIC remains less positive than or equal to O Ak/k/°F (upper limit) for all times in core life.
The EOL/ARO/RTP - MIC shall be less negative than or equal to
-4.5 x 10-4 Ak/kl°F (lower limjt).
2.1.2 The 300 ppm surveillance limit is:
The measured 300 ppm/ARO/RTP-MTC should be Jess negative than or equal to
-3.75 X 10-4 Ak/k/°F.
2.1.3 The 60 ppm surveillance limit is:
The measured 60 ppm / ARO/RTP-MTC should be less negative than or equal to
-4.28 X 10-4 Ak/k/°F.
2.2 SHUTDOWN BANK INSERTION LIMITS (LCO 3.1.6) 2.2.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps withdrawn.
2.3 CONTROL BANK INSERTION LIMITS (LCO 3.1.7) 2.3.1 The control banks are fully withdrawn or shall be limjted in physical insertion as shown in Figure 1.
2.3.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 225 steps.
2.3.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C, and Bank D. The control banks shall be sequenced in reverse order upon insertion.
Unit 1 Cycle 14 WATTS BAR Page 3 of 10 Revision 0
2.3.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap as a function of park position.
Park Position (steps) Bank Overlap (steps) Bank Difference (steps) 225 109 116 226 110 116 227 111 116 228 I 12 116 229 113 116 230 114 116 231 115 116 2.4 HEAT FLUX HOT CHANNEL FACTOR- F 0 (Z) (LCO 3.2.1)
F 0 (Z) s [CFQ / P]
- K(Z) for P > 0.5 F 0 (Z) s [CFQ / 0.5]
- K(Z) for P s 0.5 Where P = Thermal Power / Rated Thermal Power 2.4.1 CFQ = 2.50 2.4.2 K(Z) is provided in Figure 2.
2.4.3 F 0 w(Z) = Foc(Z)
- W(Z)/P for P > 0.5 F 0 w(Z) = F 0 c(Z)
- W(Z)/0.5 for P:::; 0.5 where: W(Z) values are provided in Table A. I. The table provides sufficient information to dete1mine W(Z) versus core height for all cycle burnups.
2.4.4 Part power W(Z) values are only required to be used when the pait power surveillance is performed using the moveable incore detector system.
2.4.5 F Ow (Z) Penalty Factor The F 0 w(Z) penalty factor is provided in Table A.2.
Unit 1 Cycle14 WATTS BAR Page 4 of 10 Revision 0
2.5 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F t..1-1 N (LCO 3.2.2)
FA,/ ~ Fl!HRTP * ( J + PF* ( 1-P))
where P = Thermal Power / Rated Thermal Power RTP * ,
FAH = 1.65 for RFA-2 fuel , and PF = 0.3 2.6 AXIAL FLUX DIFFERENCE - AFD (LCO 3.2.3) 2.6.1 The AFD limits for Cycle 14 are provided in Figure 3.
2.7 REFUELING BORON CONCENTRATION (LCO 3.9.1)
- 2. 7 .1 The refueling boron concentration shall be ~ 2000 ppm.
2.8 ACCUMULATORS (LCO 3.5.1) 2.8.1 There are 704 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 14.
2.9 REFUELING WATER STORAGE TANK-RWST (LCO 3.5.4) 2.9. 1 There are 704 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 14.
Unit 1 Cycle 14 WATTS BAR Page 5 of 10 Revision 0
200 z
s
<(
175 0::
C
- c I-
§ 150 V,
0..
w I-
~
z 0 125 j::
vi 0
0..
0..
w 100 I-V,
~
z<(
al C
0 75 0::
so 0.0 0.2 0.4 0.6 0.8 1.0 FRACTION OF RATED THERMAL POWER Figure 1 Control Bank Insertion Limits Versus Thermal Power Four Loop Operation
- Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of;?: 225 and $; 231 steps withdrawn.
