ML20210V194

Informs of Results of RCS Thermal Expansion Monitoring Performed During Wk of 860902.Measurements Acceptable.Data Will Be Taken When RCS Temp Reaches 340 F,In Lieu of Holding Temp at 340 F for Analysis & Evaluation

ML20210V194
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	09/25/1986
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
TAC-3399, TAC-42502, TAC-42503, TAC-61405, TAC-61523, TAC-64233, TAC-65291, TAC-6596, TAC-6663, TAC-7329, TAC-7721, NUDOCS 8610100585
Download: ML20210V194 (1)

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s.m Bart D. Withers Vce Presdent September 25, 1986 4

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Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. John B. Martin Regional Administrator, Region V 1450 Maria Lane, Suite 210 Creekside Oaks Office Park U.S. Nuclear Regulatory Commission Walnut Creek CA 94596-5368

Dear Mr. Martin:

TROJAN NUCLEAR PLANT Reactor Coolant System Thermal Expansion Monitoring On Jcly 22, 1986, we forwarded the Reactor Coolant System (RCS) Thermal Expansion Long-Term Monitoring test procedure (Temporary Plant Test 175, Rev. 0).

In accordance with Section 10.3 of that test procedure, periodic reports of monitoring program results are to be filed with your office.

During the week of September 2, 1986, a Plant cooldown and heatup were performed and the contraction and expansion of the RCS were monitored. The monitoring program measurements were evaluated and determined to bo acceptable.

1 During Plant heatup and cooldown, the test procedure calls for a hold at an intermediate RCS temperature of 340*F for data taking and evaluation. As discussed with Mr. J. Crews of your staff, the 340*F hold point is not considered to be necessary for future measurements. Three successive Plant heatups and two cooldowns have demonstrated the RCS is expanding and contracting as expected.

In lieu of holding the temperature at 340*F, data will be taken when the RCS temperature reaches 340*F, but with the heatup or cooldown still in progress, to demonstrate that movement of the reactor coolant system piping is being allowed by the steam generator snubbers.

Sincer61y, Bart D. Withers Vice President Nuclear c:

Mr. Steven A. Varga Director, PWR-A h01 85 860925 Project Directorate No. 3 P

CK 05000344 PDR Mr. Lynn Frank, Direct.or State of Oregon Department of Energy 121 S W Satmon Steet. Fort:and, Oregon 97204

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