ML20084L400

Forwards TS Change Request 251 to License DPR-50,revising TS 5.3.1.1 to Describe Use of Advanced Clad Assemblies.B&W Fuel Co Proprietary TR BAW-2133P Describing Advanced Cladding Demonstration Program Also Encl.Proprietary TR Withheld

ML20084L400
Person / Time
Site:	Three Mile Island
Issue date:	06/01/1995
From:	Broughton T GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20084L402	List: ML20084L400 ML20084L420 ML20084L435
References
C311-95-2210, NUDOCS 9506070198
Download: ML20084L400 (2)

Text

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l e E GPU Nuclear Corporation j ggggf Route 441 South P.O. Box 480 Middletown, Pennsylvania 17057-0480 (717)944-7621 l Writer's Direct Dial Number:

(717) 948-8005 l June 1,1995 C311-95-2210 l

l U. S. Nuclear Regulatory Commission Attention: Document Contml Desk Washington, DC 20555

Subject:

Three Mile Island Nuclear Generating Station, Unit 1 (TMI-1) l Operating License No. DPR-50 l Docket No. 50-289 Technical Specification Change Request (TSCR) No. 251 Use of Advanced Clad Assemblies In accordance with 10 CFR 50.4(b)(1), attached is Technical Specification Change Request No. 251 (Attachment I).

Enclosed is a Certificate of Service for this request certifying service to the chief executives of the township and county in which the facility is located, as well as the designated official of the Commonwealth of Pennsylvania, Bureau of Radiation Protection.

The purpose of this TSCR is to request that the TMI-l Technical Specifications be revised to describe the use of two zirconium-based advanced fuel md cladding materials which fall outside the specification range of Zircaloy or ZIRLO cladding material. Four rods of each of the advanced cladding materials will be used in each of two (2) fuel assemblies scheduled to be loaded during the upcoming 11R refueling outage (September 1995).

Pursuant to 10 CFR 50.91(a)(1), enclosed is our analysis, applying the standards in 10 CFR 50.92 to make a determination of no significant hazards considerations. As stated above, pursuant to 10 CFR 50.91(a), we have provided a copy of this letter, the proposed change in Technical Specifications, and our analyses of significant hazards considerations to Mr. Robert Barkanic, the designated representative of the Commonwealth of Pennsylvania.

Attachment II contains an analysis which addresses the criteria of 10 CFR 50.12 to permit the granting of an exemption to the requirements of 10 CFR 50.46,10 CFR 50.44, and Appendix K to 10 CFR 50. As described in the TSCR, the pmposed change will result in some of the allowed fuel cladding materials being outside the scope of "Zircaloy" as specified in these regulations. Therefore, an exemption to these requirements is hereby 9506070198 950601 #

PDR ADOCK 05000289 [

p PDR GPU Nuclear Corporation is a subsidiary of General Pubhc Utihties Corporation l

' Document Control Desk 7 C311-94-2210  !

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requested. Issuance of the exemption by June 23,1995, would preclude any potential impact  !

on fuel assembly mfabrication costs. However, GPU Nuclear requests appmval of this  !'

exemption no later than July 21,1995, to support final fuel delivery schedules for the upcoming 11R refueling outage.

Attachment III is a B&W Fuel Company (BWFC) Repon which describes the advanced i cladding demonstration program. Attachment IV is a BWFC evaluation of the M4 and M5 l cladding material to demonstrate the acceptability of the performance of these alloys in  !

TMI-l Cycles 11,12, and 13. Please note that the information contained in these repons is l proprietary to BWFC, and should be withheld fmm public disclosure. An affidavit j

. supponing this proprietary designation is included in each of the Attachments.

Sincerely, WAk gML T. G. Broughton l Vice Pmsident and Director, TMI '

DJD/ pip

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Enclosure:

Cenificate of Service for TSCR No. 251 Attachments: I TSCR No. 251 1 II Application for Exemption from Requimments of 10 CFR 50.46,10 CFR 50.44, and Appendix K to 10 CFR 50 that Fuel Cladding Must be Zircaloy III BWFC Topical Repon BAW-2133P IV BWFC Proprietary Document, " Evaluation of M4 and M5 Cladding Alloys for TMI-1" c: Administrator, Region I TM1 Senior Resident Inspector TMI-l Senior Project Manager l

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