Unit l Cycle 14 WATTS BAR Page 6 of 10 Revision 0
1.2 1.1 1.0 0.9
~
0.8 s....
(l) 3:
0 0.7 a..
+:
0 u.. I Core
'"C 0.6 Height 0.000 K(Z) 1.000 (1)
I 6.000 1.000 -
.!::::! 12.000 0.9256 co E 0.5 I-0 z
0.4 0.3 0.2 0.1 0
0 2 4 6 8 10 12 Core Height (feet)
Figure 2 K(Z) - Normalized F 0 (Z) as a Function of Core Height Unit l Cycle 14 WATTS BAR Page 7 of 10 Revision 0
120 110 I
I I (-12, 100) I (7, 100) I 100
... I \
90
/, Acceptable I V- I \
I '
... Operation I .. .....
80 1 Unacceptable Operation .
I Ope1al1UII I
I
~
I 0
0.. 70 J1 \ ....................
co E
I .... .
\
a,
.c I- 60 I \
/ '
"O a, ... ........ ....... ... ..... ,.. *. .. , ********** ... ********* ...
~
~
0 0
50 Ic '
- 1) I Ic ,
\
- 1) I 40 30 20 ........ ...... ..................... ,...
10 ..... ....... .... . ... '
I 0
-50 -40 -30 -20 -10 0 10 20 30 40 50 Flux Difference (L\I) %
Figure 3 Axial Flux Difference Acceptable Operation Limits as a function of Rated Thermal Power (RAOC)
Unit l Cycle 14 WATTS BAR Page 8 of 10 Revision 0
Table A.l Max W( z) Max W(z) Max W(z) Max W(z) Max W(z) Max W(z) at 150 at 150 at 150 at 2000 at 10000 a t 16000 MWD/MTU MWD!MTU MW D/MTU MWD/MTU MWD/MT U MWD/MTU Height (30~{1 (75% ( 100% (100% (100'}'" (100%
(ft) Power) Powal Power) Pow..-:r) Power) Power) 12.0749 1.0000 1.0000 1.0000 1.0000 1.0000 J.0000 11.8737 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.6724 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 ll.4712 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.2699 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 J1.0687 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10.8674 1.3674 1.3507 1.2024 .1.2297 1.1988 1.1769 10.6662 1.3473 1.3273 1.1987 1.2270 1.1871 1.1746 10.4649 1.3287 1.2971 1.1927 J.2249 1.1752 1.1699 10.2637 1.3057 1.2622 1.1842 1.2205 1.1695 J.1637 10.0624 1.2884 1.2325 l.l 826 J.2141 1.1652 1.1591 9.8612 1.2718 1.2035 1.1832 1.2058 1.1629 l.1567 9.6599 1.2491 1.1804 1.1815 1.1976 1.1619 1.1563 9.4587 1.2216 l.l 604 1.1779 l.l 960 1.1586 1.1581 9.2574 1.1901 1.1420 1.1723 1.1986 1.1557 1.1599 9.0562 1.1628 1.1302 1.1712 1.2009 1.1536 1.1668 8.8549 1.1371 J.1230 1.J 727 1.1995 1.1545 1.1778 8.6537 1.1190 1.1190 l.l 759 J.1984 1.1612 J.1914 8.4524 I.I 006 1.1169 1.1791 1.2027 1.1738 1.2102 8.2512 1.0890 1.1215 1.1873 1.2044 1.1855 1.2264 8.0499 1.0824 1.1280 1.1974 1.2029 1.1948 1.2395 7.8487 1.0758 1.1334 1.2057 1.2009 1.2021 1.2503 7.6474 1.0702 1.1376 1.2113 1.2006 1.2071 1.2583 7.4462 1.0658 1.1408 1.2145 1.2023 1.2097 1.2634 7.2449 1.0618 1.1428 1.2154 1.2018 1.2103 1.2657 7.0437 1.0570 J.1424 1.2141 J.1990 1.2086 1.2654 6.8424 1.0524 1.1405 1.2110 1.1948 1.2053 l.2624 6.6412 1.0487 1.1384 1.2068 J.1893 1.2005 1.2569 6.4399 1.0451 1.1348 1.2005 1.1820 1.1940 1.2490 6.2387 1.0413 1.1300 1.1924 1.1730 1.1858 1.2387 6.0375 1.0395 1.1271 1.1862 1.1660 