ML20202F602
| ML20202F602 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 12/31/1998 |
| From: | Gurley J, Redden D, Wurz E COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20202F598 | List: |
| References | |
| NUDOCS 9902040105 | |
| Download: ML20202F602 (12) | |
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o-NUCLEAR FUEL MANAGEMENT DEPARTMENT NUCLEAR DESIGN IS70RMATION TRANSMITTAL E SAFETYRELATED Originatics Organization NDIT No.
NFM91400232 O NON. SAFETY RELATED E NuclearFuelManagement Seq. No.
1 O REGULATORY RELATED O Other(specify)
Page 1 of 12 Station Byron Unit 1 Cycle 9 Generic To: W. G. Kouba, Byron Site Engineering Manager Subject Bvron Unit 1 Cycle 9 Core Operatina Limiu Report in its Format and W(z) Function E. Wurt NS
[W
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O Preparer Preparer's Signature d
Date J. Gurley
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50 W Reviewer R
's Sig
[
Date
~
D.' Redden 3ih6-NFM Supervuor NFM Supervisor's Signature Date Status ofInformation:
E Verified O Unverined O EngineeringJudgement Method and Schedule of Verification fa Unverified NDITs-Desuiption ofInformation: Attached is the Byron Unit i Cycle 9 Core Operating Limiu Report (COLR) in the ITS format and W(z) function.
Purpose ofInformation: Tids sequence supercedes Sequence 0. his sequence incorporates station-requested changes. "Ihe COLR incorporate the ITS format and W(Z) function. Byron Station is requested to perfam a Plant Review (ITR and FORC) of this document. Upon completion of the Plant Review, Byron Station is to transmit the COLR portion to the Nuclear Regulatory Commission pursuant to Technical Specification 5.6.5.
Please provide NFM (Erich Wurz) with a copy of Byron Stadon's completed Plant Review and COLR submittal to the NRC.
Source of Infornation: 1) NDIT NFM9800224, Seq. O, "W(z) curves for Technical Specification Fq surveillance via W(z) mettodology for BY1C9 and BY2C8," dated November 9,1998.
- 2) PND Calculation Number SP-24. "BYlC9 SPIL - Unfavorable Exposure Time," Project BYlC9 SPIL, dated November 24,1997,
- 3) Letter from M. Lesniak to U. S. Nuclear Regulatory Commission, " Application for Amendment to Facility Operating Licenses. Reactivity Control Systems; Byron Station Uniu 1 and 2, NPF -37/66: Docket Nos. 50-454/455; Braidwood Uniu 1 and 2 NPF.72/77 Docket Noe. 50-456/457 " dated December 21,1995.
Supplemental Distribution: J. Bauer (DG).
K. N. Kovar / R. J. Niederer (BY)
B. J. Adams / J. E. Langan (BY)
E. Young (DG)
H. S. Kim / T. A. Shackelford (DG)
Byror. Central Files DG Central Files 9902040105 990129 9
PDR ADOCK 05000454 p
NDIT NFM9800232 Seq.1 Page 2 of 12
. CORE OPERATING LIMITS REPORT (CoLR) for BYRON UNIT 1 CYCLE 9
?,
- 1.0 CORE OPERATING LIMITS REPORT
~ This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 9 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (1,TS).
The Technical Specifications affected by this report are listed below:
- LCO. 3.1.1 Shutdown Margin (SDNi) -
LCO 3.1.3 - Moderator Temperature Coefficient LCO 3.1.4 - Rod Group Alignment Limits.
1' LCO 3.1.5 Shutdown Bank Insertion Limits.
LCO-3.1.6 Control Bank Insertion Limits
- LCO 3.1.8 Physics Tests Exceptions-Mode 2 LCO' 3.2.1 Heat Flux Hot Channel Factor (Fo(Z))
.LCO' 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%).
LCO ' 4 3.2.3. Axial Flux Difference (AFD)
-LCO 3.3.9 Boron Dilution Protection System (BDPS)
Boron Concentration.
1 '.
