ML19291C426
| ML19291C426 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/21/1980 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| 036, 36, NUDOCS 8001240404 | |
| Download: ML19291C426 (2) | |
Text
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Vauorx A liLECTHIC AND Pow n u Con rAxy H acu> town.VanorN E A 1300f31 January 21, 1980 Mr. Harold R.
Denton, Director Serial No. 036 Office of Nucicar Reactor Regulation P0/FHT:scj Attn:
Mr. Albert Schwencer, Chief Docket No. 50-338 Operating Reactors Branch 1 License No. NPF-4 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
North Anna Unit 1 Steam Generator Repairs Acceptability of ASME Code Case N-210 Based on discussions wi*.h members of your staff on December 27, 19 79, (Messrs.
W.
Hazleton and G.
Johnson) we understand that application of ASME Code Case N-210 is acceptable in the exemption from the hydro test requirement for certain repairs performed on North Anna Unit l's steam generators.
The repairs performed consisted of replacement of several three-quarter inch root isolation valves for steam generator level and main steam line flow transmitter sensing lines.
The application of Code Case N-210 was required because of the impracticality of hydrostatically testing these valves.
In each case, the high side of the valve is not isolable from the steam genera-tors.
A hydrostatic test of the valve would involve a hydrostatic test of the steam generators themselves.
Af ter valve replacement, dye penetrant tests confirmed that the repairs were satisfactory and additional visual inservice leakage examinations are scheduled when the plant is returned to temperature and pressure.
Additional basis for acceptability of the application of Code Case N-210 to this repair is contained in Draf t Regulatory Guide, Inservice Inspection Code Case Acceptability ASME Section XI Division 1, dated August, 19 79.
Section C, Recula tory Position, paragraph 1, of the subject Draft Regulatory Guide lists Code Case N-210 as, " acceptable for application in the inservice inspection of components and their supports for water-cooled nuclear power plants".
In light of the foregoing, and as agreed to by Messrs. Hazelton and Johnson, hydrostatic testing of the replacement valves was not performed.
1794 110 80o1240 C
Vinoista EttcTulc AND POWEN Com4Y TU Mr. Ilarold R. Denton 2
If you have any questions or req 2 ire additional in fo rma tion, please contact this office.
Very truly yours,
.! /, '/.,,
,)
C. M.
Stallings Vice President-Power Supply and Production Operations cc:
Mr. James P. O'Reilly 1/ny4 111
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