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| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | ||
| page count = 4 | | page count = 4 | ||
| project = | |||
| stage = Other | |||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:. | ||
e | e r* o | ||
==1.0 INTRODUCTION== | ==1.0 INTRODUCTION== | ||
| Line 24: | Line 26: | ||
==SUMMARY== | ==SUMMARY== | ||
Sequoyah Unit 2 is in its first cycle of operation. The. unit is expected to refuel-and be ready for Cycle 2 startup in November 1983. | |||
Sequoyah Unit 2 is in its first cycle of operation. The. unit is | This report presents an evaluation for Cycle 2 operation which demonstrates that the core reload will not adversely affect the safety of the plant. Those incidents analyzed and reported in the FSAR(1) which could potentially be affected by fuel reload have been reviewed for the Cycle 2 design described herein. The applicability of the current nuclear design limits was verified for Cycle 2 using the methods described-in Reference 2. | ||
The results of new analyses have been | |||
This report presents an evaluation for Cycle 2 operation which demonstrates that the core reload will not adversely affect the safety of the plant. Those incidents analyzed and reported in the FSAR(1) which could potentially be affected by fuel reload have been reviewed for the Cycle 2 design described herein. The applicability of the current nuclear design limits was verified for Cycle 2 using the methods described-in Reference 2. The results of new analyses have been | - included, and the justification for the applicability of previous results from the remaining analyses is presented. | ||
It has been concluded that the Cycle 2 design does not cause the previously acceptable safety limits for any incident to be exceeded. | |||
The above operational conclusions are based on the assumption that: (1) | |||
Cycle 1 nominal burnup is 15,100 + 500 MWD /MTV, (2) Cycle 2 burnup is limited to 11,500 MWD /MTU, and (3) there is adherence to plant operating limitations given in the technical specifications and their proposed modifications presented herein. The irapact of this reload has been evaluated and found to be within the safety limit as described in this RSE for Cycle 2. | Cycle 1 nominal burnup is 15,100 + 500 MWD /MTV, (2) Cycle 2 burnup is limited to 11,500 MWD /MTU, and (3) there is adherence to plant operating limitations given in the technical specifications and their proposed modifications presented herein. The irapact of this reload has been evaluated and found to be within the safety limit as described in this RSE for Cycle 2. | ||
During the Cycle 1/2 refueling sixty-eight Region 1 fuel assemblies will be replaced by sixty-eight Region 4 assemblies. One of the 68 Region 4 assemblies has nineteen fuel rods of 3.40 w/o U-235. See Table 1 for the number of fuel assemblies in each region, Figure 1 for the Cycle 2 core loading pattern and Figure 1A for the placement of the nineteen 3.4 w/o U-235 fuel rods. | During the Cycle 1/2 refueling sixty-eight Region 1 fuel assemblies will be replaced by sixty-eight Region 4 assemblies. One of the 68 Region 4 assemblies has nineteen fuel rods of 3.40 w/o U-235. | ||
See Table 1 for the number of fuel assemblies in each region, Figure 1 for the Cycle 2 core loading pattern and Figure 1A for the placement of the nineteen 3.4 w/o U-235 fuel rods. | |||
Nominal design parameters for Cycle 2 are 3411 MWt core pow r, 2250 psia core pressure, nominal core inlet temperature of 546.7 F, and core average linear power of 5.43 kw/ft. | Nominal design parameters for Cycle 2 are 3411 MWt core pow r, 2250 psia core pressure, nominal core inlet temperature of 546.7 F, and core average linear power of 5.43 kw/ft. | ||
s' I | s' I | ||
8309200120 830913 PDR ADOCK 05000328 p | 8309200120 830913 PDR ADOCK 05000328 p | ||
PDR | |||
~ * * | |||
* CORE LOADING PATTEFil | * CORE LOADING PATTEFil Sequoyah Unit 2. Cycle 2 L | ||
X J | |||
4 | H G | ||
F E | |||
D C | |||
4 | B A | ||
R P | |||
N H | |||
4 | 4 4 | ||
4 2 | |||
4 4 | |||
4 I | |||
i 4 | |||
4 | 4 4 | ||
12 | 2 4 | ||
1 4 | |||
4 | 2 4 | ||
4 4 | |||
12 8 | |||
8 12 4* | |||
4 2 | |||
* Assembly contains nineteen fuel rods of 3.40 w/o U-235 | 2 4 | ||
2 3 | |||
4 i 4 2 | |||
2 4 | |||
4 8 | |||
12 12 8 | |||
33 4 | |||
2 3 | |||
3 2 | |||
