ML20199B502

Forwards Temporary Plant Test TPT-166, Reactor Coolant Thermal Expansion Test,Summary of Data & Predictive Curves, Heatup of 860608-10, Per .Future Monitoring Program Will Be Documented by 861001

ML20199B502
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/13/1986
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:	Varga S Office of Nuclear Reactor Regulation
Shared Package
ML20199B507	List: ML20199B502 ML20199B510
References
TAC-61405, NUDOCS 8606170164
Download: ML20199B502 (2)

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But D Wohers Vce Presdmt June 13, 1986 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN: Mr. Steven A. Varga Director, PWR-A Project Directorate No. 3 U.S. Nuclear Regulatory Commission Washington DC 20555

Dear Sir:

Certified Results of the RCS Thermal Expansion Monitoring Program Per your letter of June 5,1986, attached are the predictive curves from the RCS heatup monitoring program. The actual data points from the heatup are plotted relative to the predictive curves. Although the piping movement was consistently as predicted, there were several loca-tions where shim adjustments were required and the respective curves are so annotated. All other locations met acceptance criteria and are hereby certified acceptable.

The RCS heatup began approximately 0600 on June 8, 1986 and the first temperature plateau (220 i10*F) was reached at approximately 0930. The measurement data from the first plateau were determined to be acceptable and Plant heatup continued at 1500. The second temperature plateau (340 110*F) was reached at 1930 and the data measurements were taken and approved for further heatup at 0030, June 9, 1986. The temperature was held at this point while repairs were made to a steam generator level transmitter. The third temperature plateau (460 110*F) was reached at approximately 2300 on June 9, 1986. The data from this plateau were evaluated as acceptable at 0112 on June 10, 1986. The final temperature plateau (557 110*F) was reached at 0530 on June 10, 1986 and the data measurements were completed. The Plant was subsequently cooled down to allow shim adjustments to be made.

During the next heatup, gap measurements will be taken at 340 110*F at the RCS hot leg whip restraints, the steam generator lower seismic sup-port ring back bumpers, and the upper steam generator seismic support ring. At 557 10*F, gap measurements will be made at all locations where shim adjustments were made. The final certified predictive curves for these locations will be forwarded to you following the heatup. Addi-tionally, the installed monitoring instrumentation at the hot les pipe whip restraints and upper steam generator coismic support ring (ie, which verify snubber movement) will be monitored during the heatup.

0606170164 g h344 DR ADOCK PDR pf e sw nmen st emno om m

i Peruand GeneralBechicCompany Mr. Steven A. Varga June 13, 1986 Page 2 During future heatups, monitoring of snubber movement and RCS hot les pipe Whip restraint gaps will be performed utilizing the instrumentation installed in these locations. As indicated on the attached predictive curves, the physical measurements taken during the last heatup correlated very well with the instrumentation values. This future monitoring pro-gram will be documented in a Plant procedure and will include acceptance criteria, actions to be taken if outside the acceptance criteria and com-pensatory action if the installed instrumentation fails. This procedure will be in place by October 1, 1986 or prior to the first heatup, if sooner, af ter return to power operations.

Based on discussions with your staff concerning the nondestructive examination of the steam generator hot leg elbows, we committed to an increased frequency of surveillances to detect possible RCS leakage. The Containment sump inventory and Containment atmosphere particulate radio-activity monitor will be recorded at least twice per shift during the next cycle. This additional survalliance will be terminated following nondestructive examination of these elbows in 1987.

Sincerely, e ,

Bart D. Withers Vice President Nuclear Attachments c: Mr. John B. Martin Regionci Administrator, Region V U.S. Nuclear Regulatory Commiosion

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