ML20086A356
| ML20086A356 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 11/07/1991 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20086A352 | List: |
| References | |
| NUDOCS 9111190064 | |
| Download: ML20086A356 (4) | |
Text
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l 3.
GENERAt DESCRIPTION The McGuiro Unit i reactor core is described in detail in Chapter 4 of the FSAR (Reference 1).
The coro consisto of 193 assemblies, each of which is a 17-by-17 array containing 264 fuel roda, 24 guido tuboo, and 1 incore instrument tube.
There are 117 burned FAo in the coro; 116 FAs are of the Westinghouse Optimized Fuel Assembly (OFA) design; 1 FA 10 e reconstituted Mark-BW special cladding assembly.
The reconstituted Mark-BW FA contains 9 fresh fuel rods contcining natural uranium dioxido polloto.
This Mark-BW special cladding nosombly was reconstituted after being discharged from McGuire Unit 1 Cycle 6.
The 76 fresh FA's are of the Mark-BW dooign (Reference 2); Two of theso fresh FAs are Mark-BW special cladding assemblies (Reference 3). The fuel rod 4
outsido diamotors are 0.360 and 0.374 inches, and the wall l
thicknesses are 0.0225 and 0.024 inches for the OPA and Mark-BW designs, respectively.
The Mark-BW fuel consists of dished end, cylindrical pollets of uranium dioxide, (See Table 4-1 for data).
The average nominal fuel loadings ars 421.40, 454.66, 424.67, 425.78, and 454.91 kg of uranium por fuel e
assembly in batches 7A, 7C, 8A, 9A, and 10A, respectively.
The initial enrichments of batcheo 7A, 7C, 8A and 9A woro 3.40, 2.92 3.60, and 3.7 5 wt% 8"U, respectively.
The dooign enrichment of froph batch 10 is 3.75 wt% 8"U.
The 39 batch BA and 76 batch 9A assemblics will be shuffled to now locations.
One batch 7C FA discharged at the end of Cycle 6 will be reinsarted as the contor assembly.
One batch 7A FA discharged at the and of Cycle 6 will be reinsertad at location 0-11.
The 76 fresh batch 10 assemblics will be loaded into the core in a basically symmetric checkerboard pattern.
Figure 3-2 is a quarter core map showing the burnup and region reference number with corresponding initial enrichmonta of each assembly at the beginning of Cyclo 8.
Cycle 8 will be operated in a feod-and-blood mode.
Coro reactivity is controlled by 53 rod cluster control assemblies (RCCAs),
64 BPRAs, and soluble boron chim.
The Cycle 8 locations of the 53 rod cluster control assemblies with their respectivo designations are indicated in Figure 3-3.
The Cycle 8 locations and number of pins of 3.0 wt% B C-Al Oi3 BPRA cluotort are shown in Figure 3-4.
,?Illl'0064 011107 l
glIa nnOCK 0%GC69 IV-5 POR
