ML20052D968
| ML20052D968 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/30/1982 |
| From: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| TAC-11203, NUDOCS 8205070349 | |
| Download: ML20052D968 (2) | |
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April 30, 1982>, M VTTm'\\\\
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Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN:
Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
Westinghouse Dropped Rod Analyses on March 28, 1979 and November 15, 1979, a notification under 10 CFR 50.59 was made by Westinghouse which identified the potential for cer-tain dropped rod events leading to calculated DNB ratios lower than those originally reported to the NRC for certain Westinghouse plants.
Concurrent with the November 15, 1979 notification to the NRC, Westing-house recommended an interim mode of operation to licensees, and in response to this, PCE committed by letter of December 11, 1979 to require for the Trojan Nuclear Plant that if the reactor control sys-tem is in the automatic mode with power level greater than 90 percent rated power, then Bank D control rods will be withdrawn to greater than or equal to 215 steps.
As stated in our letter of December 11, 1979 the procedural changes that implemented this interim operating restriction would remain in offeet until longer term solutions have been developed as part of a report to be submitted to the NRC by Westinghouse.
It is our under-standing that Westinghouse has completed their evaluation and deter-mined that the design bar.is for the safety analysis is met and that plants may return to e' estricted automatic rod control. These con-t clusions were discussed with the Core Performance Branch of the NRC j
in August 1981, and the final report was submitted by Westinghouse to the NRC on January 20, 1982.
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l O 8205070349 820430 PDR ADOCK 05000344 p
PDR 121 S W Sa! mon Set. Podund. Oregon 97204
t Fertland General NiicCoirpany Mr. Robert A. Clark April 30, 1982 Page two Since the interim operating restrictions are no longer necessary, it is our intention to return to unrestricted automatic rod control in this regard commencing with the startup of Cycle 5.
The accept-ability of operation above 90 percent of rated power without the interim restrictions will be verified in the reload safety evaluation for the Trojan Nuclear Plant. We shall proceed with this approach unless notified otherwise by you.
Sincerely, nW-a Bart D. Withers Vice President Nuclear c:
Mr. Lynn Frank, Director State of Oregon Dcpartment of Energy v