ML20148F997

License Amend Request 97-02,to License NPF-86,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

ML20148F997
Person / Time
Site:	Seabrook
Issue date:	05/29/1997
From:	Feigenbaum T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20148F999	List: ML20148F997 ML20148G001
References
NYN-97060, NUDOCS 9706050122
Download: ML20148F997 (8)

Text

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, Nonh Atlamic Eng Suse Corporation P.O. Box 300 i

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M (603) 474-9T21 l The Northeast Utilities System j May 29,1997 Docket No. 50-443 l

NYN-97060 i

United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

? l Seabrook Station l License Amendment Request 97-02 l

" Technical Soecification 5.3.1 - Fuel Assemblies ZIRLO or Zircalov-4 Fuel Claddine Material" I:

l North Atlantic Energy Service Corporation (Nonh Atlantic) has enclosed herein License Amendment j Request (LAR) 97-02. License Amendment Request 97-02 is submitted pursuant to the requirements of l 10 CFR 50.90 and 10 CFR 50.4. North Atlantic requests that LAR 97-02 be reviewed on an exigent 1 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 v hich 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.

License Amendment Request 97-02 proposes a change to Technical Specification 5.3.1, " Fuel Assemblies." The proposed change replaces the current term "zircaloy" with terminology that explicitly identifies the NRC approved Westinghouse fuel assembly design in use at Seabrook 3tation consisting of assemblies with either "ZlRLO or Zircaloy-4" fuel cladding material. The Seabrook Station Cycle 5 core design incoroorated Vantage 511 fuel utilizing ZIRLO cladding material in addition to the 17X17 STD fuel assemblies with Zircaloy-4 cladding. The Seabrook Station Cycle 6 core design will also consist of Vantage 511 and 17X17 STD fuel assemblies with ZIRLO and Zircaloy-4 cladding material.

The NRC has recently issued similar license _ amendments to several licensees for the purpose of identifying in Technical Specifications the use of ZIRLO fuel cladding material. The specific licensees i are identified in the enclosure. The NRC has also approved Westinghouse topical reports addressing l ZlRLO fuel cladding material. The specific Westinghouse topicals and NRC safety evaluations are l

- referenced in the enclosure. I{

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. NYN-97060/Page 2 Previously,' Technical Specification 5.3.1 specified " zirconium alloy" fuel cladding material, a generic term intended by North Atlantic to accurately describe and encompass the materials ZIRLO or Zirca

4. The use of the term " zirconium alloy" was previously approved by the NRC in Amendment No. 33 to the Seabrook Station Operating License to specifically permit flexibility for future implementation of ZlRLO cladding.

North Atlantic requests that LAR 97-02 be reviewed on an exigent basis pursuant to the requirements of 10 CFR 50.9)(a)(6). The circumstances supporting North Atlantic's request for an exigent review are discussed below.

The proposed change will explicitly recognize in Technical Specification 5.3.1 the NRC approved Westinghouse fuel assembly design in use at Seabrook Station consisting of"ZlRLO or Zircaloy-4" fuel cladding material. Currently, Technical Specification 5.3.1 utilizes the terminology "zircaloy" to describe the fuel assembly cladding, a term which North Atlantic considered generic and accurate with respect to the Westinghouse zirconium alloy fuel assembly cladding materials in use at Seabrook Station.

Previously, Technical Specification 5.3.1 specified " zirconium alloy" fuel cladding material, a generic term intended by North Atlantic to encompass the materials ZlkLO or Zircaloy-4. The generic term

" zirconium alloy" was also incorporated into the Updated Final Safety Analysis Report in Revision 4.

During the Cycle I through Cycle 4 operational periods Technical Specification 5.3.1 specifically identified that the fuel cladding material was Zircaloy-4.

North Atlantic submitted License Amendment i mest 97-01 on February 18,1997 ,2 and received NRC approval in License Amendment 51 on May 13, " 7. Amendment 51 approved a revision to Technical Specification 5.3.1 which had the primary purpose of providing flexibility in the repair of fuel assemblies containing damaged or leaking fuel rods. Amendment 51 authorized " Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations ..." License Amendment Request 97-01 was submitted in accordance with NRC Generic Letter 90-02, Supplement I, " Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications." License Amendment Request 97-01 employed the model Technical Specification 5.3.1 language contained in the GL 90-02S1 as modified slightly by another licensee which had recently received NRC approval. License Amendment 51 also revised the description of fuel assemblies in accordance with GL 90-02S1 language to state that they consist of" . zircaloy clad fuel rods...".