1.1758 1.2264 5.8362 1.0386 l.l 246 1.1803 1.J 591 l.1648 1.21.17 5.6350 1.0380 1.1213 1.1731 1.1516 l.1578 I.I 958 5.4337 1.0408 1.1205 1.1682 1.1485 1.1582 1.1818 5.2325 1.0455 1.1210 1.1644 1.1473 1.1596 1.1731 5.0312 1.0512 1.1225 1.J 622 J.1457 1.1599 1.1702 4.8300 1.0577 1.1243 I.J604 1.1441 1.1593 1.1698 4.6287 1.0646 1.1260 1.1581 1.1430 1.1578 1.1686 4.4275 1.0736 l.l 288 J.1568 1.1410 1.1554 1.1665 4.2262 J.0825 1.131 J 1.1548 1.1386 1.1525 1.1637 4.0250 1.0908 1.1328 1.1521 1.1357 1.1486 1.1602 3.8237 1.0991 1.1345 1.1492 1.1323 1.1462 1.1560 3.6225 1.1071 1.1352 1.1455 J.1311 1.1465 1.1518 3.4212 I.I 151 1.1356 1.1416 J.1357 I.J 522 J.1492 3.2200 1.1284 1.1409 1.1426 1.1386 I.J 576 1.1500 3.0187 1.1458 1.1496 1.1470 1.1495 1.1617 1.1569 2.8175 1.1730 1.1671 1.1602 1.1691 1.1679 1.1714 2.6162 1.2105 1.1948 1.1834 1.1910 1.1803 1.1905 2.4150 1.2477 1.2218 1.2058 1.2128 1.1990 1.2086 2.2137 1.2850 1.2487 1.2278 1.2343 1.2174 1.2262 2.0125 1.3225 1.2750 1.2494 1.2551 1.2347 1.2430 1.8112 1.3599 1.3009 1.2700 1.2758 1.2514 1.2590 1.6100 1.3971 1.3267 1.2893 1.2964 1.2668 1.2738 1.4087 1.4340 1.3519 1.3064 1.3145 1.2800 .1.2865 1.2075 1.4720 J.3743 1.3197 1.3292 1.2897 1.2956 1.0062 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.8050 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.6037 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.4025 1.0000 J.0000 1.0000 1.0000 1.0000 1.0000 0.2012 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Unit 1 Cycle 14 WATTS BAR Page 9 of 10 Revision 0
Table A.2 F Q w (Z) Penalty Factor Core FQ (Z)
~llt1:)llp r'-:1:l~!!Y (MWD/MTU) Factor 1.0200 Note:
- l. The Penalty Factor, which is applied to FQw(Z) for compliance with Surveillance Requirement 3.2.1.2, is the maximum factor by which F Ow(Z) is expected to increase per 31 Effective Full Power Days (EFPD) starting from the burnup at which the FQ w(Z) was determined.
Unit 1 Cycle 14 WATTS BAR Page 10 of 10 Revision 0
EDMS PACKAGE Document Type: Technical Requirements Manual Date: April 7, 2017 ACCNO: T35 170407 227 Document ID: Cycle 15 COLR
Title:
Cycle 15 Core Operating Limits Report (COLR)
Revision: TRM Revision 62
References:
Cycle 15 COLR TRM and TRM Bases
PFE-3484, Rev. 0 L36 170403 800 April 3, 2017 K.D. Hulvey, WBN Manager, Site Licensing WATTS BAR UNIT 1 CYCLE 15 CORE OPERA TING LIMITS REPORT (COLR),
REVISION 0 The approved Watts Bar Unit 1 Cycle 15 Core Operating Limits Report (COLR) is attached (EDMS # L36 170317 800). Operations requires issuance of the COLR prior to core reload (Technical Specification 5.9.5.a). Unit I Cycle 15 core reload is forecast to commence 04/08/2017 at 05:00. Please distribute the COLR to Operations no later than 04/06/2017 to support plant operation. Please, also, transmit the COLR to the NRC in accordance with Technical Specification 5.9.5.d.
