RS-03-088, Clarification of Commitment Regarding Request for Relief

Clarification of Commitment Regarding Request for Relief

ML031340527
Person / Time
Site:	Dresden
Issue date:	04/30/2003
From:	Simpson P Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-03-088
Download: ML031340527 (2)

Text

Exelkrn.

Exelon Generation www.exeloncorp.corn Nuclear 4300 Winfield Road Warrenville, IL 60555 RS-03-088 April 30, 2003 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 2 Facility Operating License No. DPR-19 NRC Docket No. 50-237

Subject:

Clarification of Commitment Regarding Request for Relief

Reference:

Letter from K. R. Jury (Exelon Generation Company, LLC) to U.S. NRC, "Request for Relief from Certain Requirements of 10 CFR 50.55a(g)(4)(ii)

Regarding Control Rod Drive Housing Welds," dated October 25, 2002 In the referenced letter, Exelon Generation Company, LLC (Exelon) requested temporary relief for Dresden Nuclear Power Station (DNPS), Unit 2 from certain requirements of 10 CFR 50.55a, "Codes and standards," paragraph (g)(4)(ii) concerning implementation of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 1989 Edition, Section Xl, Examination Category B-O, "Pressure Retaining Welds In Control Rod Housings," for the third inservice inspection interval which ends on September 30, 2003.

In the referenced letter, DNPS committed to examine the Unit 2 control rod drive (CRD) tube-to-tube welds required by ASME Section Xl at the next outage of sufficient duration. The next scheduled opportunity to perform the required examinations is the next Unit 2 refueling outage, which is now scheduled to begin in mid-October 2003, approximately two weeks following the end of the current inspection interval.

In a communication from Mr. L. W. Rossbach of the NRC to Mr. A. R. Haeger of Exelon on March 31, 2003, the NRC requested clarification of our commitment to examine these welds at the next outage of sufficient duration. The examination of the CRD housing welds will require access to an area directly under the reactor vessel inside of the reactor vessel support skirt.

Due to the proximity of the reactor vessel, the plant must be in cold shutdown with reactor vessel temperatures low enough to permit personnel access into this area to perform the inspections. Thus, DNPS will examine these welds at the next outage in which the reactor is expected to be in cold shutdown for at least four days.

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April 30, 2003 U. S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning this letter, please contact Mr. A. R. Haeger at (630) 657-2807.

Respectfully, Patrick R. Simpson

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Manager, Licensing Mid-West Regional Operating Group