ML19248C835
| ML19248C835 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/26/1979 |
| From: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| BDW-575-79, NUDOCS 7907050370 | |
| Download: ML19248C835 (7) | |
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I Portland General Electric Company Troian Nuclear Plant P O Box 439 June 26, 1979 Rainter. Oregon 97048 BDW-575-79 Mr. R. H. Engelken, Director Nuclear Regulatory Commissior., Region V 1990 North California Blvd.
Walnut Creek, California 94596
Dear Sir:
SUBJECT:
Immediate Recort of Reportable Occut
.ee This letter is a followup to a report made by Mr. W. S. Orser, Engineering Supervisor, to Mr. M. H. Malmros, NRC Resident Inspector at 9:00 a.m.,
Tuesday, June 26, 1979 concerning a situation identified by the Westinghouse Safety Review Committee (see attached letter) and reported by Westinghouse to the NRC on June 21, 1979 under the provisions of 10CFR21.
High energy line breaks inside containment may result in heatup of the steam generator (S/G) level measurement reference leg.
This will cause the indicated S/G water level exceeding the actual S/G water level resulting in the S/G low-low level reactor trip protection signal being delayed.
In the specific case of a feedwater line rupture inside containment, the S/G low-law trip is the primary protection signal for this accident.
Backup reactor trip protection is available frem S/G Icw level coincident with feed flow - steam flow mismatch, evertemperature AT, high pressurizer pressure, containment pressure and safety injection.
Prior to reactor startup we will change the S/G low-lcw level trip point from 5% to 15%. Additionally, operations persannel will be provided with appro-priate instructions to compensate for containment temperature induced errors in the S/G 1evel indication.
This occurrence will be reported to the Nuclear Regulator Commission as a Licensee Event Report in accordance with our established Technical Specification.
Sincerely,
- 3. D. Withers h48 Plant Superintendent BDW/JCP:na c: LER Pistribution List 79070503b
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