ML20134Q345
| ML20134Q345 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 02/18/1997 |
| From: | NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | |
| Shared Package | |
| ML20134Q216 | List: |
| References | |
| NUDOCS 9702260395 | |
| Download: ML20134Q345 (7) | |
Text
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OESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE maximum internal pressure of 52.0 psig and a tempera s
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5.3 REACTOR CORE gsgAT" ATTKbf
" FUEL ASSEMBLIES poKbib V ele 12'-
b 5.3.
he core 1 contain fuel assemblies v each fuel asse y
i ntaining 264 uel rods el with a zirconium a i
a nominal a ve fuel len of 144 inches.
initial core ding shall i
y.
Each. fuel.r shall have have a a taum enrichoe of 3.15 weight pe ent U-235. Re ad fuel shall be i
similar n physical ign to the initial ore loading a shall have a maximum )
enrich nt of 5.0 w ght percent U-235.
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CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 57 full-length control rod assemblies.
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length control rod assemblies shall contain a nominal 142 inches of absorber The full-i material.
indium, and 5% cadmium.The nominal values of absorber material shall be 80% silv i
tubing.
All control rods shall be clad with stainless steelt.
i 5.4 REACTOR COOLANT SYSTEM
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DESIGN PRESSURE AND TEMPERATURE 1
j 5.4.1 The Reactor Coolant System is designed and shall be maintained:
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s In accordance with the Code requirements specified in Section 5.2 a.
of the FSAR, with allowance for normal degradation pursuant to the i
applicable Surveillance Requirements, i
b.
For a pressure of 2485 psig, and For a temperature of 650*F, except for the pressurizer which is c.
680*F.
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VOLUME i
i 5.4.2 cubic feet as a nominal T, of 588.5'F.The total water and steam volum l
5.5 METEOR 0 LOGICAL TOWER LOCATION j
5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
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PDR SEABROOK - UNIT 1 5-9
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II. LAR 97-01 Pronosed Techntesi Snecifications Channes 5.3 REACTOR CORE FUEL ASSEMBLIES
- 5.3.1 The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of cylindrical zircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO ) as fuel material. Limited substitutions of zirconium alloy or stainless 2
steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.
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l SECTION III Retype of Proposed Changes Page 11
DESIGN FEATURES a,
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DESIGtl PRESSURE AND TEMPERATURE maximum internal pressure of 52.0 psig and a tem 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 193 fuel assemblies.
consist of a matrix of cylindrical zircaloy clad fuel rods with an initialEac composition of natural or slightly enriched uranium dioxide (UOy as fue material.
Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods in accordance with NRC-approved applications of fuel rod configurations, may, be used.
Fuel assemblies shall be limited to those fuel methods and shown by tests or analyses to co bases.
A limited number of lead test assemblies that have not completed presentative testing may be placed in nonlimiting core regions.
a maximum enrichment of 5.0 weight percent U-235.shall Reload fuel CONTROL R00 ASSEMBLIES l
5.3.2 The core shall contain 57 full-length control rod assemblies.
length control rod assemblies shall contain a nominal 142 inches o The full-material.
The nominal values of absorber material shall be 80% si indium, and 5% cadmium.
i tubing.
All control rods shall be clad with stainless steel
. 15%
5.4 REACTOR COOLANT SYSTEM 1
DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System 1s designed and shall be maintained:
In accordance with the Ccde requirements specified in Section 5.
a.
of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and For a temperature of 650 F. except for the pressurizer which is c.
680 F.
YOLUME 5.4.2 cubic feet at a nominal T,yThe total water and steam volume of the of 588.5 F.
55 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1 SEABROOK - UNIT 1 5-9 Amendment No. 6. 34
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Section IV l
Determination of Significant Ilazards for Proposed Changes i
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DETERMINADON OF SIGNIFICANT HAZARDS FOR PROPO3ED CHANGES 4
L License Amendment Request (LAR) 97-01 proposes a change to reactor core fuel assembly j
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design features requirements contained in Technical Specification 53.1," Fuel Assemblies". The l
proposed change will allow the use of solid stainless steel or zirconium alloy filler rods in fuel assemblies to replace failed or damaged fuel rods. In addition, the proposed change is in j
accordance with the guidance provided in Generic L.etter 90-02, Supplement 1, " Alternative Requirements For Fuel Assemblies In The Design Features Section of Technical Specifications".
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In accordance with 10CFR50.92, North Atlantic has reviewed 'the attached proposed change (s) l and has concluded that they do not involve a significant hazards consideration (SHC). The basis for the conclusion that the proposed change does not involve a SHC is as follows:
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1.
The prcposed change does not involve a sign,ficant increase in the probability or consequences cfan accidentpreviously evaluated.
3 All Seabrook Station fuel assemblies will continue to meet the same fuel assembly and fuel rod design bases as the current fuel assemblies. In addition, the 10 CFR 50.46 criteria (acceptance criteria for emergency core cooRg systems) will continue to be satisfied for all fuel assemblies. The use of reconstituted fuel assemblies will not result in a change to the Seabrook Station reload design and safety analysis limits. Since the j
dose predictions in the safety analyses are not sensitive to the presence of solid stainless steel or zirconium alloy filler rods in the fuel assemblies the radiological consequences of accidents previously evaluated in the safety analyses remain valid. Therefore, neither the pro *. ability of occurrence nor the consequences of any accident previously evaluated is significantly increased.
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2.
The proposed change does not create the possibility cf a new or djerent kind cf accidentfrom anypreviously analyzed.
All Seabrook Station fuel assemblies will continue to satisfy the same design bases used for previous fuel regions. Since the original design criteria are being met, initiators for any new accident have not been introduced. All design and performance criteria will continue to be met for the use of reconstituted assemblies containing solid stainless steel or zirconium alloy filler rods. No new single failure mechanisms have been created, and.
the use of reconstituted fuel assemblies does not involve any alteration to plant equipment or procedures which would introduce any new or unique operational modes or accident precursors. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously analyzed.
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3.
The prcposed change does not involve a signficant reduction in the margin cfscfety.
The Seabrook Station reload design and safety analysis limits are unchanged by the use of fuel assemblies containing solid stainless steel or zirconium alloy filler rods. The use of all fuel assemblies will continue to be limited by the normal core operating conditions j
defined in ~ the Technical Specifications.
Reconstituted fuel assemblies will be i
specifically evaluated for each cycle reload core in which they are inserted using i
approved reload design methods and approved fuel rod design models and methods.
i This will include consideration of the core physics analysis peaking factors and core i
average linear heat rate effects, as well as evaluation of the impact on safety and LOCA j
analyses, and on core thermal hydraulics (DNB). The 10 CFR 50.46 criteria' will l
continue to be applied each cycle and analyses or evaluations will be performed each cycle to confirm that 10 CFR 50.46 will be met. Therefore, the margin er safety as
- defined in the Bases to the Technical Specifications is not significantly reduced by the j
proposed change.
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l Based on the above evaluation, North Atlantic concludes that the use of a limited number of solid stainless steel or zirconium alloy filler rods will not significantly affect the performance of l
the fuel assemblies, and that the proposed change to the Technical Specifications does not
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constitute a significant hazard.-
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