It was very recently identified to North Atlantic by the NRC Project Manager while conducting a plant tour on May 23,1997, and confirmed on May 27,1997, that the Technical Specifications must be revised to identify the specific fuel cladding materials in use at Seabrook Station. North Atlantic concurs with the NRC's assessment and as a result is submitting License Amendment Request 97-02 on an exigent basis to correct Technical Specification 5.3.1 to identify the specific fuel assembly cladding material in use at Seabrook Station North Atlantic believes that the proposed change to Technical Specification l

' " Amendment No. 33 to Facility Operating License NPF-86: Wide-Band Operation and Core Enhancements -

License Amendment Report 93-18 (TAC M87849)", dated November 23,1994

' " License Amendment Request 97-01" dated February 18,1997

l U. S. Nuclear Regulatory Commission l

. NYN-97060/Page 3 l

5.3.'l has very low safety significance and when balanced against the importance of restarting Seabrook Station, on schedule, prior to the summer peak electricity demand, justifies the exigent review being requested.

LAR 97-02 has been reviewed and approved by the Station Operation Review Committee and the Nuclear Safety Audit Review Committee.

As discussed in LAR 97-02,Section IV, the proposed change does not involve a significant hazard consideration pursuant to 10 CFR 50.92. A copy of this letter and the enclosed LAR have been forwarded to the New llampshire State Liaison Officer pursuant to 10 CFR 50.91(b).

North Atlantic has determined that LAR 97-02 meets the criteria of 10 CFR Sl.22(c)(9) for a categorical exclusion from the requirements for an Environmental Impact Statement (see Section VI enclosed).

Should you have any questions regarding this letter, please contact Mr. Terry L. liarpster, Director of Licensing Services, at (603) 773-7765.

Very truly yours, NORTil ATLANTIC ENERGY SERVICE CORP.

_Wh .

kd C. Feigenbaut Executive Vice P esident and Chief Nuclear Officer cc: 11. J. Miller, NRC Regional Administrator A. W. De Agazio, NRC Project Manager J. B. Macdonald, NRC Senior Resident inspector Mr. George L. Iverson, Director New liampshire Office of Emergency Management 107 Pleasant Street Concord, Nil 03301 l

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, s LICE 20SE' AMENDMENT REQUEST NO; 97 42 .

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l This License Amendment Request is submitted by North Atlantic Energy Service Corporation l pursuant to 10 CFR 50.90 and 10 CFR 50.4. The following information is enclosed in support of th*s i License Amendment Request:

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l e Section 1 Introduction and Safety Assessment for Proposed Changes l l

e Section 11 - Markup of Proposed Changes e Section 111 -

Retype of Proposed Changes e Section IV -

Determination of Significant Hazards for Proposed Changes

. Section V - Proposed Schedule for License Amendment issuance and Effectiveness e Section VI - Environmentalimpact Assessment Sworn and Subscribed before me this MQ day of in 6 Y .1997 , gpg 4, b b (ftu u,39

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did C. Feigenbaum

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p Notary Public Executive Vice Pr ident Ny cowgu gg and Chief Nuclear Officer 2(EMD,

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I. INTRODUCTION AND SAFETY ASSESSMENT OF PROPOSED CHANGES A. Introduction License Amendment Request 97-02 proposes a change to Technical Specification 5.3.1, " Fuel Assemblies." The proposed change replaces the current term "zircaloy" with terminology that explicitly identifies the NRC approved Westinghouse fuel assembly design in use at Seabrook Station consisting of assemblies with either "ZlRLO or Zircaloy-4" fuel cladding material. The Seabrook Station Cycle 5 core design incorporated Vantage SH fuel utilizing ZlRLO cladding material in addition to the 17X17 STD fuel assemblies with Zircaloy-4 cladding. The Seabrook Station Cycle 6 core design will also consist of Vantage 5H and 17X17 STD fuel assemblies with ZIRLO and Zircaloy-4 cladding material. The NRC has recently issued similar license amendments to several licensees for the purpose of identifying in Technical Specifications the ,

- use of ZlRLO fuel cladding material. The specific licensees are Callaway, Beaver Valley 2,  !

