ML19253A480
| ML19253A480 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/13/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Weigand J GULF STATES UTILITIES CO. |
| References | |
| NUDOCS 7909100111 | |
| Download: ML19253A480 (1) | |
Text
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NUCLEAR REGULATORY COMMISSION
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August 13, 1979 In Reply Refer To:
RIV Docket Nos.
50-l.53/IE Bulletin 79-21 30-459/IE Bulletin 79-21 Gulf States Utilities Attn:
W. J. G. Weigand General Manager, Nuclear Projects Post Office Box 2931 Beau =ont, Texas 77704 Gentlemen:
The enclosed IE Bulletin 79-21 is forwarded to you for information. No writcen response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
~
SM4!4'
/Karl V. Seyfrit Direci or
/
Enclosures:
1.
Listing of IE Bulletins Issued in Last 6 Months
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7909100
UNITED STATES NUCLEAR REGULATORY COBl?!ISSION OFFICE OF INSPECTION AND ENFORCEMENT WASlflNGTON, D.C.
20555 IE Bulletin No. 79-21 Date:
August 13, 1979 Page 1 of 2 TEMPERATL'RE EFFECTS C'N LEVEL MEASUREMENTS Descripuca of Circumstances:
On June 22, 1979, West.inghouse Electric Corporation reported to NRC a potential substan ual safety hazard under 10 CFR 21.
The report, Enclosure No. 1, addresses the effect 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. I addresses only a Westinghouse steam generator reference leg water column; however, safety related liquid level measuring systems utilized on other steam generators and reactor coclant 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: 1-1.
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 ltem 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 ef fects of varying fluid pressure and flashing of reference leg to steam on the water level measure-meats.
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 setpoints derived from level signale u -"
that the setpoints will initiate t' analyses throughout the range of a.
DUPLICATE DOCUMENT ina t t ucuenta tio n, including acciden these setpoints.
Entire document Previously entered into system under:
- Boiling water reactors have been reque O
ANO the NP,C to provide similar information No. of Pages:
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