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FIGURE 3-1 CORE LOADING DIAGRAM FOR McGUIRE UNIT 1 CYCLE 8 REGION REFERENCE NUMBERS R2010N NUMBERS FREV10tts Cons toCAT10Ns J61 E06 JO2 K31 J73 K36 J43 1
SA 10A 9A 10A 9A 10A DA K 13 F
K-11 F
Fall F
F-13 J43 J34 R$5 J41 E57 H10 K03 J33 E71 JOS J70 2
9A 9A 10A 9A 10A DA 10A 9A 10A 9A 9A Jale D 13 F
L-04 F
N 16 F
B-04 F
N 13 0 14 J07 J39 E13 J30 Ret H64 J26 H51 E50 J46 941 J65 J33 3
9A 9A 10A DA 10A 6A 9A SA 10A 9A 10A 9A DA B-07 E-07 F
0 04 F
K-15 H 15 F 15 F
J-04 F
F 07 F-07 J10 F468 B73 E30 H34 K33 J14 E01 H21 E54 H53 E28 J26 4
9A 10A SA 10A SA 10A 9A 10A SA 10A SA 10A 9A C-12 F
F=04 F
B-01 F
0 06 F
L-01 F
B+04 F
N 12 J12 Ell J16 E64 J23 J50 H44 R62 H16 J31 J27 E52 J40 R76 J51
^
5 9A 10A 9A 10A 9A 9A SA 10A 8A 9A 9A 10A 9A 10A SA C-06 F
M-09 F
B 08 S 14 R-09 F
A 09 L-14 5 11 F
D*09 F
N 06 F51 J28 E47 R07 J73 J22 E60 H62 Ele J63 J20 H39 K66 J52 K12 6
10A 9A 10A GA 9A 9A 10A SA 10A 9A 9A SA 10A 9A 10A F
M 05 F
R 11 B 11 J-OS
-F F 13 F
H 07 P-11 A-11 F
D-05 F
J66 E32 H30 E59 H24 E39 H42 E63 H43 E65 H26 E75 B54 E07 J47 7
9A 10A BA 10A SA
.10A SA 10A SA 10A BA 10A SA 10A 9A 8 06 F
A-06 F
0 01 F
M-02 F
D-02 F
J 01 F
R 06 F
L 06 E74 H29 J30 J60 E00 H76 K32 072' K11 H2O K23 J19 J74 H12 E3D 8
104 BA 9A 9A 10A SA 10A 7C 10A SA 10A 9A 9A SA 10A F
C-14 A-06 J 06 F
B-13 F
F-10 F
F-03 F
0 10 R-08 Nf4 F
J53 E37 H72 E16 Hol E56 H71 K44 H55 R67 H33 K40 H49 E17 J10 9
9A 10A 8A 10A SA 10A SA 10A SA 10A 8A 10A SA 10A 9A B-10 F
A-10 F
0-15 F
M-14 F
D-14 F
J 15 F
R 10 F
L-10 E39 Joe E10 H67 J76 J44 K09 H02 Elp J11 J54 H37 E53 J69 E69 10 10A 9A 10A 4A 9A 9A 10A SA 10A 9A 9A SA 10A 9A 10A F
M 11 F
R-05 B-05 H-09 F
B 03 F
0-06 F 05 A 05 F
D-11 F
d68 E20 J59 E04 J64 J57 H75 E03 019' J31 J00 E37 J75 E73 J29 11 SA 10A 9A 10A 9A 9A SA 10A 7A 9A 9A 10A 9A 40A 9A C-10 F
M 07 F
H-05 3-02 R-07 F
E-07 L-02 L-06 F
D-07 F
N 10 J01 E69 H47 E72 H57 E36 JO9 E24 H03 E49 H15 Ee58 J50 12 9A 10A 8A 10A SA 10A 9A 10A SA 10A SA 10A DA c-04 F
F 12 F
R-15 F
J 10 F
L-15 F
B 12 F
N 04 J17 J56 K35 J45 K10 H68 J06 H27 E05 Je9 E61 J67 J37 13 9A 9A 10A 9A 10A SA 9A SA 10A 9A 10A 9A 9A B 09 E-09 F
0 12 P
E-01 H+01 F-01 F
J 12 F
F-09 F-09 J36 J48 E43 J24 K34 H66 E21 J35 K42 J03 J55 14 9A 9A 10A 9A 10A DA 10A SA 10A 9A 9A J-02 D-03 F
L-12 F
C-02 F
3-12 F
M-03 0 02 J71 K70 J15 Ele J62 K25 J13 15 9A 10A 9A 10A 9A 10A 9A E-03 F
K-05 F
F-05 F
F-03 A
F N
N L
E J
H 0
F B
D C
S A
KAZ REGION REFERENCE NUMEER YY REGION NUMBRA E-EE CYCLE 7 LOCATIONS
- Full core locations H-00 and 0-11 refer to cycle 6 locations.
- Assemblies K45 and K46, in locations C-12 and N-04, respectively, are MkBW special cladding assemblies.
