ML20117N640

Application for Amends to Licenses NPF-68 & NPF-81,changing TS Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo

ML20117N640
Person / Time
Site:	Vogtle
Issue date:	06/17/1996
From:	Woodard J GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20117N644	List: ML20117N640 ML20117N647
References
LCV-0826, LCV-826, NUDOCS 9606240006
Download: ML20117N640 (6)

Text

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. . Georgia Power Compa y 333 Piedmont Avenue AtlaNa. Gaorg a 30309 Te:ephone 404 526-3195

' Malhng Adtess 40 inverness Center Parkway Post Once Box 1295 Birmingnam. Alabama 35201 Telephone 205 868-5086

a. o. wooe.,d June 17, 1996 ' " " " ' " " " ' *

• Senior V ce President LCV-0826 Docket Nos. 50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Ladies and G< #'emen:

VOGTLE ELECTRIC GENERATING PLANT REQUEST FOR TECHNICAL SPECIFICATIONS CHANGES ZIRLO* CLAD FUEL RODS In axordance with the provisions of 10 CFR 50.90 and 10 CFR 50.92, Georgia Power Company (GPC) proposes to amend the Vogtle Electric Generating Plant (VEGP) Units 1 and 2 Technical Specifications, Appendix A to Operating Licenses NPF-68 and NPF-81. The proposed change to Technical Specification secticn 5.3.1 allows the use of fuel assemblies containing fuel rods clad with ZIRLO*~

The use of this cladding has previously been reviewed and accepted by the NRC on a generic basis through the review and approval of WCAP 12610-P-A and the api repriate revisions to 10 CFR 50.46 and 50.44, which was the basis of the NRC ctaff s previous approvt! for the use of ZIRLO* clad fuel rods at other nuclearpilants. This WCAP serve as a eference core design report for a fuel assembly design using ZIRLO' clad fuel rods. It presents ne information necessary to apport the licensing basis for the use of fuel assemblies containing ZIRLO* clad fuel rods for fuel rebad regions. It includes me:..anical, nuclear, thermal-hydraulic, accident and radiological evaluations It also ir.cludes appendices to document 23RLO* material properties, support fuel rod performance, and provide LOCA models and evaluat'ons. WCAP-12610-P-A was approved in NRC Safety Evaluations issued on July 1,1991 and October 9,1991. These Safety Evaluations approved the use of VANTAGE +

fiiel design, i.e., ZIRLO* clad fuel and found it acceptable for up to a rod-average burnup level of 60,000 MWD /MTU. Therefore, the proposed change to the VEGP Technical Specifications is an administrative change indicating the expected use of fuel cladding at VEGP which has already been generically accepted by the NRC. l l

This change has been incorporated into the Improved Technical Specifications (ITS) currently under

! review by the NRC. Originally it was anticipated tha; the 17 J.! be approved on a schedule that would hilow the use of ZlRLO* cladding by the fali eT ' de approval of the ITS has been delayed for an unrelated reason; therefore, Georgia Pmer n, iwuestkg this specific change to the current Technical Specifications be approved priu to the first anticipated use of the new cladding at VEGP. Fuel assemblies containing fuel rods clac with 7.lKLO* will be utilized in VEGP Unit 2, beginning with Cycle 6, which is scheduled fcu stcrtup i., the Fall of 1996. Therefore, Georgia Power l Company requests approval of this Technical Specifaion :evisia by August 15,1996.

9606240006 960617 POR ADOCK 05000424 P ?DR i gt l

Ccorgia l'ower U. S. Nuclear Regulatory Commission Page 2 Encicsure i provides a description of the proposed change and the basis for the change. Enclosure 2 provides the basis for a determination that the proposed change does not involve significant hazards considerations. Enclosure 3 provides instructions for incorporating the proposed change into the Technical Specifications. Enclosure 4 provides a conclusion concerning an environmental assessment of the pr, posed change.

In accordance with 10 CFR 50.91, the designated state official will be sent a copy of this letter and the enclosures.

hir. J. D. Woodard states that he is a Senior Vice President of Georgia Power Company and is authorized to execute this oath en behalf of Georgia Power Company and that, to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true.

GEORGIA POWER COhfPANY By: do.

. D. Woodard Sworn to and subscribed before me this / 7Nay o pe1fs ,1996. l

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MW JDW/HWhi/gmb g /

MY COWMGCi' 3XPIR!dS Enclosures F/4-f8 I cc: Georgia Power Company hir. J. B. Beasley, Jr.

hir. hi. Sheibani NORhiS U. S. Nuclear Regulatory Commission hir. S. D. Ebneter, Regional Administrator hir. L. L. Wheeler, Licensing Project hianager, NRR hir. C. R. Ogle, Senior Resident Inspector, Vogtle State of Georgia J. D. Tanner, Commissioner, Department of Natural Resources i

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ENCLOSURE 1 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATION ZIRLO* FUEL CLADDING

.id_ SIS FOR PROPOSED CHANGE Ergposed Change The Vogtle Units 1 and 2 Techtical Specifications, Design Features section 5.3.1 has the following text:

"The core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4 except for two fuel assemblies which may each contain up to twelve (12) fuel rods clad with ZIRLO* Each fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading shall w;- 4 maximum enrichment not to exceed 3.2 weight percent U-235. Reload fuel sho!! be similar in physical design to the initial core loading and shall have a maximum enrichment not to exceed 4.55 weight percent U-235."

