ML19290A007
| ML19290A007 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 08/13/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Goodwinc PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 7908280384 | |
| Download: ML19290A007 (1) | |
Text
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UNITED STATES lk g\\
~ ', n NUCLEAR REGULATORY COMMISSION
$ c; cE REGION V o,'?f; gf 1990 N. CALIFORNIA BOULEVARD d.
SUITE 202, WALNUT CREE K PLAZA WALNUT CREE K, CALIFORNI A 94596 August 13, 1979 Docket tto. 50-344 Portland General Electric Company sci
- o. n. Salmon Street Portland, Oregon 97204 Attention:
Mr. Charles Goodwin Assist' ant Vice President Gentlemen:
Enclosed is IE Bulletin 79-21 which requires action by you with regard to your PWR power reactor facility (ies) with an operating license.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely,
/
(
fWW
/. H. Engelken V
lDirector
Enclosures:
1.
IE Bulletin ilo. 79-21 2.
List of IE Bulletins Issued in the Last Six Months cc w/ enclosures:
B. Withers, PGE F. Gaidos, PGE 7908280 M
.i Accession No:
7908090193 SSINS No:
6820 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 13, 1979 IE Bulletin No. 79-21 TEMPERATURE EFFECTS ON LEVEL MEASUREMENTS Description of Circumstances:
On June 22, 1979, Westinghouse Electric Corporation reported, to NRC, a potential substantial safety hazard un. der 10 CFR 21.
The report, Enclosure No.1, addresses the effe.ct of increased containment temperature on the reference leg water column and the resultant effect on the indicated steam generator water level. This' effect would cause the indicated steam generator level to be higher than the actual level and could delay or prevent protection signals and could, also, provide erroneous information during post-accident monitoring.
Enclosure No.1 addresses only a Westinghouse steam generator reference leg water column; however. safety related liquid level measuring systems utilized on other steam gene ators and reactor coolant systems could be affected in a similar manner.
Actions To Be Taken By Licensees:
For all pressurized water power reactor facilities with an operating license:*
1.
Review the liquid level measuring systems within containment to determine if the signals are used to initiate safety actions or are used to provide post-accident monitoring information.
Provide a description of systems that are so employed; a description of the type of reference leg shall be included, i.e., open column or sealed reference leg.
2.
On those systems described in Item 1 above, evaluate the effect of post-accident ambient temperatures on the indicated water level to determine any change in indicated level relative to actual water level. This evaluation must include other sources of error including the effects of varying fluid pressure and flashing of reference leg to steam on the water level measurements.
The results of this evaluation should be presented in a tabular form similar to Tables 1 and 2 of Enclosure 1.
3.
Review all safety and control setpoi that the setpoints will initiate the 2043 2,43 analyses throughout the range of amb DUPLICATE DOCUMENT instrumentation, including accident these setpoints.
Entire document previously entered into system under:
- Boiling water reactors have been reques ANO NRC to provide similar information.
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