ML19098B470
| ML19098B470 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/16/1976 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | Reid R, Rusche B Office of Nuclear Reactor Regulation |
| References | |
| Serial No. 737 | |
| Download: ML19098B470 (2) | |
Text
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Mr. Benard C. Rusche Director of Nuclear Reactor Reg U.S. Nuclear Regulatory Commissio Washington, D. C.
20555 Attn:
Mr. Robert W. Reid, Chief Operating Reactors Branch 4
Dear Mr. Rusche:
Serial No. 737 PO&M/JTB:clw Docket Nos.(5b-28f>
50-28 License Nos. DPR-32 DPR-37 Representatives of the Regulatory Staff and Vepco met on September 17, 1975 to discuss the fracture toughness requirements of the Unit No. 1 reactor vessel.
In the notes of conference dated September 26, 1975 issued by your office, we wish to clarify certain statements reported in the NRG summary.
The notes of conference indicate that "Vepco also agreed to perform a volumetric inspection of the beltline welds after 3~ years of operation rather than at the end of 10 years as presently called for in the technical specifi-cations."
The intent of the statements made at the meeting was that the re-mote inspection tool for performing inspections of internal reactor vessel welds would be used during Refueling Outage No. 3 for Unit No. 1 tentatively scheduled for October 15, 1976.
Since we plan to have the remote inspection tool at the site during the outage, it was indicated that we could perform the normal inspections conducted after ten (10) years during this time.
This in-spection would require that the lower reactor internals be removed.
The purpose of the meeting was to discuss the results of the material sur-veillance capsule analysis program and to mutually determine the appropriate additional actions which may be required.
However, before making a commitment to move up the 10 year inspection of the reactor beltline welds, we believe that any inspection activity should be integrated with the overall program of action which may be necessary to address the concerns of Appendix G, 10 CFR SO, and those of the Regulatory Staff.
As agreed to with the Staff, we shall await the results of the generic discussions which the Staff has scheduled before pre-maturely instituting a program.
Therefore, before making a commitment r_egarding the inspection of reactor vessel welds, agreement to a complete program, if necessary, should be made to assure an orderly and meaningful resolution of any items which may be identified as a concern.
578
e VIRGINIA ELECTRIC AND POWER COMPANY TO We shall await the outcome of the proceeding with any additional action.
discussions are required.
e Mr. Benard C. Rusche Page 2 Commission's.generic discussions.before Please advise us as to when further Very truly yours, 7{).ll?.vffe~~
C. M. Stallings Vice President-Power Supply and Production Operations