In order to allow for the insertion of fuel assemblies clad with ZIRLO into Vogtle reload core designs, the following revision to Technical Specifications Design Features section 5.3.1 is proposed:

"The core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4 or 21IU,0*-except-for-twofuelessemblies whielunay-each<entain-up4o4welve{42) fuel-rods < lad with-Z4RLO*. Each fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading shall have a maximum enrichment not to exceed 3.2 weight percent U-235.

Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment not to exceed 4.55 weight percent U-235." l l

l Basis I i

l In order to implement a long-term fuel management strategy planned by Georgia Power Company (GPC) for the Vogtle Electric Generating Plant (VEGP) Units 1 and 2, Westinghouse VANTAGE-5 fuel assemblies, each containing fuel rods clad with the advanced zirconium alloy cladding material ZIRLO* , will be utilized in future VEGP reload core designs. The use of this cladding has ,

previously been reviewed and accepted by the NRC on a generic basis through the review and l i

approval of WCAP 12610-P-A and the revisions to 10 CFR 50.46 and 50.44. The NRC has approved the use of this type of cladding at other nuclear plants.

The use of ZIRLO* cladding for VEGP does not require the application of any new methodology that has not already been reviewed and approved by the NRC. Currently the Technical Specifications for VEGP allow the use of two lead test assemblies with fuel rods using this type of claddir.g. Each specific fuel cycle design will continue to be evaluated using NRC approved methods and design criteria.

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EhCLOSURE 1 (continued)

} i j BASIS FOR PROPOSED CHANGE l

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This change has been incorporated into the Improved Technical Specifications (ITS) currently under review by the NRC. Originally it was anticipated that the ITS would be approved on a schedule that 4 would allow the use of ZIRLO* cladding by the fall of 1996. The approval of the ITS is currently  ;

l deicyed for an unrelated reason; therefore, Georgia Power is requesting this specific change to the current Technical Specifications be approved prior to the first anticipated use of the new cladding at i VEGP, Fuel assemblies containing fuel rods clad with ZIRLO* will be utilized in VEGP Unit 2, j beginning with Cycle 6, which is scheduled for startup in the Fall of 1996.

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l ENCLOSURE 2

• 1 VOGTLE ELECTRIC GENERATING PLANT l

REQUEST TO REVISE TECHNICAL SPECIFICATION ZIRLO* FUEL CLADDING 10 CFR 50.92 EVALUATION l

Pursuant to 10 CFR 50.92, Georgia Power Company (GPC) has evaluated the attached proposed amendment and has determine' 1 't operation of the facility in accordance with the revised Technical Specifications will not invol' 4gnificant hazards consideration. The basis for this determination is '

as follows.

Analysis The use of this cladding has previously been reviewed and accepted by the NRC on a generic basis through the review and approval of WCAP 12610-P-A and the appropriate revisions to 10 CFR 50.46 and 50.44, which was the basis of the NRC stafl's previous approval for the use ofZIRLO* clad fuel rods at other nuclear plants. This WCAP serves as a reference core design report for a fuel assembly design using ZIRLO* clad fuel rods. It presents the information necessary to support the licensing basis for the use of fuel assemblies containing ZIRLO* clad fuel rods for fuel reload regions. It includes mechanical, nuclear, thermal-hydraulic, accident and radiological evaluations. It also includes appendices to document ZIRLO* material propenies, support fuel rod performance, and provide LOCA models and evaluations. WCAP-12610-P-A was approved in NRC Safety Evaluations issued on July 1,1991 and October 9,1991. These Safety Evaluations approved the use of VANTAGE +

fuel design, i.e., ZIRLO* clad fuel and found it acceptable for up to a rod-average burnup level of 60,000 MWD /MTU. Therefore, the proposed change to the VEGP Technical Specifications is an administrative change indicating the expected use of fuel cladding at VEGP which has already been generically accepted by the NRC.

Summary Based on the information discussed above, the following conclusions can be reached with respect to 10 CFR 50.92. ,

The proposed change does not involve a significant increase in the probability or consequences of an l accident previously evaluated because: l 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 ofZIRLO* 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 operation within the limits will remain in accordance with NRC-approved methodologies. Other than the changes to the fuel assemblies cladding, 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.

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ENCLOSURE 2 (continued) 10 CFR 50.92 EVAL.UATION The 10 CFR 50.46 criteria are applied to the ZIRLO* 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 afTected. ZIRLO* 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.

The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated because:

The possibility for a new or different kind of accident from any accident previously evaluated is not created since the fuel assemblies containing ZIRLO 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 involve any alterations to plant ,

equipment or procedures which would introduce any new or unique operational mode or accident ,

precursor. Therefore, the possibility for a new or different kind of accident from any accident i previously evaluated is not created.  !

The proposed change does not involve a significant reduction in a margin of safety because:

The margin of safety is not significantly reduced since the 7.IRLO* 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 Specifications. Each specific cycle's reload core will continue to be specifically evaluated using NRC approved reload design methods and approved fuel rod design models. This willinclude consideration of the core physics j analysis peaking factor and core average linear heat rate effects.  !

Conclusion Based upon the preceding analysis, GPC has determined that the proposed change to the Technical Specification Design Features section 5.3.1 meets the requirements of 10 CFR 50.92 (c) and does not mvolve a significant hazards consideration.

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