ML19208B979
| ML19208B979 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/13/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Herbein J METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7909240250 | |
| Download: ML19208B979 (1) | |
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UNITED STATES
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"- r AUG 13 B13 Docket Nos. 50-289 50-320 Metropolitan Edison Company ATTN:
Mr. J. G. Herbein Vice President P. O. Box 542 Reading, Pennsylvania 19640 Gentlemen:
The enclosed 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.
Sincesaly, 1
NJ Boyce H. Grier Director
Enclosures:
1.
List of IE Bulletins Issued in the Last 6 Months cc w/encls:
E. G. Wallace, Licensing Manager J. J. Barton, Prcject Manager R. C. Arnold, Vice President - Generation L. L. Lawyer, Manager - Generation Operations G. P. Miller, Manager - Generating Station - Nuclear J. L. Seelinger, Unit 1 Superintendent W. E. Potts, Unit 1 Superintendent - Technical Support J. 8. Logan, Unit 2 Superintendent G. A. Kunder, Unit 2 Superintendent - Technical Support I. R. Finfrock, Jr.
Mr. R. Conrad G. F. Trowbridge, Esquire Miss Mary V. Southard, Chairman, Citizens for a Saf' Environment 799 009 7909240 ^a g o Ch
ENCLOSURE 1 UNITED STATES NUCLEAP REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No. 79-21 Date:
August 13, 1979 Page 1 of 2 TEMPERATURE EFFECTS ON LEVEL MEASUREMENTS Description of Cf ecumstances:
On June 22, 1979, Westinghouse Electric Corporation reported, to NRC, a poter.t.jal substantial. safety hazard under 10 CFR 21.
The report, Attachment 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.
Attachment No. 1 addresses only a Westinghouse 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 ;wessurized water power reactor facilities with _n 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-ac-cident 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 measure-ments. The results of this evaluation shculd be presented in a tabular form similar to Tables 1 and 2 of Attachment 1.
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DUPLICATE DOCUMENT
^ Boiling water reactors have been req Entire document previously entered NRC to provide similar information.
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No. of pages:
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