ML20148G001

Proposed Tech Specs Replacing Term Zircaloy W/Terminology That Identifies NRC Approved Westinghouse Fuel Assembly Design Consisting of Assemblies W/Either ZIRLO or Zircaloy- 4 Fuel Cladding Matl

ML20148G001
Person / Time
Site:	Seabrook
Issue date:	05/29/1997
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20148F999	List: ML20148F997 ML20148G001
References
NUDOCS 9706050124
Download: ML20148G001 (7)

Text

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DESIGN FEATURES l l

DESIGN PRESSURE AND TEMPERATURE l

5.2.2 The containment building is designed and shall be maintained for a  !

maximum internal pressure of 52.0 psig and a temperature of 296 F 0

53 REACTOR CORE f FUEL ASSEMBLIES \ E. LD o f

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5.3.1 The reactor shall contain 193 fue assemblies. Each assembly shall i consist of a matrix of cylindricalCnrg lad fuel rods with an initial l composition of natural or slightly enri uranium dioxide (UO2 ) as fuel l 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 i shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.

CONTROL R00 ASSEMBLIES 5.3.2 The core shall contain 57 full-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber i material. The nominal values of absorber material shall be 80% silver, 15% '

indium, and 5% cadmium. All control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:

a. In accordance with the Code requirements specified in Section 5.2 of the FSAR. with allowance for normal degradation pursuant to the .

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.

VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12.255 cubic feet at a nominal Tg of 588.5 F.

5.5 (THIS SPECIFICATION NUMBER IS NOT USED) 9706050124 970529 PDR ADOCK 05000443 P PDR SEABROOK - UNIT 1 5-9 Amendment No. frl.

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III. RETYPE OF PROPOSED CHANGES 1

h Refer to the attached retype of the proposed changes to the Technical Specifications. The l attached retype reflects the currently issued version of the Technical Specifications. Pending Technical Specification. changes or Technical Specification changes issued subsequent to this j submittal are not reflected in the enclosed retype. The enclosed retype should be checked for >

continuity with Technical Specifications prior to issuance.

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DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The containment building is designed and shall be maintained for a maximum internal pressure of 52.0 psig and a temperature of 296 F.

5.3 REsCTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of cylindrical ZIRLO or Zircaloy-4 clad fuel rods with an l initial composition of natural or slightly enriched uranium dioxide (UO ) as fuel material. Limited substitutions of zirconium alloy or stainless sleel filler rods for fuel rods in accordance with NRC-a) proved applications of fuel rod configurations, may be used. Fuel assemblies s1all 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 j 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.

l CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 57 full-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber mater ial . The nominal values of absorber material shall be 80% silver. 15%

! indium, and 5% cadmium. All control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM j i

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! DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:

a. In accordance with the Code requirements specified in Section 5.2 l of the FSAR. with allowance for normal degradation pursuant to the t

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.

VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12.255 cubic feet at a nominal Tm of 588.5 F.

5.5 (THIS SPECIFICATION NUMBER IS NOT USED) l SEABROOK - UNIT 1 5-9 Amendment No. f4.

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• l IV. DETERMINATION OF SIGNIFICANT IIAZARDS FOR PROPOSED CII ANGES License Amendment Request (LAR) 97-02 proposes a change to reactor core fuel assembly j design feature requirements contained in Technical Specification 5.3.1, " Fuel Assemblies." The '

proposed change will allow the use of fuel assemblies containing ZIRLO or Zircaloy-4 as a fuel l

cladding material for fuel rods at Seabrook Station.

In accordance with 10 CFR 50.92, North Atlantic has reviewed the attached proposed change and l has concluded that it does not involve a significant hazards consideration (SHC). The basis for the conclusion that the proposed change does not involve a SHC is as follows:

1. The proposed change does not involve a significant increase in the probability or consequences ofan accidentpreviously evaluated.

