ML20134J284
| ML20134J284 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/21/1985 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Thompson H Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20134J287 | List: |
| References | |
| 85-607, NUDOCS 8508290234 | |
| Download: ML20134J284 (3) | |
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VIMOINIA ELECTHIC AND POWER COMPANY RIcitwoxn,VtuoxNrA const w.L.srsw m vice r==. ion =1 woc m m o
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August 21, 1985 Mr. Harold R. Denton, Director Serial No.85-607 Office of Nuclear Regulation NAPS /JHL Attn:
Mr. H. L. Thompson, Jr., Director Docket No. 50-339 l
Division of Licensing License No. NPF-7 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 CONFIRMATION OF COMPLETION OF LICENSE CONDITION 2.C(18)
North Anna Unit No. 2 license condition 2.C(18) requires that no later than five years from the date of issuance of the license, VEPCO demonstrate to the satisfaction of the Commission that its examination techniques provide a reliable means of detection and evaluation of individual reactor vessel nozzle clad cracks should they grow larger than the acceptance standards contained in ASME Section XI.
VEPCO has performed an inservice inspection of the reactor vessel nozzles.
The examination was performed as required by the Technical Specifications, ASME Section XI, 1974 Edition, 1975 Summer Addenda, and Regulatory Guide 1.150, using the Westinghouse remotely operated reactor vessel inservice inspection tool.
A description of the inservice inspection that was performed and a summary report of the examination results is included in the attachment (refer to the Reactor Vessel Inservice Inspection Program). The examination results did not indicate any significant degradation.
Should you require more detailed information, the entire report is maintained on file at North Anna Power Station and at the corporate office.
VEPCO believes that the completion of the inservice inspection for the reactor vessel nozzles completes the requirements of License Condition 2.C(18).
If you should require further information, please contact us.
Vqrytruly)yours, o
z.' e b Attachment 8508290234 850821 DR ADOCK 05000339 PDR
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,,3 VigoINIA Ex.scraic Amo powan CourawY T Mr. Harold R. Denton Page 2 cc: -Dr. J. Nelson Grace Regional Administrator Region II Mr. Edward J. Butcher, Acting Chief Operating Reactors Branch No. 3 Division of Licensing Mr. M. W. Branch NRC Resident Inspector North Anna Power Station
9 ATTACHMENT TO VEPC0 LETTER SERIAL NO.85-607 I
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