ML20217Q589

Clarifies Two Items in NRC SER & Documents Results of Conference Call W/Nrc Staff on 980428 Re Exam Requirements for part-length Control Rod Drive Mechanism Housing Repair

ML20217Q589
Person / Time
Site:	North Anna
Issue date:	04/29/1998
From:	Saunders R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
98-187A, NUDOCS 9805080211
Download: ML20217Q589 (2)

Text

..O VIRGINI A EE.ECTRIC A NI) POW E H COM i% N Y l Riciiuoso, Vincisia 2326:

April 29, 1998 '

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U.S. Nuclear Regulatory Commission Serial No. 98-187A  ;

Document Control Desk NLOS/ETS:R1 Washington, D.C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 CLARIFICATION OF NRC SER FOR EXAMINATION REQUIREMENTS FOR l PART-LENGTH CONTROL ROD DRIVE MECHANISM HOUSING REPAIR  !

The purpose of this letter is to clarify two items in the NRC SER and to document the results of a conference call with the NRC staff, in a letter dated April 8,1998 (Serial l No.98-187), Virginia Electric and Power Company requested the use of an alternate

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examination technique for the seal welds after the part-length control rod drive mechanism housings were removed and capped. In a letter dated April 20,1998,th9 NRC provided a Safety Evaluation Report (SER) that approved the use of the alternate examination technique. l The staff's SER states that "a final examination of the weld surface using a camera and a VT-2 (visual) examination of the weld and cap for leakage would be performed during the post-outage hydrostatic test." During a subsequent discussion, the NRC staff  ;

clarified that this statement was intended to specify a post-outage " leakage" test rather than a Code-defined hydrostatic test. In addition, the NRC staff agreed that a VT-2 (visual) inspection during the leakage test of the " reactor head area" instead of "the weld and the cap" was acceptable and was intended in the SER.

Based on a telephone conversation with Dr. G. E. Edison and Mr. E. J. Sullivan, Jr. on April 28,1998, the staff confirmed that the inspection requirement to permit a final visual examination of the weld surface using a camera and a VT-2 (visual) inspection of the reactor head area in accordance with IWA-5241(b) during the start-up leakage test of the Reactor Coolant System would provide an acceptable level of quality and safety consistent with the approved relief.  ;

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if you have any questions or require additional information concerning this matter, please contact us.

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Very truly yours, l '

l R. F. Saunders l Vice President - Nuclear Engineering and Services I l Commitments made in this letter:

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1. None cc: U. S. Nuclear Regulatory Commission Region 11 Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 l Atlanta, Georgia 30303 I J

Mr. M. J.' Morgan NRC Senior Resident inspector North Anna Power Station l

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