- The portions of the Technical Requirements Manual affected by this report are listed below:
TRM TLCO'3.1.b '
Boration Flow Paths-Operating
- TRM TLCO 3.1.d Charging Pumps-Operating -
TRM TLCO 3.1.f Borated Water Sources Operating
- TAM TLCO 3.1.h.
Shutdown Margin (SDM)- MODE 1 and MODE 2 with keff 21.0 -
4 a
TRM TLCO 3.1.1-Shutdown Margin (SDM)- MODE 5
-~ TRM TLCO 3.1.] '
Shutdown and Control Rods l'
n r, l.
a 1
..-w r
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. _ _ _ _._. _. ~. - _ _.. ~....
L NDIT NFM9800232 Seq.- 1 1
Page 3 of 12
)
CORE OPERATING LIMITS REPORT (coLR) for BYRON UNIT 1 CYCLE 9 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 are applicable for the entire cycle unless otherwise identified.: These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5.
4 s
2.1 Shutdown Marain iSDM)
~
The SDM limit for MODES 1, 2,3, and 4 is:
2.1.1 The SDM shall be greater than or equal to 1.3% Ak/k (LCOs 3.1.1, 3.1.4, 3.1.5,
. 3.1.6, 3.1.8, 3.3.9; TRM TLCOs 3.1.b,3.1.d,3.1.f. 3.1.h, and 3.1.j).
The SDM limits for MODE 5 are:
2.1.2.1 SDM shall be greater than or equal to 1.0% Ak/k (LCO 3.1.1) 2.1'2.2 SDM shall be greater than or equal to 1.3% Ak/k (LCO 3.3.9; TRM TLCO 3.1.1.
i i
and 3.1.J)
' 2.2 jdoderator Ternsereture Coefficient (LCO 3.1.3)
- The Moderator Temperature Coefficient (MTC) limits are:
-i 2.2.1 The BOUARO/HZP-MTC shall be less positive than +2.5 x 10 Ak/k/'F.
2.2.2.,The EOUARO/HFP-MTC shall be less negative than -4.1 x 10" Ak/k/*F.
2.2.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be less negative than or equal to -3.2 x 10" Ak/k/*F.
. where: BOL stands for Beginning of Cycle Life "ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power
(
1 a,;
NDIT NFM9800232 Seq.1 Page 4 of 12 CORE OPERATING LIMITS REPORT (coLR) for BYRON UNIT 1 CYCLE 9 2.3 Shutdown Bank Insertion Limit (LCO 3.1.5) 2.3.1 All shutdown banks shall be withdrawn to at least 228 steps.
2.4 Control Bank Insertion Limits (LCO 3.1.6) 2.4.1 The control banks shall be limited in physical insertion as s' hown in Figure 2.4.1.
2.4.2 - 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.
1 2.4.3 The control banks shall be operated with a 113 step overlap.
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NDIT NFM9800232 Seq.1 Page 5 of 12 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 9 Figure 2.4.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power (29 %, 228)
. (79%, 228)
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2M BANK B 180
? go i w (100%,161) 3 E
(0%,162) l 140 i
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6 120
/ l BANK C l
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80
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BANK D
-m,
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- l(0%,47) l j
/
(30%, 0) o d
0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent) i
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NDIT NFM9800232 Seq.1-Page 6 of 12
- CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 9 2.5 Heat Flux Hot Channel Factor (F (ZM (LCO 3.2.1) 9 2.5.1 Fq
- Fq(Z)s xK(2)for P s0.5 0.5^
Fq* K(2)forP >0.5 Fq(Z)s x
P where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F," = 2.60 K(Z)is provided in Figure 2.5.1.
2.5.2 W(Z) is provided in Figures 2.5.2.a through 2.5.2.c.
The normal operation W(Z) values have been determined at burnups of 150, 8000 and 15600 MWD /MTU.
