ML20030A574
| ML20030A574 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 11/11/1976 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20030A572 | List: |
| References | |
| NUDOCS 8101100111 | |
| Download: ML20030A574 (16) | |
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CONSUMERS PorER COMPANY BIG ROCK POINT PLANT 1
1 SPECIAL REPORT NO 24 CYCLE 14 START-UP REPORT
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Prepared By: CONSUMERS POWER COMPAIPI November 11, 1976 i
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A, 1M RODUCTION The 14th cycle at Big Rock Point was designed for operation between 220 and 230 Mwt (rated power) for a period of approximately 256 effective full power days (5 GWD/ST). The core consists of the following fuel types:
Fuel Type No. of Assemblies General Electric Reload ?
36 Nuclear Fuel Service Demonstration Assemblies 4
Exxon Nuclear J-2 2
Exvan Nuclear Reload G 21 Exxon Nuclear Reload G2 21 Each of the Reload G, NFS-DA, J-2 and seven of the Reload G2 assemblies are plutonium recycle, mixed oxide designs. All but one fresh assembly j
inserted this cycle were Reload G2. That one was Reload G.
B.
EXPERII M S Modifications were made to fourteen (14) assemblies during the 13th refueling outage for experimental purposes. They are:
Experiment Modified Assemblies 1.
General Electric Corner F32,F36,F47,F51,F56, Rod Experiment F60,F63,F64,F65,F66, F67,F68 2.
General Electric Hydrogen F84 Impurity Test 3
Exxon Nuclear Clad Study G21 The following is a brief description of these modifications.
1.
GE Corner Rod Experiment This experiment was continued from Cycle 13 A description of this experiment and its effects on core operation can be found
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in a letter to the Directorate of Licensing dated March 26, 1974.
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GE Long-Term Hydrogen Impurity 'iest Prosr. ram The General Electric long-term hydrogen impurity test continues from Cycle 11. During this refueling, eleven (11) of the experimental rods were replaced by new rods containing similar experiments. This experiment could help eliminate internal hydriding as a fuel failur9 mechanism. The rod transferals were handled by a facility change and will be described in the 1976 Big Rock Point annual report.
3 ENC Clad Study Three (3) fuel rods were removed from G21 and replaced by solid Zr rods. The rods removed provide comparison data between annealed, highly ductile and stress relieved clads (PCI data). The experiment was handled as a facility change and will be described in the 1976 Big Rock Point annual report.
4.
Reactor Start-Up Core shutdown margin was verified by withdrawal of the strongest blade and withdrawal of an adjacent blade six (6) notches as required by the Technical Specifications. Computer calculations indicated a total shutdown margin in excess of 3 5% A k/k with the highest worth blade (3.7% Sk/k) withdrawn from the core. Two rcd shutdown margin was shown not to be available.
The Cycle 14 BOC cold critical control rod pattern differed from computer predictions by three notches (approximately 0.2% Ak/k).
Figure 1 shows the predicted and actual critical control rod patterns.
Tne moderator temperature coefficient test was conducted as required by Technical Specifications Section 5.2.4.
Results of the test indicated a maximum addition of reactivity of 40p from ambient (~70 F) to approximately 122 F, well within the Technical Specifications limit of one dollar. Figures 2 and 3 are plots of y vs temperature and the temperature coefficient (A / AT) vs temperature.
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Initial power escalation was very slow (occurring over a period of about six weeks). The slow start-up is related to the General Electric concept of fuel preconditioning. Fluxwire measurements were taken at power level' of ~150.0,177 3,194.2, 200.6 and 210 9 MWt. Figures 4 through 11 are comparisons of the actual and eniculated flux shapes for the last fluxwire run. Good agreement is indicated. Even with good agreement., expected power levelt haven't been attained. MAPLIUR values have limited power to ~ 215 MWt.
F fuel (F75) is limiting and indications are that it will be limiting throughout the cycle. Offgas activity has been the lowest ever, thus far.
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FIGURE 1 ACTUAL VS PREDICTED BOC 14 COLD CRITICAL k
ROD POSITIONS (23=OUT)
A B
C D
E F
1 5
7 5
6 2
6 0
0 0
0 5
3 5
0 0
0 0
7 4
7 0
0 0
0 5
5 5
0 0
0 0
6 6
6 5
7 5
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PREDICTED CRITICAL A
B C
D E
F 1
5 7
5 7
2 7
0 0
0 0
5 3
5 0
0 0
0 7
4 7
0 0
0 0
5 5
5 0
0 0
0 7
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6 6
5 7
5 ACTUAL CRITICAL
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REACTIVITY VS TEMPERATURE BOC14
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d' = 0.311515E-4 SEC
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BIG ROCK POINT
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REACTIVITY COEFFICIENT VS TEMPERATURE BOC14 3.0 2.0 m
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TEMP - F l UUn_Uhluss1rtL
FIGURF. 4 NORMAllZED AXIAL PROFILE
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BIG ROCK POINT FLUXWIRES O
FLUXWIRE DATA 9 76 COMPUTER PREDICTIOblS A LOCATION No1 1.6 1.5 1.4 1.3 1~2 O
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40 60 80 100 120 14 0 160 180 TOP FLUXWIRE UNITS ( 1/2 INCH)
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FIGURE 5 NORMAllZED AXlAL PROFILE
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FLUXWIRE DATA 9 76 COMPUTER PREDICTIONS A LOCATION No 2 1.6 1.5 1.4 oO O S h
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i FIGURE 6 NORMALIZED AXIAL PROFILE
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FLUXWIRE DATA 9 76 COMPUTER PREDICTIONS A LOCATION No 3 1.6 1.5 1.4 1.3 ggg D
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TOP FLUXWIRE UNITS (1/2 INCHES)
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FLUXWIRE DATA 9 76 COMPUTER PREDICTIONS A LOCATION No4 1.6 -
1.5 1.4 AA OO A
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FIGURE 8 NORMAllZED AXIAL PROFILE
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FLUXWIRE DATA 9 76 COMPUTER PRED!C.ilONS A LOCATION No 5 1.6 1.5 1.4 1.3 DBn 1.2 A
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FLUXWIRE DATA 9 76 COMPUTER PREDICTIONS A LOCATION No 6 1.6 1.5 1.4 1.3 o O O
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FIGURE 10 NORMAllZED AXIAL PROFILE BIG ROCK POINT
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FLUXWIRES O
FLUXWIRE DATA 9 76 COMPUTER PREDICTIONS A LOCATION No 7 1.6 1.5 1.4
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FLUXWIRE DATA f
9 - 2 8 - 76 COMPUTER PREDICTIONS A LOCATION No 8 1.6 1.5 14 o2 2 1.3 h
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