ML20211B297

Discusses How Radiation Status of Secondary Sys Normally Assessed by Spds.Main Steam Line Activity Monitors Added to SPDS to Improve Secondary Sys Activity Monitoring Capability.Color Coding on SPDS Computer Changed as Noted

ML20211B297
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	10/09/1986
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
TAC-51292, NUDOCS 8610170181
Download: ML20211B297 (2)

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m m Bart D Wahors Vce Prescent October 9,1986 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTH: Mr. Steven A. Varga Director, PWR-A Project Directorate No. 3 U.S. Nuclear Regulatory Commission Washington DC 20555

Dear Sir:

Safety Parameter Display System (SPDS)_

Our letter of July 19, 1985 provided a response to the NRC Safety Evaluation Report request for additional information. One of the items discussed in our letter was how the radiation status of the secondary system is normally assessed try the SPDS. This assessment is made by monitoring Process and Effluent Radiation Monitor (PRM) 10 on the steam generator blowdown systcm.

In the event of a steam generator tube rupture and overfill accident, the emergency procedures direct the steam generator to be isolated. Once the steam generator is isolated, the only method for displaying the activity level in the generator on the SPDS would be to lineup blowdown and obtain a reading on PRM-10. This method may, however, result in the release of unmonitored and untreated liquids. Therefore, to improve the secondary system activity menitoring capability of the SPDS, we intend to add the main steam line activity monitors (PRM-16 A-D) to the SPDS. This action will be completed by July 31, 1987. The steam generator blowdown treatment system is described in Section 10.4.8 of the Updated Trojan Final Safety Analysis Report. PRM-16 is described in Section 11.5.2.2.7 of the Updated Trojan Final Safety Analysis Report.

In November 1985, a human factors review of the SPDS was completed. As a result of that review, the color coding on the computer has been changed.

The color coding now conforms to the standard convention of green (normal),

yellow (caution), red (alarm), and purple (bad data quality).

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W W BOCidCM Mr. Steven A. Varga October 9, 1986 Page 2 We trust this information will resolve the remaining concerns identified in the NRC Safety Evaluation Report.

Sincerely, Bar . Withers 7

Vice President Nuclear c: Mr. John B. Martin

> Regional Administrator, Region V U.S. Nuclear Regulatory Conunission J

Mr. Lynn Frank, Director State-of Oregon Department of Energy i

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