For this cycle, the F*o(z) penalty factors are equal to 2% per 31 Effective Full 7
Power Days. These values shall be~ used to increase the F*o(z) as per
~ Surveillance Requirement 3.2.1.2. The'2% penalty factor shall be used at all.
cycle burnups.
s
- Multiplication Factor = 1.02 ;
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NDIT NFM9300232 Sey.1 Page 7 of 12 CORE OPERATING LIMITS REPORT (coLR) for BYRON UNIT 1 CYCLE 9 i
Figure 2.5.1: K(Z)- Normalized Fq(Z) as a Function of Core Height 1.1 l
(0.0, 1.0)
(6.0, 1.0) 1 (12.C70.925) 0.9 0.8 f7 0.7 Y'
30.6
=
1o 0.5 z
8
+LOCA Limiting I
- 04 Envelope I
0.3
- 0.2 0.1 0
0 1
2 3
4 5
6 7
8 9
10 11 12 BOTTOM Core Height (ft)
TOP J
n
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NDIT NFM9800232 e
Seq.1 Page 8 of 12 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 9 Neight M X W(Z)
Feet Byron Unit ! Cycle 9 0.00 1.0000 0.20 1.0000 Fi ure 2.5.2.a 8
0.40 1.0000 0.60 1.0000 Sanmary of WCZ)Functwn at 150 MwDMIU 0.80 1.0000 (Top and Bonain 15% Exchuled per VCAP.10216) 1.00 1.0000
~
1.20 1.0000 1.40 1.0000
(
l.60 1.0000 1
1.25 1.80 1.2147 2.00 1.2088 2.20 1.203' 2.40 1.1985 2.60 1.1342
' 2.80 1.!W4 j
3.00 '
l.18'A 3 20 1.1715 3.40 1.l(46 1.20 3.60 1.1'31 9 3.80 1.1593 P
4.00 1.1561 4.20 1.1529 4.40 1.1499 4.60 1.1467 4.80 1.1426 4,
5.00 1.1384 5.20 1.1341 e
5.40 1.1295
'e 5.60 1.1245 5.80 1.1179 5
6.00 1.!!54 E
i j
6.20 1.1163 e
E 6.40 1.1213 6.60 1.1257 6.80 1.1290 7.00 1.1312 1.10 7.20 1.1323 o
7.40 1.1328 N** '
-7.60 1.1324 7.80
-1.1306
'8.00 1.1273' 8.20 -
1.1226 8 40
't.!!71 4.60 1.1108 8.80 1.1039 1.05 9.00.
1.0980 9.20 1.094A 9.40 1.0940 9.60 1.0938 9.80 1.0930 10.00 1.0927
'10.20 1.0930 10.40 1.0000 10.60 l#XX) 10.80 1.0000 1.00 j g 00 g,0ooo 0.00 2.00 4.00 6.00 8.00 10.00 12.00
- 11.20 1.0000 CORE HEIGHT (FEET)
I1.40 1.0000 11.60 1.0000 11.80 1.0000 s
12.00 1,0000
l l
NDIT NFM9800232 1
Seq.1-Page 9 of 12 CORE OPERATINO LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 9 1[eight. MkX W(Z)
Feet Byron Unit 1 Cycle 9 0.00
-1.0000 0.20 1.0000 Figure 2.5.2.b j
0.40 1.0000 0.60 1.0000 Sanmary of W(Z)Functka at 8000 MWDSITU 0.80 1.0000 (Top and Bonan 15% Excluded per WCAP-10216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1.0000 1.25 1.80 f.2280 i
2.00 12216 2.20 1.2153 2.40 1.2100 2.60
.1.2049.
2.80 1.1982
. 3.00 1.1888 i
3.20 -
1.1795
)
3.40 1.1732 g,;o j
160 1.1692 3.80 1.1668 4.00 1.1642 4.20 1.1611 -
e
' 4.40 1.1580 -
e 4.60 1.1546 4.80 1.1506 i
5.00 -
1.1456 520 1.1399 1.15
^
5.40
- 1.1Mi o
5.60 1.1279 I
5.80 1,1195 e
ose.
