ML20215C753
| ML20215C753 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/12/1987 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20215C712 | List: |
| References | |
| 87TSB07, 87TSB7, NLS-87-103, NUDOCS 8706180232 | |
| Download: ML20215C753 (10) | |
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ENCLOSURE 2 TO NLS-87-103 I
PROPOSED TECHNICAL SPECIFICATION PAGES BRUNSWICK-1 FUEL ASSEMBLY / FUEL STORAGE DESCRIPTIONS (87TSB07) i i
i 8706180232 870612' PDR ADOCK 05000324 (5197 MAT /ccj)
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SUMMARY
LIST OF REVISIONS j
PAGE NO.
DESCRIPTION OF CHANGE 5-1 Revised Specification 5.3.1 to restrict fuel designs to those j
approved by the NRC. Eliminated reference to maximum i
enrichment.
54 Continuation of revision to Specification 5.3.1.
5-5 Revised Specification 5.6.1.1 to limit the k-infinity of new fuel assemblies.
Revised Specification 5.6.1.2 to limit k-infinity rather than the..
enrichment of fuel assemblies.
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(5197 MAT /ccj )
(BSEP-1-105) i 3.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 1
I 5.1.1 The exclusion area shall be as shown in Figure 5.1.1-1.
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i LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1.2-1, based on
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the information given in Section 2.2 of the FSAR.
j SITE BOUNDARY 5.1.3 The SITE BOUNDARY shall be as a shown in' Figure 5.1.3-1.
'For the purpose of effluent release calculations, the boundary for atmospheric-i releases is the SITE BOUNDARY and the boundary for liquid releases is the SITE BOUNDARY prior to dilution in the Atlantic Ocean.
5.2 CONTAINMENT CONFIGURATION 5.2.1 The PRIMARY CONTAINMENT is a steel-lined reinforced concrete structure composed of a series of vertical right cylinders and truncated cones which form a drywell. This drywell is attached to a suppression chamber through a series of vents. The suppression chamber is a concrete steel-lined pressure vessel in the shape of a torus. The primary containment has a minimum free air volume of (288,000) cubic feet.
DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained for:
Maximum internal pressure 62 psig.
a.
b.
Maximum internal temperature: drywell 300 F.
0 suppression chamber 200 F.
c.
Maximum external pressure 2 psig.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 560 fuel assemblies.
The mechanical design of all fuel assemblies contained in the core shall be consistent with those presented and approved by the NRC in the fuel vendor's generic fuel design licensing topical report.
1 BRUNSWICK - UNIT 1 5-1 Amendment No.
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(BSEP-1-105)
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l DESIGN FEATURES 5.3 REACTOR CORE
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i CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 137 control rod assemblies, each consisting of a cruciform array of stainless steel tubes containing approximately 143 inches or boron carbide, B C, powder or hafnium absorber 4
rods surrounded by a cruciform-shaped stainless steel sheath, i
5.4 REACTOR COOLANT SYSTEM 1
DESIGN PRESSURE AND TEMPERATURE 5.4.1 The nuclear boiler and reactor recirculation system'is designed and shall be maintained:
I a.
In accordance with the code requirements specified in Section 4.2 of j
the FSAR, with allowance for normal degradation pursuant to the 1
applicable Surveillance Requirements.
4 b.
For a pressure of 1250 psig, and c.
For a temperature of 575 F.
VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 18,670 cubic feet.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown in Figure 5.1.1-1.
BRUNSWICK - UNIT 1 5-4 Amendment No.
(BSEP-1-105) i l
DESIGN FEATURES' 5.6 FUEL STORACE 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 gg 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 sp'ent 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 keff equivalent to less than 0.95 with the storage pool filled.with unborated water with:
'I a.
PWR fuel assemblies with a maximum infinite core geometry lattice multiplication factor less than or equal to 1.411st 20*C.
b.
BWR fuel assemblies with a maximum infinite core geometry lattice' multiplication factor less than ior equal to 1.33 at 20*C.