If you have any questions, please call me at 423-751-2714.
- Regards, Digitally signed by Ritchie, John A DN: dc=gov, dc=tva, dc:=main, ou:Main, Ritchie, John A =~:;::=~*:cn=Ritch~.John1-Reason: I am th* authot of this document Date: 2017.04.03 15:u:,s -04'00' John A. Ritchie PWR Fuel Engineering Attachment cc:
D.C. Baker, WBN Site Licensing L.S. Barnes, WBN Reactor Engineering J.T. Elkins; PWR Fuel Engineering K.R. Kenner, PWR Fuel Engineering C.A. Setter; Manager, PWR Fuel Engineering J.E. Strange, Senior Specialist, PWR Fuel Engineering Page 1 of 1
T35 170407 227 April 7, 2017 Barbara Perry, EQB, Watts Bar Nuclear Plant WATTS BAR NUCLEAR PLANT (WBN)-TRANSMITTAL OF APPROVED CORE OPERATING LIMITS REPORT (COLR), CYCLE 15, REVISION 0 Attached is the approved Revision O of the Cycle 15 COLR. The COLR is located in the Technical Requirements Manual as a miscellaneous document. Please perform the required distribution and filing in accordance with the attached instruction sheet. Please direct any questions regarding the filing of this document to me at 423-365-2004.
P4~.
Gordon Arent WBN Site Licensing Director ADM 1L-WBN Attachment cc (Attachment):
Licensing Engineers Licensing Files W. F. Smith, WTC 1G-WBN W. E. Sprinkle, MOB 2M-WBN EDMS, WTA-K
ATTACHMENT WATTS BAR NUCLEAR PLANT UNIT 1 TECHNICAL REQUIRMENTS MANUAL INSTRUCTION SHEET FOR PAGE REPLACEMENT CYCLE 15 CORE OPERATING LIMITS REPORT (COLR)
Remove {Front/Back) Insert {Front/Back)
COLR Cycle 14, Rev. 0, Pages 1 - 10 COLR Cycle 15, Rev. 0, Pages 1 - 10
QA Record L36 170317 800 WATTS BAR NUCLEAR PLANT, UNIT 1, CYCLE 15 CORE OPERA TING LIMITS REPORT Revision 0 March 2017 I ?, [ i 'l. { to r=,
Date I 3 £t2-L?Q1l-Date Verified by:
~~
K e l l ~WR Fuel Engineering I 03/-z..:2... /2.017 Date Reviewed by:
/)~'1rl~ I 3/z2J_17 David M. Brown, General Manager, Reactor Engineering & Fuels Date for Manager, PWR Fuel Engineering
~~ulvey,D.Manager, Kimberly D.
Urdi, i\eactor Engineering I o3 j z-z,lz.o 11-Date
~~~---'=--;;7~-------~h Date of PORC PORC Meeting Affected Revision Aooroval Number Paoes Reason for Revision 0 All Initial issue Unit 1 Cycle 15 Watts Bar Page 1 of 10 Revision 0
1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Watts Bar Unit 1 Cycle 15 has been prepared in accordance with the requirements of the Technical Specifications 5.9.5.
