ML20134Q345

Proposed Tech Specs 5.3.1 Re Fuel Assemblies

ML20134Q345
Person / Time
Site:	Seabrook
Issue date:	02/18/1997
From:	NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:
Shared Package
ML20134Q216	List: ML20134Q212 ML20134Q329 ML20134Q345
References
NUDOCS 9702260395
Download: ML20134Q345 (7)

Text

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}** OESIGN FEATURES

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, DESIGN PRESSURE AND TEMPERATURE s

maximum internal pressure of 52.0 psig and a tempera

[ 5.3 REACTOR CORE gsgAT" ATTKbf

" FUEL ASSEMBLIES poKbib b V ele 12'-

5.3. he core 1 contain i

ntaining 264 uel rods el fuel assemblies v each fuel asse y i'

a nominal a ve fuel len with a zirconium a y. Each. fuel.r shall have of 144 inches. initial core ding shall have a a taum enrichoe i similar n physical of 3.15 weight pe ent U-235. Re ad fuel shall be enrich nt of 5.0 w ght percent ign to the initial ore loading a U-235. i j shall have a maximum ) t CONTROL ROD ASSEMBLIES

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5.3.2 ~

! The core shall contain 57 full-length control rod assemblies.

i length control rod assemblies shall contain a nominal 142 inches The full-of absorber material.

i indium, and 5% cadmium.The nominal values of absorber material shall be 80% silv tubing. All control rods shall be clad with stainless steelt.

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5.4 REACTOR COOLANT SYSTEM .

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< . DESIGN PRESSURE AND TEMPERATURE j 5.4.1 i

The Reactor Coolant System is designed and shall be maintained: l i

s a.

! In accordance with the Code requirements specified in Section 5.2 i of the FSAR, with allowance for normal degradation pursuant to the i

applicable Surveillance Requirements,

b. For a pressure of 2485 psig, and

c.

For a temperature of 650*F, except for the pressurizer which is 680*F.

t j VOLUME i i

5.4.2 cubic feet as a nominal T, of 588.5'F.The total water and steam l volum 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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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 (UO2 ) as fuel 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 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 l

Retype of Proposed Changes Page 11

a, DESIGN FEATURES I

- l 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 fuel material.

rods for fuelLimited rods substitutions of zirconium alloy or stainless steel filler in used.

configurations, may, be accordance with NRC-approved applications of fuel rod Fuel assemblies shall be limited to those fuel methods bases. and shown by tests or analyses to co A limited number of lead test assemblies that have not completed presentative testing may be placed in nonlimiting core regions.

Reload fuel a maximum enrichment of 5.0 weight percent U-235.shall CONTROL R00 ASSEMBLIES l

5.3.2 The core shall contain 57 full-length control rod assemblies.

length material. control rod assemblies shall contain a nominal The142 full- inches oi The nominal values of absorber material shall . 15% be 80% si i

indium, and 5% cadmium.

tubing.

All control rods shall be clad with stainless steel 5.4 REACTOR COOLANT SYSTEM 1 DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System 1s designed and shall be maintained:

a.

In accordance with the Ccde requirements specified in Section 5.

of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.

For a pressure of 2485 psig, and c.

ForF.a 680 temperature of 650 F. except for the pressurizer which is YOLUME 5.4.2 cubic feet at a nominal T,yThe of 588.5 F. total water and steam volume of the 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 ;

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i IV[ DETERMINADON OF SIGNIFICANT HAZARDS FOR PROPO3ED CHANGES 4

L License Amendment Request (LAR) 97-01 proposes a change to reactor core fuel assembly j j .. 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:  :

4 1 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 l 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 l steel or zirconium alloy filler rods in the fuel assemblies the radiological consequences l 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 i

specifically evaluated for each cycle reload core in which they are inserted using

. 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 'l j constitute a significant hazard.-

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