ML19207C188
| ML19207C188 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 08/13/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Eric Turner HOUSTON LIGHTING & POWER CO. |
| References | |
| NUDOCS 7909100115 | |
| Download: ML19207C188 (1) | |
Text
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,p e r amh, UNIT ED STATES S %,
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NUCLEAR REGULATORY COMMISSION a
7, Y, k 'h d /' [
'. C REGION IV o,
Y 611 HYAN PL AZA DRIVE, SUITE 1000
[
AR LINGTON, T E X AS 76012 August 13, 1979 In Reply Re f er To :
RIV Docket Nos. 30-u93/IE Bulletin 79-21 50-499/IE Bulletin 79-21 Houston Li;;n;ing & Power Ccapany ATTN:
't. E. A. Turner, Vice President Power Plant Construction and Technical Services Post Office Sox 1700 Houston, Texas 77001 Gentleten:
The enclosed IE Bulletin 79-21 is forwarded to you for information.
No written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, 9
/
/
./
C /
arlV.Seyfrit[
Director
Enclosures:
1.
Listing of IE Bulletins Issued in Last 6 Months qg]
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No. 79-21 Date: August 13, 1979 Page 1 of 2 TEMPER.C 2E EFFECTS ON LEVEL MEASUREMENTS Description of Circumstances:
On June 22, 1979, Westinghouse Electric Corporauon reported to NRC a potential substantial safety hazard under 10 CFR 21.
The report, Enclosure No.
1, addresses the effect of increased containment temperature on fhe 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 Westingbouse steam generator reference leg water column; however, safety related liquid level measuring systems utilized on other steam generators 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 licase:*
1.
Review the liquid levei 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 watet 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 measure-ments. 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 signals to seri'i that the setpoints will initiate the wipag-twM-Q analyses throughout the range of a: p-
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instrumentation, including accident dDUPLICATE DOCUMENT these setpoints.
I Entire document previously antered q
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