ML19269D193
| ML19269D193 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 02/27/1979 |
| From: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7903070249 | |
| Download: ML19269D193 (5) | |
Text
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Portland Geneml Electric Company
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February 27, 1979 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTh:
Mr. A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
Our letter of December 23, 1977, in response to your requests of October 4, 1977 and October 27, 1977 regarding fracture toughness and potential for lamellar tearing of steam generator and reactor coolant pump support materials, stated that we would provide additional information in response to NRC Request Number 4 at a later date.
Our supplementary response is as follows:
NRC Request Number 4.
Specify the minimum operating temperature for the supports and describe the extent to which material tempera-tures have been measured at various points on the supports during operation of this Plant.
PGE Response. The attached table shows the surface temperatures measured on supports for Steam Generators A and D at both upper and lower positions on the supports.
Surface temperatures for the supports for Reactor Coolant Pumps A and D were also measured at upper and lower positions and are shown on the attached table.
These temperatures were measured under hot conditions with the Plant at normal operating temperature (>550 F) and with the Plant in refueling shutdown conditions, Operational Modes 2 and 6, respectively.
In addition, attached is a copy of Detail 1 from Engineering Drawing C-373 showing the locations at which the surface temperatures were measured on the steam generator supports.
Also attached is a figure showing Detail 1 of Engineering Drawing C-377 indicating the point.s where the surface temperatures were measured on the reactor coolant pump supports. Complete drawings of C-373 and C-377 were provided with our response of December 23, 1977. Although the temperatures were measured on only two reactor coolant pump supports and two steam generator supports, it is felt that these were the most representative supports and would provide the best range of measurable values.
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7003070 At/7
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Portland Genem! ElectricCompany Mr. A. Schwencer February 27, 1979 Page 2 This inforniation completes our action on your letters of October 4 and October 27, 1977. As be'. ore, we have forwarded three signed and 40 copies of this letter for your us2.
If you have any questions, please do not hesitate to contact me.
Sincerely, Qk
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<H C. Goodwin, Jr.
Assistant Vice President Thercial Plant Operation and Maintenance CG/CAZ/4gah7A12 Attachments c:
Dr. W. Kelly Woods, Acting Director State of Oregon Department of Energy
STEAM GENERATOR SUPPORTS POINT 110T COLD A
1 153*F 87*F 2
92 F 79*F D
1 162 F 84*F 2
85 F 77*F REACTOR COOLANT PUMP SUPPORTS POINT liOT COLD A
3 151*F 85 F 4
92 F 80 F D
3 143 F 82*F 4
82 F 72 F
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