5.6.1.3 The k for the unpoisoned racks includes a conservative allowance of 0.5% ak/k f,ggor uncertainties. The k gg calculated for the poisoned rar.ks includes the sum of all appropriate bi,ases and the root-mean-square (RMS) of-the uncertainties.
DRAINACE i
1 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 116'4".
CAPACITY l
5.6.3 The fuel storage pool is designed and shall be maintained with a storage capacity limited to 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.
t BRUNSWICK - UNIT 1 5-5 Amendment No.
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ENCLOSURE 3 TO NLS-87-103
-1 PROPOSED TECHNICAL SPECIFICATION PAGES i
BRUNSWICK-2 FUEL ASSEMBLY / FUEL STORAGE DESCRIPTIONS (87TSB07)
($197 MAT /ccj )
SUMMARY
LIST OF REVISIONS PAGE NO.
DESCRIPTION OF CHANGE -
5-1:
Revised Specification 5.3.1 to restrict fuel designs to those approved by the NRC. Eliminated reference to maximum enrichment.
3-4 Continuation of revision to Specification 5.3.1.
5-5 Revised Specification 5.6.1.1 to limit the k-infinity of new fuel assemblies.
Revised Specification 5.6.1.2 to limit k-infinity rather than the enrichment of fuel assemblies.
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(5197 MAT /cej)
(BSEP-2-106) l 5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1. 1 The exclusion area shall be as shown in Figure 5.1.1-1.
LOW POPULATION ZONE q
5.1.2 The low population zone shall be as shown in Figure 5.1.2-1.
SITE BOUNDARY 5.1.3 The SITE BOUNDARY shall be as shown in Figure 5.1.3-1.
For the purposes-l of effluent release calculations, the boundary for atmospheric releases is the
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SITE BOUNDARY and the boundary for liquid releases is the SITE BOUNDARY prior to dilution in the Atlantic Ocean.
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5.2 CONTAINMENT
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CONFIGURATION 5.2.1 The PRIMARY CONTAINMENT is a steel-lined, reinforced concrete structure
]
composed of a series of vertical right cylinders and truncated cones which form a drywell. This drywell is attached to a suppression chamber through a series of vents. The suppression chamber is a concrete, steel-lined pressure j
vessel in the shape of a torus. The primary containment has a minimum free j
air volume of 288,000 cubic feet.
i DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained for:
l a.
Maximum internal pressure 62 psig.
b.
Maximum internal temperature: drywell 300"F Suppression chamber 200*F c.
Maximum external pressure 2 psig.
l 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 560 fuel assemblies. The mechanical design of all fuel assemblies contained in the core shall be consistent with those presented and approved by the NRC in the fuel vendor's generic fuel design licensing topical report.
BRUNSWICK - UNIT 2 5-1 Amendment No.
(BSEP-2-106) l DESIGN FEATURES 1
5.3 REACTOR CORE j
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain'137 control. rod assemblies, each consisting of a cruciform array of stainless steel tubes containing approximately 143 inches of boron' carbide, B C, powder or hafnium absorber 4
rods surrounded by a cruciform-shaped stainless steel sheath.
1 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The nuclear boiler and reactor recirculation system is designed and shall be maintained.
In accordance with the code requirements specified in Section 4.2 of a.
the PSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 1250 psig, and c.
For a temperature of 575 F.
VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 18,670 cubic feet.
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5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown in Figure 5.1.1-1.
l BRUNSWICK - UNIT 2 5-4 Amendment No.
(BSEP-2 -106 )
7 DESIGN FEATURES 5.6 FUEL STORACE 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 gg 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 j
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 keff 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.
5.6.1.3 The k f r the unpoisoned racks includes a conservative allowance eff of 0.5% Ak/k for uncertainties. The keff calculated for the poisoned racks includes the sum of all appropriate biases and the root-mean-square (RMS) of-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 116'4".
CAPACITY 5.6.3 The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 144 PWR fuel assemblies and 1839 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.
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BRUNSWICK - UNIT 2 5-5 Amendment No.
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