The Technical Specifications affected by this report are listed below:
3.1.4 Moderator Temperature Coefficient (MTC) 3.1.6 Shutdown Bank Insertion Limits 3.1. 7 Control Bank Insertion Limits 3.2.l Heat Flux Hot Channel Factor (Fo(Z))
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FaHN) 3.2.3 Axial Flux Difference (AFD) 3.9.l 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 the Technical Specifications Section 5.9.5.
The following abbreviations are used in this section:
BOL Beginning of Cycle Life ARO All Rods Out HZP Hot Zero Thermal Power EOL End of Cycle Life RTP Rated Thermal Power Unit 1 Cycle 15 WATTS BAR Page 2 of 10 Revision 0
2.1 MODERATOR TEMPERATURE COEFFICIENT - MTC (LCO 3.1.4) 2.1.1 The MTC limits are:
The ARO/HZP - MTC shall be less positive than or equal to OAk/k/°F (upper limit).
With the measured BOL/ARO/HZP - MTC more positive than -1.30 x 10-~ Ak/k/°F (as-measured MTC limit), establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to OAk/k/°F (upper limit) for all times in core life.
The EOL/ARO/RTP - MTC shall be less negative than or equal to
-4.5 x 10 4 Ak/k/°F (lower limit).
2.1.2 The 300 ppm surveillance limit is:
The measured 300 ppm /ARO/RTP-MTC should be less negative than or equal to
-3.75 X 10* 4 Ak/k/°F.
2.1.3 The 60 ppm surveillance limit is:
The measured 60 ppm /ARO/RTP-MTC should be less negative than or equal to
-4.28 X 10 4 Ak/k/°F.
2.2 SHUTDOWN BANK INSERTION LIMITS (LCO 3.1.6) 2.2.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps withdrawn.
2.3 CONTROL BANK INSERTION LIMITS (LCO 3.1.7) 2.3.1 The control banks are fully withdrawn or shall be limited in physical insertion as shown in Figure I.
2.3.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 225 steps.
2.3.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C, and Bank D. The control banks shall be sequenced in reverse order upon insertion.
Unit l Cycle 15 WATTS BAR Page 3 of 10 Revision 0
2.3.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap as a function of park position.
Park Position (steps) Bank Overlap (steps) Bank Difference (steps) 225 109 116 226 110 116 227 111 116 228 112 116 229 113 116 230 114 116 231 115 116 2.4 HEAT FLUX HOT CHANNEL FACTOR-FQ(Z) (LC03.2.1)
FQ(Z) s [CFQ / P]
- K(Z) for P > 0.5 FQ(Z) s [CFQ/ 0.5]
- K(Z) for P s 0.5 Where P = Thermal Power I Rated Thermal Power 2.4.1 CFQ = 2.50 2.4.2 K(Z) is provided in Figure 2.
2.4.3 Fo w(Z) = Foc(Z)
- W(Z)/P for P > 0.5 F0 w(Z) = F0 °(Z)
- W(Z)/0.5 for P ~ 0.5 where: W(Z) values are provided in Table A.I. The table provides sufficient information to determine W(Z) versus core height for all cycle bumups.
2.4.4 Part power W(Z) values are only required to be used when the part power surveillance is performed using the moveable incore detector system.
2.4.5 FQ w(Z) Penalty Factor The F0 w(Z) penalty factor is provided in Table A.2.
Unit 1 Cycle 15 WATTS BAR Page 4 of 10 Revision 0
2.5 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - FAHN (LCO 3.2.2)
FMl]I; ~ F,1/TP * (I+ PF* ( 1-P))
where P = Thermal Power/ Rated Thermal Power F11 /TP = 1.65 for RFA-2 fuel, and PF = 0.3 2.6 AXIAL FLUX DIFFERENCE - AFD (LCO 3.2.3) 2.6.1 The AFD limits for Cycle 15 are provided in Figure 3.
2.7 REFUELING BORON CONCENTRATION (LCO 3.9.1) 2.7.1 The refueling boron concentration shall be.!: 2000 ppm.
3.0 NUMBER OF TPBARS IN REACTOR CORE (TS 4.2.1) 3.0.1 There are 1104 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 15.