FIGURE 3-2 ENRICHMENT AND DOC DURNUP DISTRIBUTION FOR McGUIRE UNIT 1 CYCLE 8 H
0 F
E D
C B
A l
26689.0 0
22507.4 0
21751.1 12817.6 22509.9 0
l 8
28503.7 0
25952.9 0
22841.4 16748.5 25194.5 0
7c 10A 8A 10A 9A 9A 8A 10A 0
25649.3 0
26301.2 0
25731.4 0
21548.4 9
0 28207.9 0
30386.1 0
30294.1 0
22469.8 10A BA 10A 8A 10A 8A 10A 9A 22507.4 0
20390.3 17601.7 21198.4 0
21186.6 0
10 25185.8 0
22256 21248 26843.4 0
22368.3 0
SA 10A 9A 9A BA 10A 9A 10A 0
26284.0 17609.7 21573.4 0
21162.4 0
21322.3 il 0
30337.5 21264.8 23124.0 0
22249.5 0
22354.5 10A 8A/7A 9A 9A 10A 9A 10A 9A 21751.1 0
22175.9 0
25676.2 0
19505.0 12 22772.0 0
26821.6 0
28228.7 0
21861.7 9A 10A 8A 10A BA 10A 9A 12848.3 25794.6 0
21169.5 0
21753.8 18906.9 13 16795.4 30308.1 0
22257.8 0
22960.5 21560.1 9A BA 10A 9A 10A 9A 9A 22509.9 0
21214.2 0
19575.1 18916.9 AVElmGE 14 25942.8 0
22383.9 0
21855.6 21571 MAXIMUM 8A 10A 9A 10A 9A 9A REGION No.
0 21572.4 0
21338.0 15 0
22474.3 0
22368.5 10A 9A 10A 9A FUEL ENRICHMENT CYCLES NUMBER OF BOC BURNUP RERLQH TYPE W/O U-235 AURNED ASSEldBLIES MWD /MTH 7A (OFA) 3.40 2
1 24,481 7C (MK-BW)*
2.92 2
1 26,689 8A (OFA) 3.60 2
39 24,435 9A (OFA) 3.75 1
76 20,053 10A (MK-BW) 3.75 0
76 0
CORE 193 13,071
- MKBW Reconstituted demonstration assembly NOTE: Core locations J-05, G-05, J-11 are region 8A assemblies and core location G-11 is a region 7A assembly.
The BOC burnup for the assembly at core location G-11 is 24,481 l
MWD /MTU.
I t
l 5.
NUCLEAR DESIGN 5.1 Ehyaica_CharacLcrintics Table 5-1 provides the core physica parameters for Cycles 7 and B. The values were generated using the methodology described in DPC-NF-2010A (Reference 7) and are valid for the design cycle length (370 EFPD plus 10 EFPD).
Figure 5-1 illustratos a representative relativo power distribution for the beginning of Cycle 8 at full power.
This case was calculated by using tho PD007 methodology as described in DPC-NP-2010A (Reference 7) as part of the design depletion.
This case containod equilibrium xenon and rods in the All Rods Out (ARO) position.
Ultrasonic testing of fuel assemblies to be loaded in McGuire 1 Cycle 8 discovered a failed fuol rod in assembly H63. This assembly was schedulod to be loaded in core location G-ll.
The replacement assembly, Gl9, has neutronic charactoristics similar to assembly H63.
An evaluation of the roload design with this replacement assembly showed negligible changos in core characteristics and confirmed the applicability of the original reload safety evaluation performed for McGuiro Unit 1 Cycle 8.
During verification of the control rod insertion limits specified in the COLR, calculated ejected rod worths and their adherence to acceptance critoria wore considered.
The adequacy of the shutdown margin with Cycle 8 stuck rod worths is damonstrated in Tablo 5-2. The shutdown margin calculations include a 10% uncortainty available rod worth.
The shutdown calculation at the end of Cyclo 8 was analyzed at 380 EFPD.
5.2.
Changes in Nuclear Desion The core design changes for Cycle 8 include the use of Mk-BW fuel assemblies and DPRAs with variable numbers of poison rods as described in Section 3.
The Cycle 8 physica parameters appearing in this report were calculated with the PDQ07 and EPRI-NODE-P codes.
These codes and methods were approved by the NRC as documented in Reference 7.
The PD007 calculations were performed in two dimensions; the EPRI-NODE-P calculations were performed in three dimensions.
The Reactor Protection System (RPS) limits and Operational limits for the coro woro verified by analyses for this fuel cycle using methodology approved by the NRC in Reference 8 and are provided in the COLR. Revisions to the COLR for Cycle 8 are presented in Section 8.
IV-10