ML20217Q589
| 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 4
l 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
]
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.
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.
a, Very truly yours, l
l R. F. Saunders Vice President - Nuclear Engineering and Services I
l Commitments made in this letter:
l 1.
None cc:
U. S. Nuclear Regulatory Commission Region 11 Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 J
Mr. M. J.' Morgan NRC Senior Resident inspector North Anna Power Station l
l