ML20035E666
| ML20035E666 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/13/1993 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20035E665 | List: |
| References | |
| NUDOCS 9304190075 | |
| Download: ML20035E666 (9) | |
Text
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ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC D.i (ET NOS. 50-325 & 50-324 OPER9 M JCENSE NOS. DPR-71 & DPR-62 REOUEST FOR LICENSE AMENDMENT SPENT FUEL STORAGE DRAINAGE PAGE CHANGE INSTRUCTIONS UNIT 1 Removed Pace inserted Pace 5-5 5-5 UNIT ?
Egynoved Pace Inserted Pace 5-5 5-5 i
E4-1 h41gK05000324
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5 930413 p
ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT SPENT FUEL STORAGE DRAINAGE Marked-Up TECHNICAL SPECIFICATION PAGES - UNIT 1 l
l 1
l
1 DESIGN FEATURES 1
5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The new fuel storage racks are designed and shall be maintained with sufficient center-to-center distance between fuel assemblies placed in the storage racks to ensure a k than 0.95 when flooded with,gg equivalent to less than 0.90 when dry and less unborated water.
In order to meet these limits, i
new fuel assemblies shall have an infinite core geometry lattice multiplication factor less than or equal to 1.31 at 20*C.
l 5.6.1.2 The spent fuel storage racks are designed and shall be maintained with sufficient center-to-center distance between fuel asseeblies placed in the storage racks to ensure a k,gg equivalent to less than 0.95 with the storage pool filled with unborated water with:
PWR fuel assemblies with a maximum infinite core geometry lattice s.
multipiteation factor less than or equal to 1.41 at 20*C.
b.
BWR fuel assemblies with a maximum infinite core geometry lattice multiplication factor less than or_ equal to 1.33 at 20'C.
{
t 5.1.6.3 The k for the unpoisoned racks includes a conservative allokance of 0.5% Ak/k f,ggor uncertainties. The k gg calculated for the poisoned racks includes the sum of all appropriate bi,ases and the root-mean-square (RMS) of the uncertainties.
DRAINACE
\\
5.6.2 The spent fuel storage pool is designed and shall be maintained to i
inadvertent draining of the pool below elevation 110"4". //fi fj" prevent i
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with no more than 160 PWR fuel assemblies and 1803 BWR fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7.1-1 are designed and shall be maintained within the cycle or transient limits of Table 5.7.1-1.
i i
BRUNSWICK - UNIT 1 5-5 Amendment No. 137
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ENCLOSURE 6 l
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT SPENT FUEL STORAGE DRAINAGE l
Marked-Up l
TECHNICAL SPECIFICATION PAGES - UNIT 2
h 1
j i
)
DESICN FEATURES I
4 5.6 FUEL STORACE j
CRITICALITY ~
i a
5.6.1.1 The new fuel storage racks are designed and shall be maintained with sufficient center-to-center distance between fuel assemblies placed in the i
than 0.95 when flooded with,gg equivalent to less than 0.90 when dry and less storage racks to ensure a k unborated water. In order to meet these limits, new fuel assemblies shall have an infinite core geometry lattice multiplication factor less than or equal to 1.31 at 20*C.
[
I 5.6.1.2 The spent fuel storage racks are designed and shall be m'intained a
j vith sufficient center-to-center distance between fuel assemblies placed in the storage racks to ensure a k,gg equivalent to less than 0.95 with the storage pool filled with unborated water with:
a.
PWR fuel assemblies with a maximum infinite core geometry lattice multiplication factor less than or equal to 1.41 at 20*C.
b.
BWR fuel assemblies with a maximum infinite core geometry lattice l
multiplication factor less than or equal to 1.33 at 20*C.
5.1.6.3 The k for the unpoisoned racks includes a conservative allowance of 0.5% ak/k f,ggor uncertainties. The k includes the sum of all appropriate bia,gg calculated for the poisoned racks
(
ses and the root-mean-square (RMS) of the uncertainties.