Unit I Cycle 15 WATTS BAR Page 5 of 10 Revision 0
250
-~
j BANK A (ALL POWERS, 225) 225 (0.197, 225) (0. 703, 225) 200 (1.0, 177) 2 175 I
Q
- c (0.0, 180) c 3 150 f
~
-~ 125 EIll ia.
~ 100 Ill
- I.::
z
- IQ 75 i
(0.0, 64) so 25 ---+--
(0.227, O) 0 .,._ _ _ _ _..,.. ._ _ _...._ _ _ _..._ _ _ _ _ ~ ....- - - , - .
0.0 0.2 0.4 0.6 0.8 1.0 FRACTION OF RATED THERMAL POWER Figure 1 Control Bank Insertion Limits Versus Thermal Power Four Loop Operation Note: Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of :2: 225 and S 231 steps withdrawn.
Unit 1 Cycle 15 WATTS BAR Page 6 of 10 Revision 0
1.2 1.1 1.0 0.9 --
0.8 L...
Q) 0 0.7 a..
. 0 u.
"C 0.6 Core Height 0.000 K(ZI 1.000 -
Q)
-~ro E 0.5 6.000 12.000 1.000 0.9256 -
L...
0 z
0.4 0.3 0.2 0.1 0
0 2 4 6 8 10 12 Core Height (feet)
Figure 2 K(Z)- Normalized FQ(Z) as a Function of Core Height Unit 1 Cycle 15 WATTS BAR Page 7 of 10 Revision 0
120 f-- -
I
-+
110 1- L -
t- 1-- ;
-+
!I ---* ---
~ (-12, 100) t ~ (7, 100) ~ I *--**
_I 100 ! --***
I f-- -r---
i--
90 ---, Acceptable Operation 80 Unacceptable Unacceptable
... Operation Operation
~ --1 I Q. 70 -- --!
cu L_ I I
E -
-+ ---1 r---
Cl>
.=.
I- 60 t-- T i i - - --- --i---- -
r- --i-
~ -l 0
50 r- (-28, 50) 0~
i
[ __
+-
40 >- i -
T
~--
I i -
r- - 1-
---r ;-- ,-
I 30
-1 r-20 I_
1-
_J 10 --f ---+ --
i
_J
~I --+ --i '*
I 0
-50 -40 -30 -20 -10 0 10 20 30 40 50 Flux Difference (~I)%
Figure 3 Axial Flux Difference Acceptable Operation Limits as a function of Rated Thermal Power (RAOC)
Unit I Cycle 15 WATTS BAR Page 8 of 10 Revision 0
Table A.I RAOC W(Z) Surveillance Factors MuW(z) MaxW(z) MaxW(z) MaxW(z) MaxW(z) MuW(z) MaxW(z) MaxW(z) MaxW(z)
- 150 at 150 at 150 at 2000 at4000 118000 at 12000 at 16000 ar 18000 Height MWD/MTl MWD/MTI: :YIWD/MTU MWD/MTU MWD/MTU .\1WD/MTU MWD/MTl MWD/MTU MWD/MTU (ft)
(30% (75"!. ooo*;. (100% (100"!. (100"/e (100% (100% (100%
Power) Power\ Power\ Powtrl Power) Power) Power\ Power\ Power\
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Table A.2 FQ w(Z) Penalty Factor FQW(Z)
Core Burnup Penalty (MWD/MTU)
Factor All Bumups 1.0200 Note:
- l. The Penalty Factor, which is applied to FQw(Z) for compliance with Surveillance Requirement 3.2.1.2, is the maximum factor by which Fo w (Z) is expected to increase per 31 Effective Full Power Days (EFPD) starting from the bumup at which the FQ w(Z) was determined.
Unit l Cycle 15 WATTS BAR Page 10 of 10 Revision 0