Vogtle 1 & 2, Byron 1 & 2, Braidwood I & 2, Ft. Calhoun, Maine Yankee, and Calvert Cliffs 1. l The NRC has also approved Westinghouse topical reports addressing ZlRLO fuel cladding material. The specific Westinghouse topicals and NRC safety evaluations are referenced in the Safety Assessment below.

B. Safety Assessment of Proposed Changes BACKGROUND The proposed change will explicitly recognize in Technical Specification 5.3.1 the NRC I approved Westinghouse fuel assembly design in use at Seabrook Station consisting of"ZIRLO l

or Zircaloy-4" fuel cladding material. Currently, Technical Specification 5.3.1 utilizes the i terminology "zircaloy" to describe the fuel assembly cladding, a term which North Atlantic considered generic and accurate with respect to the Westinghouse zirconium alloy fuel assembly cladding materials in use at Seabrook Station. Previously, Technical Specification 5.3.1 specified " zirconium alloy" fuel cladding material, a generic term intended by North Atlantic to encompass the materials ZlRLO or Zircaloy-4. The generic term " zirconium alloy" was also incorporated into the Updated Final Safety Analysis Report in Revision 4. During the Cycle 1 through Cycle 4 operational periods Technical Specification 5.3.1 specifically identified that the fuel cladding material was Zircaloy-4. Further discussion of the license amendment requests and license amendments which authorized these changes are discussed below.

North Atlantic submitted License Amendment Request (LAR) 93-18," Wide Band Operation and ,

Core Design Enhancements (TAC No. M87849)," on November 23,1993 to support Cycle 5 l operation. Several changes to the Seabrook Station Technical Specifications were proposed in LAR 93-18. Specifically, Item 13) of LAR 93-18 stated:

"The fuel assembly description is changed to allow the possibility of future implementation of Zirlo cladding. The thermal performance characteristics of Zirlo were censidered in the revised LOCA analysis which accompanies YAEC-1871. Affects- Technical Specification Design Feature 5.3.1, Fuel Assemblies (Page 5-9)."

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.The proposed change to Technical Specification 5.3.1 was the replacement of the term

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"Zircaloy-4" with the term " zirconium alloy." The term " zirconium alloy" was intended by North Atlantic to accurately describe and encompass the materials ZIRLO or Zircaloy-4.

License Amendment Request 93-18 was approved by the NRC in Amendment No. 33, dated November 23, 1994. In its safety evaluations for Amendment No. 33, the NRC specifically l stated that the term " zirconium alloy" was to provide flexibility for future implementation of ZlRLO cladding.

North Atlantic submitted License Amendment Request 97-01 on February 18,1997, and received NRC approval in License Amendment 51 on May 13,1997. Amendment 51 approved a revision to Technical Specification 5.3.1 which had the primary purpose of providing flexibility in the repair of fuel assemblies containing damaged or leaking fuel rods. Amendment 51 authorized " Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations ...". License Amendment Request 97-01 was submitted in accordance with NRC Generic Letter 90-02, Supplement 1,

" Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications." License Amendment Request 97-01 employed the model Technical Specification 5.3.1 language contained in the GL 90-02S1 as modified slightly by another licensee which had recently received NRC approval. License Amendment 51 also revised the description of fuel assemblies in accordance with GL 90-02S1 language to state that they consist of"... zircaloy clad fuel rods...".

It was very recently identified to North Atlantic by the NRC Project Manager while conducting a -

plant tour on May 23,1997, and confirmed on May 27,1997, that the Technical Specifications must be revised to identify the specific fuel cladding materials in use at Seabrook Station.

