ML19290A012
| ML19290A012 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Vogtle  |
| Issue date: | 08/13/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | John Miller GEORGIA POWER CO. |
| References | |
| NUDOCS 7908280462 | |
| Download: ML19290A012 (2) | |
Text
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'o UNITED STATES l'
.,, 7 [,,g NUCLEAR REGULATO9Y COMMt.CSIDN REGION ll
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r 101 MARIETT A ST., N.W., SUITE 3109 f y
AT LANTA, GEORGI A 30303
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j In Reply Refer To:
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50-321, 50-366 50-h2h, 50-425 Georgia Power Conpany Attn:
J. H. Miller, Jr.
Executive Vice President 270 Peachtree Street, N. W.
Atlanta, Georgia 30303 Gentlemen:
The enclosed Bulletin 79-21 is forwarded to you for infomation.
No written response is required. If yoi. desire additional infomation regarding this matter, please contact this office.
Sincerely, C4 James P. O'Reilly Director
Enclosures:
1.
IE Bulletin No. 79-21 v/ enc 1.
2.
List of IE Bulletins Issued in the Last 614onths 2043 246 7908280 y(p A
. Georgia Power Company cc w/ encl:
M. Manry, Plant Manager Post Office Box 442 Baxley, Georgia 31513 C. E. Belflower Site QA Supervisor Post Office Box 442 Baxley, Georgia 31513 K. M. Gillespie Construction Project Manager Post Office Box 282 Waynesboro, Georgia 30830 E. D. Groover QA Site Supervisor Post Office Box 282 Waynesboro, Georgia 30830 2043 247
Accession No:
7908090193 SSINS No: 6820 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND EhTORCEMEhT WASHINGTON, D.C.
20555 August 13, 1979 IE Bulletin No. 79-21 TEMPERATURE EFFECTS ON LEVEL MEASUREMENTS Description of Circumstances:
NRC, a potential Westinghouse Electric Corporation reported, to On June 22, 1979, substantial safety hazard under 10 CFR 21.
The report, Enclosure No. 1, addresses the effect of increased co ltant effect on the temperature on the reference leg water column and the resuThis effect would indicated steam generator water level. steam generator level information during d could delay or prevent protection signals and could, also, provide erroneousEnclo liquid level generator reference leg water column; however, safety related post-accident monitoring.
coolant systems measuring systems utilized on other steam generators and reactor could be affected in a similar manner.
Actions To Be Taken By Licensees:
For all pressurized water power reactor facilities with an operatin Review the liquid level measuring systems within containmen ide if the signals are used to initiate safety actions or are used to pro 1.
post-accident monitoring information.that are so employed; leg shall be included, i.e., open column or sealed reference leg.
id On those systems described in Item 1 above, evaluate the effe change ambient temperatures on the indicated water level to determine any 2.
This evaluation must in indicated level relative to actual water level. incl fluid level measuremen pressure and flashing of reference leg to steam i ilar to Tables 1 and 2 of Enclosure 1.
'fy 3
Review all safety and con that the setpoints will i DUPLICATE DOCUMEN7 analyses throughout the r
/h43 248 instrumentation, includin Entire document previously these setpoints.
entered into system under:
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- Boiling water reactors have
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NRC to provide similar info No.. of pages:
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