ML20078S259

Forwards Plant Specific Fracture Mechanics Assessment as Attachment to to Nrc.Info Contained in Encl Rept Believed to Be True & Reliable

ML20078S259
Person / Time
Site:	Quad Cities
Issue date:	02/17/1995
From:	Schrage J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20078S260	List: ML20078S259 ML20078S284
References
RTR-NUREG-0619, RTR-NUREG-619 NUDOCS 9502240061
Download: ML20078S259 (3)

Text

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[ N Commonwealth Edison

) 1400 Opus Place (C J Downers Grove, Illinois 60515

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February 17,1995 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Quad Cities Station Units 1 and 2 NUREG-0619 Feedwater Nozzle Inspections Additional Information NRC Docket Nos. 50-254 and 59-265

Reference:

J. Schrage to USNRC letter dated December 14,194 In the referenced letter, Comed requested NRC Staff review and approval to use an enhanced, automated UT technique to examine the feedwater nozzles during the upcoming refuel outages at Quad Cities Station (QlRIS and Q2R13), in lieu of the PT required by Section 4.3.2, Table 2 of NUREG-0619. The use of the enhanced, automated UT from the nozzle outer surface,instead of the PT from the inside of the reactor vessel, will avoid significant radiation exposure associated with the removal of the feedwater spargers and performance of the required PT, As part of the referenced letter, Comed provided the technical basis and justification for the use of the enhanced, automated UT technique to examine the feedwater nozzles. This technical justification included a commitment to complete a plant specific fracture mechanics assessment to verify that an assumed crack of 0.25" deep, which is the current conservative detection limit of an automated UT system, would not grow to exceed the allowable crack depth for the remainder of life for both units.

This letter transmits this plant specific fracture mechanics assessment as an attachment to the letter.

To the best of my knowledge and belief, the statements contained herein are true and correct. In some respects, these ste:ements are not based on my personal knowledge but obtained information furnished by other Commonwealth Edison employees and consultants. Such information has been reviewed in accordance with Company practices and I believe it to be reliable.

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U.S. NRC February 17,1995 We trust that the information is satisfactory; however, should you have any questions or desire any additional information on this issue, please do not hesitate to contact this office.

Sincerely, v>

John L. Sch(rage k

Nuclear Licensing Administrator i

Attachment I cc: J. Martin, Regional Administrator - Rill l l

C. Miller, Senior Resident Inspector - Quad Cities R. Pulsifer, Project Manager - NRR Office of Nuclear Facility Safety - IDNS l

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ATTACIIMENT FLAW TOLERANCE EVALUATION QUAD CITIES STATION UNIT I AND UNIT 2 FEEDWATER NOZ7LES i

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