The methodologies used in the accident analyses remain unchanged. The proposed change does not change or alter the design assumptions for the systems or components used to mitigate the consequences of an accident. Use of ZIRLO fuel cladding does not adversely affect fuel performance or impact nuclear design methodology. Therefore, accident analysis results are not significantly impacted.

The operating limits will not be changed and the analysis methods to demonstrate I operation within the limits will remain in accordance with NRC-approved ,

I methodologies. Other than the fuel design enhancements to the fuel assemblies cladding and grids, there are no physical changes to the plant associated with this Technical Specification change. A safety analysis will continue to be performed for each specific reload cycle to demonstrate compliance with all fuel safety design bases.

The 10 CFR 50.46 criteria are applied to the ZlRLO clad fuel rods. The use of these fuel assemblies will not result in a change to the reload design and safety analysis limits.

Since the original design criteria are met, the ZlRLO clad fuel rods will not be an initiator for any new accident. The clad material is similar in chemical composition and has similar, physical and mechanical properties as Zircaloy-4. Thus, the cladding integrity is maintained and the structural integrity of the fuel assembly is not affected.

ZlRLO cladding improves corrosion performance and dimensional stability. Since the dose predictions in the safety analyses are not sensitive to the fuel rod cladding material used, the radiological consequences of accidents previously evaluated in the safety analysis remain valid.

2. The proposed change does not create the possibility of a new or di((erent kind of accidentfrom anypreviously analy:ed.

The possibility for a new or different kind of accident from any accident previously evaluated is not created since the fuel assemblies containing ZlRLO clad fuel rods will satisfy the same design bases as that currently used for Zircaloy-4 clad fuel assemblies.

All design and performance criteria will continue to be met and no new single failure mechanisms have been defined. In addition, the use of ZlRLO fuel assemblies does not Page 6

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- j involve any alterations to plant equipment or procedures which would introduce any new i or unique operational mode or accident precursor. Therefore, the possibility for a new or i different kind of accident from any accident previously evaluated is not created.

3. The proposed change does not involve a sigmficant reduction in the margin ofsafety.

The margin of safety is not signiGcantly reduced since the ZlRLO clad fuel assemblies will not change the reload design and safety analysis limits. Their use will take into consideration the normal core operating conditions allowed for in the Technical SpeciGcations. Each specific cycle's reload core will continue to be speciGeally evaluated using NRC approved reload design methods and approved fuel rod design models. This will include consideration of the core physics analysis peaking factor and l core average linear heat rate effects. I Based on the above evaluation, North Atlantic concludes that the use of fuel assemblies

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containing ZlRLO clad fuel rods will not signiGeantly affect the performance or safety analyses  ;

of the plant, and that the proposed change to the Technical SpeciGcations does not constitute a  ;

signiGeant hazard.

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. 1 V. PROPOSED SCHEDULE FOR LICENSE AMENDMENT ISSUANCE AND EFFECTIVENESS North Atlantic requests that LAR 97-02 be reviewed on an exigent basis pursuant to the requirements of 10 CFR 50.91(a)(6) and that a license amendment be issued to support startup from the current refueling outage (i.e. MODE 2). North Atlantic is currently conducting Refueling Outage 5 with the current best estimate for achieving criticality (MODE 2) on June 16, 1997. It should be noted, however, that North Atlantic believes that there are multiple opportunities available to improve on this schedule which may result in MODE 2 being achieved earlier than June 16,1997. North Atlantic will keep the NRC apprised of schedule changes that may result in MODE 2 being achieved earlier than June 16,1997.

North Atlantic requests a license amendment having immediate effectiveness and implementation required within 60 days.

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VI. ENVIRONMENTAL IMPACT ASSESSMENT North Atlantic has reviewed the proposed license amendment against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not involve a significant hazards consideration, nor increase the types and amounts of effluent that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, North Atlantic concludes that the proposed change meets the criteria delineated in 10CFR51.22(c)(9) for a categorical exclusion from the requirements for an Environmental Impact Statement.

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