ML19256B757
| ML19256B757 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/13/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 7908280322 | |
| Download: ML19256B757 (1) | |
Text
&
sd n
+f o,Io v
UNITED STATES 8 y >.,(
NUCLEAR REGULATORY COMMISSION 5 -? ' '% ( j
/
REGION I
%, ' N J [. C S,4 h
.[
631 PARK AVENUE
,o" KING OF PRUSSIA, ^*NNSY LVANIA 19406 Docket Nos. 50-277 50-278 AUS 13 in)
Philadelphia Electric Company ATTN:
Mr. S. L. Daltroff Vice President Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 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.
Sincerely, fih l N.
Boyce H. Grier Director
Enclosures:
1.
List of IE Bulletins Issued in the Last 6 Months cc w/encls:
W. T. Ullrich, Station Superintendent Troy B. Conner, Jr., Esquire Eugene J. Bradley, Esquire Raymond L. Hovis, Esquire Warren Rich, Esquire 7908280322
ENCLOSURE 1 UNITED STATES NUCLEAR REGULATORY COMMILSION 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 Circumstances:
On June 22, 1979, Westinghouse Electric Corporation reported, to NRC, a potential 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 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 desci ption 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 ac+1al water level.
This evaluation must include other sources of error ~
uding the effects of varying fluid pressure and flashing of referencs leg to stear., 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 Attachment 1.
DUPLICATE DOCUMENT
- 8 oiling water reactors have been r Entire document previously NRC to provide similar information.
entered into system under:
Pdh
/
ANO No. of pages:
/M