SAFETY ASSESSMENT:

The use of fuel assemblies containing ZIRLO material as a fuel clad materiai has been successfully demonstrated at numerous facilities that use Westinghouse VANTAGE + fuel with ZIRLO as the standard cladding material. The earlier generation VANTAGE 5H fuel in use at Seabrook Station also employed the use of ZlRLO cladding. ZlRLO is a new cladding and thimble tube alloy. ZlRLO employs a zirconium alloy similar to Zircaloy-4 but with enhanced corrosion resistance. ZlRLO includes a reduction in the tin and iron content, eliminating the chromium content, and adding one percent niobium.

Nonh Atlantic's LAR 93-18," Wide Band Operation and Core Design Enhancements (TAC No.

M87849)," dated November 23, 1993, noted that the thermal performance characteristics of ZIRLO were considered in the revised LOCA analysis which accompanies YAEC-1871.

Subsequently, Amendment No. 33 was isstied to incorporate the majority of changes proposed by LAR 93-18. Amendment No. 33 provided a summary of the changes proposed by North Atlantic which noted the implementation of fuel design enhancements, namely, low AP Zircaloy grids and zirlo cladding. The majority of the Safety Evaluation addresses North Atlantic's submittals supporting the proposed changes which included the supporting reanalyses of those transients and accidents which are discussed in Seabrook Station's UFSAR. Specifically, Section 2.2 of the Safety Evaluation noted: "The revised LOCA analysis assumes the swelling / burst characteristics of the zirlo fuel cladding which bounds the Zircaloy cladding as well. This permits flexibility for future implementation of zirlo cladding. TS 5.3.1 is revised accordingly."

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4 "Section 2.3, Thermal and Hydraulic Analysis makes note of the fuel cladding performance parameters that were detennined using FROSSTEY-2, an NRC-approved code. ]

1 In addition, the Cycle 5 Core Reload Safety Evaluation for Seabrook Station, dated October j 1995, also notes the effects of the additional zirconium in the core and concludes that the '

conclusions of the UFSAR with respect to the radiologicsl consequences for the Design-Basis  !

LOCA event are not affected, doses remain "well within the design limits given in 10 CFR Part  !

100 and General Design Criteria 19."

The Westinghouse ZIRLO fuel desin is described in topical report WCAP-12610-P-A,

" VANTAGE + Fuel Assembly Reference Core Report," which was approved by NRC Safety Evaluations dated July 1,1991 and October 9,1901. In addition, the NRC staff also approved the ZlRLO growth model as discussed in a Safety Evaluation dated September 15,1994, for the Westinghouse Topical Report WCAP 12610, Appendix B, Addendum 1," Extended Burnup Fuel Design Methodology and ZlRLO Fuel Perforraance Models." The WCAP-12610 report supports the following conclusions:

1. The mechanical design bases and limits for the ZIRLO clad fuel assembly design are the same as those for Zircaloy-4 clad fuel design, except those for enhanced clad corrosion resistance.

2. The neutronic evaluations have shown that ZIRLO clad fuel nuclear design bases are l satisfied and that the key safety parameter limits are applicable. The nuclear design models !

and methods accurately describe the behavior of ZlRLO clad fuel.

l 3. The thermal hydraulic design basis for the ZlRLO clad fuel is unchanged.

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4. The methods and computer codes used in the analysis of the non-LOCA licensing basis l events are valid for ZlRLO clad fuel and all licensing basis criteria will be met.

5. The large break LOCA evaluation model was modified to reflect the behavioi of the ZlRLO clad material during a LOCA. It is concluded that the revised evaluation model satisfies the intent of 10 CFR 50.46 and Appendix K of 10 CFR Part 50. There is no significant impact  ;

on typical large break LOCA analysis results for the ZlRLO model revisions. I NUREG-1431, " Standard Technical Specifications for Westinghouse Plants," specifically includes ZlRLO as an acceptable cladding material.

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II. MARKUP OF PROPOSED CIIANGES Refer to the attached markup of the proposed changes to the Technical Specifications. The attached markup reflects the currently issued revision of the Technical Specifications listed below. Pending Technical Specifications or Technical Specification changes issued subsequent to this submittal are not reflected in the enclosed markup.

The following Technical Specification is included in the attached markup:

Technical Snecification Iltle Page(s)

TS 5.3.1 Fuel Assemblies 5-9 Page 4