DRAINACE 5.6.2 The spent fuel storage pool is designed and shall be maintained' to prevent inadvertent draining of the pool below elevation 110". /IS'il*,
CAPACITY l
t 5.6.3 The spent fuel storage pool is designed and shall be maintained with no more than 144 PWR fuel assemblies and 1839 BWR fuel assemblies.
1 5.7 CON CYCLIC OR TRANSIENT-LIMIT 5.7.1 The components identified in Table 5.7.1-1 are designed and shall be maintained within the cycle or transient limits of Table 5.7.1-1.
BRUNSWICK - UNIT 2 5-5 Amendment No. 167
ENCLOSURE 7 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT l
SPENT FUEL STORAGE Dr.AINAGE l
l Typed TECHNICAL SPECIFICATION PAGES - UNIT 1 l
I l
i
' DESIGN FEATURES 5.6 FUEL STORT.GE CRITICALITY 5.6.1.1 The new fuel storage racks are designed and shall be maintained with sufficient center-to-center distance between fuel assenblies placed in the storage racks to ensure a k,,, equivalent to less than 0.90 when dry and less than 0.95 when flooded with unborated water.
In order to meet these limits, new fuel assemblies shall have an infinite core geometry lattice multiplication factor less than or equal to 1.31 at 20*C.
5.6.1.2 The spent fuel storage racks are designed and shall be maintained with sufficient center-to-center distance between fuel assemblies placed in the storage racks to ensure a k,, equivalent to less than 0.95 with the storage pool filled with unborated water with:
a.
PWR fuel assemblies with a maximum infinite core geometry lattice multiplication factor less than or equal to 1.41 at 20*C.
b.
BWR fuel assemblies with a maximum infinite core geometry lattice multiplication factor less than or equal to 1.33 at 20*C.
5.1.6.3 The k,,, for the unpoisoned racks includes a conservative allowance of 0.5% Ak/k for uncertainties. The k,,, calculated for the poisoned racks includes the sum of all appropriate biases and the root-mean-square (RMS) of l
the uncertainties.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 115'11".
l CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with no more than 160 PWR fuel assemblies and 1803 BWR fuel assemblies.
I 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7.1-1 are designed and shall be l
maintained within the cycle or transient limits of Table 5.7.1-1.
l I
BRUNSWICK - UNIT 1 5-5 Amendment No.
ENCLOSURE 8 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT SPENT FUEL STORAGE DRAINAGE Typed TECHNICAL SPECIFICATION PAGES - UNIT 2 i
i i
i
i
' DESIGN FEATURES i
~
5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The new fuel storage racks are designed and shall be maintained with j
sufficient center-to-center distance between fuel assemblies placed in the storage racks to ensure a k,,, equivalent to less than 0.90 when dry and less than 0.95 when flooded with unborated water.
In oider to meet these limits, new fuel assemblies shall have an infinite core geometry lattice multiplication factor less than or equal to 1.31 at 20*C.
i 5.6.1.2 The spent fuel storage racks are designed and shall be maintained with sufficient center-to-center distance between fuel assemblies placed in the storage racks to ensure a k,,, equivalent to less than 0.95 with the storage pool filled with unborated water with-a.
PWR fuel assemblies with a maximum infinite core geometry lattice i
multiplication factor less than or equal to 1.41 at 20*C.
b.
BWR fuel assemblies with a maximum infinite core geometry lattice multiplication factor less than or equal to 1.33 at 20*C.
5.1.6.3 The k,,, for the unpoisoned racks includes a conservative allowance of 0.5% Ak/k for uncertainties.
The k,,, calculated for the poisoned racks I
includes the sum of all appropriate biases and the root-mean-square (RMS) of l
the uncertainties.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 115'11".
l CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with no more than 144 PWR fuel assemblies and 1839 BWR fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT i
5.7.1 The components identified in Table 5.7.1-1 are designed and shall be maintained within the cycle or transient limits of Table 5.7.1-1.
BRUNSWICK - UNIT 2 5-5 Amendment No.
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