ML20091D589

Provides Addl Info Re 910531 License Amend Request to Revise Fuel Assembly Description in Tech Spec 5.3.1,per 910814 & 21 Meetings W/Nrc

ML20091D589
Person / Time
Site:	Davis Besse
Issue date:	10/15/1991
From:	Shelton D CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1990, TAC-80507, TAC-M80507, NUDOCS 9110250108
Download: ML20091D589 (4)

Text

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pC h w CENTERDOR ENERGY conned c. shdon 300 Maesen Avenue Vce PreWent.Nudear Toledo, OH 436520001 DavisBesse (419)249 2300 Docket Number 50-346 License Fumber NPS-3 Serial Number 1990 October 15. 1991 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C.

20555 Subject License Amendment Request to Revise Technical Specification 5.3.1, Fnel Assemblies: Additional Information Gentlemen:

In anticipation of the need to conduct fuel repair activities during the Davis-Besse Nuclear Power Station (DBNPS) Seventh Refueling Outage (7RFO), Toledo Edison submitted a License Amendment P quest (LAR) to revise the Fuel Assemtly (FA) description in Technical Specification S.3.1 (reference letter Serial Number 1924 dated May 31, 1991).

In subsequent meetings with the NRC staff on August 14 and 21, 1991, Toledo Edison agreed to provide supplemental information relative to the LAR.

A follovup letter (reference letter Serst,' Number 1976 dated August 29, 1991) provided the supplemental informr*,lon.

This letter provides additional information as requested by the NRC Staff in phorn calls earlier this month.

As a result of the FA inspe.tlon and repair activities described belov, Toledo Edison is pleased to have met its objective of beginning the upcoming Cycle 8 with no known fuel defects.

Ultrasonic Testing (UT) was performed on all FAs intended to be reinserted for Cycle 8.

Eleven FAs which were to be discharged, but which vere potertial substitute candidates, vere also tested.

"ive FAs scheduled for reinsertion vere found to have one defective fuel pin each. Three of these five FAs are from Batch 8 (initially inserted in Cycle 6).

The other two FAs are from Batch 9 (initially inserted in Cycle 7).

The Batch 9 FAs have design features which allow defective pin replacement. The Batch 8 FAs do not have those features.

By inserting eleven FAs which vere originally intended to be discharged, and shuffling the core, the three Batch 8 FAs and one of the Batch 9 FAs were replaced.

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License Nurber NPF-3 Serial Number 1990 Page 2 The remaining Batch 9 FA had a defective fuel pin in a location adjacent to a control rod guide tube. This FA vas reconstituted by removing the upper end fitting, extracting the defective fuel pin, moving an adjacent fuel pin into the location vacated by the defective fuel pin, inserting a solid stainless steel (SS) filler rod into the location vacated by O good pin, and then replacing the upper end fitting. The attached Figure 1 shows the location of the SS filler rod lo the FA and the location of the FA in Cycle 8.

The resulting configuration has the SS pin surrounded by heated rods (i.e., there are no adjacent cold valls).

As discussed in the above-mentioned previous meetings with the NRC Staff, this FA configuration does not require any critical heat flux (CHF) penalties. The channels with the SS pin and surrounding fuel pins are not the lead channels for '>over generation in this FA.

The minimum thermal margin for this FA vill be greater than 5 percent relative to the lead power generation FAs in the core.

The cycle-specific vendor analyses to support the Cycle 8 redesign are underway.

Preliminary results show that the existing Reload Report conclusions vill remain bounding. The cycle-specific analyses vill further verify that acceptable safety margins are maintained.

Conformance to existing design criteria and safety analysis limits will be confirmed. The attached Figure 2 shows the core r.ap for Cycle 8.

The failure mechanism for the five defective fuel pins is not presently known. Grid fretting is the likely failure cause for the three Br.tch 8 FAs.

Based on visual observation, grid fretting did not appear to be the cause of failurc of the defective rod which was pulled from the reconstituted FA.

Any follovup investigation of fuel defect causes vill be controlled under the DBNPS fuel integrity program.

The fuel shuffle for Cycle 8 has been completed, and Mode 5 was entered on October 9, 1991. Toledo Edison requests that the NRC process the LAR in an expeditious manner to avoid a delay in the startup of the DBNPS from 7RFO.

If you have any further questions regarding the amendment request, please contact Mr. Robert V.

Schrauder, Manager - Nuclear Licensing, at (419) 249-2366.

Very tr

yours, gnK MKL/dlm cc:

A. B. Davis, Regional Administrator, NRC Region III J. B. Hopkins, NRC Senior Project Manager V. Levis, DB-1 NRC Senior Resident Inspector J. R. Villiams, Chief of Statf, Ohio Environmental Management Agency, State of Ohio (NRC Liaison)

Utility Radiological Safety Board

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