2 2 | |||
2 2 | |||
3 3 | |||
2 4 | |||
l 4 | |||
4 2 | |||
3 | |||
.2 3 | |||
3 3 | |||
3 3 | |||
2 3 | |||
2 4 | |||
4 12 12 4 | |||
2 4 l 2 3 | |||
2 3 | |||
2 3 | |||
2 3 | |||
2 4 | |||
/ | |||
4 I | |||
12 l 12 4 | |||
4 ' 2 2 | |||
3 3 | |||
2 3 | |||
2 3 | |||
3 2 | |||
2 4 | |||
4 8 | |||
8 90 4 | |||
4 2 | |||
2 3 | |||
3 2 | |||
3 2 | |||
3 3 | |||
2 2 | |||
4 4 | |||
8 8 | |||
4 2 | |||
4 2 | |||
3 2 | |||
3 2 | |||
3 | |||
'2 3 | |||
2 4 | |||
2 4 | |||
12 12 i | |||
~ | |||
~~ | |||
4 4 | |||
4 2 | |||
3 2 | |||
3 3 | |||
3 3 | |||
3 2 | |||
3 2 | |||
4 12 12 8 | |||
4 2 | |||
3 3 | |||
2 2 | |||
2 2 | |||
2 3 | |||
3 2 | |||
4 3 | |||
4 4 | |||
2 2 | |||
4 2 | |||
3 2 | |||
4 2 | |||
2 4 | |||
4 | |||
) | |||
8 12 12 8 | |||
i y | |||
4 4 | |||
4 2 | |||
4 1 | |||
4 2 | |||
4 4 | |||
4 12 8 | |||
8 12 | |||
'I 4 | |||
4 4 | |||
2 4 | |||
4 4 | |||
1 0 | |||
x | |||
- Region Numbar Y | |||
- Number of Burnable Poison Rods | |||
- Secondary Source Rods s | |||
* Assembly contains nineteen fuel rods of 3.40 w/o U-235 mev----w.wve-e---v-- | |||
er--*t w--a3r | |||
-mwwre--re-ayg== | |||
--wew- | |||
=v---wwg ewrve r -w. wwyy w | |||
._m,e...n.-.. | |||
.--e-.w ww-> | |||
y | |||
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+c* | |||
m-- | |||
w}} | |||
Latest revision as of 22:11, 14 December 2024
| ML20080G186 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 09/13/1983 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20080G182 | List: |
| References | |
| TVA-SQN-TS-47, NUDOCS 8309200120 | |
| Download: ML20080G186 (4) | |
Text
.
e r* o
1.0 INTRODUCTION
AND
SUMMARY
Sequoyah Unit 2 is in its first cycle of operation. The. unit is expected to refuel-and be ready for Cycle 2 startup in November 1983.
This report presents an evaluation for Cycle 2 operation which demonstrates that the core reload will not adversely affect the safety of the plant. Those incidents analyzed and reported in the FSAR(1) which could potentially be affected by fuel reload have been reviewed for the Cycle 2 design described herein. The applicability of the current nuclear design limits was verified for Cycle 2 using the methods described-in Reference 2.
The results of new analyses have been
- included, and the justification for the applicability of previous results from the remaining analyses is presented.
It has been concluded that the Cycle 2 design does not cause the previously acceptable safety limits for any incident to be exceeded.
The above operational conclusions are based on the assumption that: (1)
Cycle 1 nominal burnup is 15,100 + 500 MWD /MTV, (2) Cycle 2 burnup is limited to 11,500 MWD /MTU, and (3) there is adherence to plant operating limitations given in the technical specifications and their proposed modifications presented herein. The irapact of this reload has been evaluated and found to be within the safety limit as described in this RSE for Cycle 2.
During the Cycle 1/2 refueling sixty-eight Region 1 fuel assemblies will be replaced by sixty-eight Region 4 assemblies. One of the 68 Region 4 assemblies has nineteen fuel rods of 3.40 w/o U-235.
See Table 1 for the number of fuel assemblies in each region, Figure 1 for the Cycle 2 core loading pattern and Figure 1A for the placement of the nineteen 3.4 w/o U-235 fuel rods.
Nominal design parameters for Cycle 2 are 3411 MWt core pow r, 2250 psia core pressure, nominal core inlet temperature of 546.7 F, and core average linear power of 5.43 kw/ft.
s' I
8309200120 830913 PDR ADOCK 05000328 p
~ * *
- CORE LOADING PATTEFil Sequoyah Unit 2. Cycle 2 L
X J
H G
F E
D C
B A
R P
N H
4 4
4 2
4 4
4 I
i 4
4 4
2 4
1 4
2 4
4 4
12 8
8 12 4*
4 2
2 4
2 3
4 i 4 2
2 4
4 8
12 12 8
33 4
2 3
3 2
2 2
2 2
3 3
2 4
l 4
4 2
3
.2 3
3 3
3 3
2 3
2 4
4 12 12 4
2 4 l 2 3
2 3
2 3
2 3
2 4
/
4 I
12 l 12 4
4 ' 2 2
3 3
2 3
2 3
3 2
2 4
4 8
8 90 4
4 2
2 3
3 2
3 2
3 3
2 2
4 4
8 8
4 2
4 2
3 2
3 2
3
'2 3
2 4
2 4
12 12 i
~
~~
4 4
4 2
3 2
3 3
3 3
3 2
3 2
4 12 12 8
4 2
3 3
2 2
2 2
2 3
3 2
4 3
4 4
2 2
4 2
3 2
4 2
2 4
4
)
8 12 12 8
i y
4 4
4 2
4 1
4 2
4 4
4 12 8
8 12
'I 4
4 4
2 4
4 4
1 0
x
- Region Numbar Y
- Number of Burnable Poison Rods
- Secondary Source Rods s
- Assembly contains nineteen fuel rods of 3.40 w/o U-235 mev----w.wve-e---v--
er--*t w--a3r
-mwwre--re-ayg==
--wew-
=v---wwg ewrve r -w. wwyy w
._m,e...n.-..
.--e-.w ww->
y
--weeee
+c*
m--
w