ML20202C354

Informs That Remote Monitoring of Electronic Instrumentation Will Be Used to Assure That Steam Generator Snubbers Allow RCS Thermal Movement,Per 860616 Safety Evaluation.Only Remote Monitoring Will Be Repeated During Each Heatup

ML20202C354
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/26/1986
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
TAC-61405, NUDOCS 8607110221
Download: ML20202C354 (2)

Text

- _ _ _ _

w n

-.- Pbetlarici Getietal Electric Coit ,icniy 003 h - " ju t r, Bart D WRhers Vce Presdent Til:. _

June 26, 1986 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 Pursuant to discussions with Mr. Jess Crews of your staff during his recent visit to the Trojan Nuclear Plant, we agreed to provide a detailed descrip-tion of the continuing monitoring program of RCS thermal expansion. Inas-much as the continuing monitoring program has not yet been implemented by a specific procedure, the details cannot be provided at the present time.

This was discuased in a telephone conversation with Jess Crews on June 19, 1986. At that time, we agreed to forward either a detailed description of our continuing monitoring program or a copy of the specific implementing procedure following its development and implementation within 30 days or prior to the next heatup.

In addition, on June 16, 1986, the NRC forwarded a copy of the Safety Evaluation of Inoperable Steam Generator Snubbers cn the Trojan Nuclear Plant Reactor Coolant Loop dated June 19, 1986. This safety evaluation specifically discusses the continutng ronitoring program of RCS thermal expansion by reference to Temporary Plant Test TPT-166. The SER indicates that the specific TPT will be repeated for each subsequent heatup. PGE considered this approach but determined that it was not practical or necessary in order to assure that the steam generator snubbers operate as designed to allow thermal movement of the RCS. To satisfy this requirement remote monitoring of the electronic instrumentation will be used.

3607110221 860626 PDR ADOCK 05000344 a P PDR I0 121 S W Sa mon Street Porta % Oregon 97204

o \

MMMM Mr. John B. Martin June 26, 1986 Page 2 Therefore, only the remote monitoring of the electronic instrumentation portion of the TPT-166 will be repeated during each heatup. This was agreed to in meetings and discussions with the NRC staff. This clarifica-tion should be made to the statements provided in the SER.

Sincerely, gr Bart D. Withers Vice President Nuclear c: Mr. Steven A. Varga Director, PWR-A Project Directorate No. 3 Mr. Lynn Frank, Director State of Oregon Department of Energy

_ ._ . _ _ , _ . . _ - . _ . . - _ _ _ . - ,