ML20043B279
| ML20043B279 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/22/1990 |
| From: | Bevan R Office of Nuclear Reactor Regulation |
| To: | Walt T PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 9005250196 | |
| Download: ML20043B279 (3) | |
Text
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May 22, 1990 l Docket No. 50-344 i
Mr. Thomas D. Walt Acting Vice President, Nuclear
-Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204
Dear Mr. Walt:
SUBJECT:
USE OF B&W STEAM GENERATOR TUBE PLUGS MADE OF ALLOY 690 J-By zietter of April 9,1990, Portland General Electric Company requested approval 3
for the use of B&W steam generator plugs and plug-retaining devices manufactured i
with a nickel-base alloy, ASME designation SB-166 (Alloy 690) in their Trojan nuclear unit.
i The NRC staff has reviewed the request and supporting information and concludes that the use of Alloy 690 as a proposed alternative to the use of Alloy 600, in accordance with the requirements of the ASME Boiler and Pressure Vessel Code, will provide an acceptable level of quality and safety.
Its use is, therefore, acceptable and is authorized under the provisions of 10 CFR 50.55a(a)(3).
Sincerely, Roby Bevan, Project Manager Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION EDecket tile;:M LA NRC & LPDRs RBevan PD5 Reading OGC JZwolinski E. Jordan JLarkins ACRS(10)
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May 22, 1990 Docket No. 50-344 Mr. Thomas D. Walt M
Acting Vice President, Nuclear Portland General Electric Company a
121 S.W. Salmon Street Portland, Oregon 97204
Dear Mr. Walt:
_.I
SUBJECT:
USE OF B&W STEAM GENERATOR TUBE PLUGS MADE OF ALLOY 690
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By letter of April 9,1990, Portland General Electric Company requested approval for the use of B&W steam generator plugs and plug-retaining devices manufactured with a nickel-base alloy, ASME designation SB-166 (Alloy 690) in their Trojan nuclear unit.
The NRC staff has reviewed the request and supporting information and concludes that the use of Alloy 690 as a proposed alternative to the use of Alloy 600, in accordance with the requirements of the ASME Boiler and Pressure Vessel Code, will provide an acceptable level of quality and safety.
Its use is, therefore, acceptable and is authorized under the provisions of 10 CFR 50.55a(a)(3).
L Sincerely, m
Roby Bevan, Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects 5
Office of Nuclear Reactor Regulation cc: See next page i
i.,
. Trojan-Nuclear Plant Mr.-. Thomas D. Walt Portland. General Electric Company-cc:
Senior Resident Inspector U.S. Nuclear Regulatory Commission Trojan Nuclear Plant-Post Office Box-0 Rainier,. Oregon 97048 Mr.' Michael J. Sykes, Chairman Board of County Commissioners Columbia County-St..Helens, Oregon 97501 Mr. David Stewart-Smith.
Oregon Department of Energy-Salem, Oregon 97310 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450' Maria Lane, Suite 210 Walnut Creek, California 94596 (4).
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