6.00 1.1178
--e.*-
6.20 1.1202 6.40 1.1254 m,-
6.60 '
l.1297 6.40 1.1329 7.00 1.1346 1.10 7.20 '
1.1353 4
7.40 1.1721 7.60 1.1341 7.80' I.1316 8 00 1.1274 8.20 1.1220 8.40 1.1159 8.60 1.1092 8 80 1.1020 05 9.00 1.0967
- 9.20 1.0944 9.40 1.0941 9.60 1.0936 9.80 1.0923 10.00 1.0918 10.20 1.0922 10.40 <
1.0000
~-
10.60-1.0000 10.80 1.0000 33.00 33xn 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.20 1.0000 CORE HEIGHT (FEET) i1.40 iAno 11 60 1.0000 11.80 1.0000 12.00.,
1.0lX0
NDIT NFM9800232 Seq. I 1
Page 10 of 12 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 9
}{eight hfAX W(Z)
Feet Byron Unit 1 Cycle 9 0.00 1.0000 0.20 1.0000 Figure 2.5.2.c 0.40 1.0000 0.60 1.0000 Summary d W(Z) Function at 15600 MWD /MTU 0.80 1.0000 (Tg and Bottom 15% Excluded per WCAP 10216) 1.00 1.0000 1.20 1.0000 1.40 1.0000
\\
1.60 1.0000 1.25 1.80 1.2452 2.00 1.2361 2.20 1.2267 2.40 1.2380 2.60 1.2093 2.80 1.1998 3.00 1.1877 3.20 1.1755 3.40 1.1678 1.20 3.60 1.1653 3.80 1.1639 j
o 4.00' 1.1619 4.20 1.1592 l
4.40 1.1564 4.60 1.1533 4
4.80 1.1493 5.00 1.1445 1
5.20 1.1397 1.15 5.40 1.1340 o
5.60 1.1273 e
5.80 1.1300 4
6.00 1.1366
.I 6.20 1.1420 g
6.40 1.1467 g
6.60 1.1505 g
6.80 1.1528 7.00 1.1535 1,10 7.20 1.1529 7.40 1.1513 q
~
7.60 1.1486 -
7.80 1.1445 8.00 1.1385 8.20 1.1313 8.40 1.1229 8.60 1.1139 8.80 1.1063 1.05 9.00 1.0989 9.20 1.0936 9.40 1.0927 9.60 1.0945 9.80-1.0980 10.00 1.1016 10.20 1.1044 10.40 1.0000 10.60 1.0000 9,co __.
. 10.80 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.00 1.0000 11.20 1.0000 CORE HEIGHT (FEET) 11.40 1.0000 11.60 1.0000 11.80 1.0000 12.00 1.0000
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i-NDIT NFM9800232 L
Seq.1 Page 11 of 12 l-CORE OPERATING LIMITS REPORT (coLR) for BYRON UNIT 1 CYCLE 9 l'
'2.6 Nuclear Enthalo'v Rise Hot Channel Factor (F"y (LCO 3.2.2)-'
l.
2.6.1 F"s s F27[1.0 + PFas(1.0 - P)]
4 L1 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER f-FJ" = 1.70
~ PFan = 0.3 -
- 2.7 Axial Flux Difference (AFD) (LCO 3.2.3) 2.7.1 The AXIAL FLUX DIFFERENCE (AFD) target band is +3, -12% of the target flux
. difference.
? 2.7.2 'The AFD Acceptable Operation Omits are provided in Figure 2.7.1.
. 2.8 -
Boron Concentration (LCO 3.9.1) -
l 2.8.1 ~ The refueling boron concentration shall be greater than or equal to 2000 ppm.'
1 l-
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NDIT NFM9800232 Seq,1 Page 12 of 12 CORE OPERATINO LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 9 FIGURE 2.7.1: Axial Flux Difference Limits As A Function of Rated Thermal Power lO?
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'1 1, X) d UNACCEPTABLE UNACCEPTABLE OPERATION i
OPERATION 7
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(31,50) l ACCEPTABLE OPERATION j
2:
50
-40
-30
-20
-10 0
10 20 30 40 50 Flux Difference %