ML19253A483
| ML19253A483 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/13/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Koester G KANSAS GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7909100116 | |
| Download: ML19253A483 (1) | |
Text
[.pn necq '%
UNITED STATES E % #, yj NUCLEAR REGULATORY COMMISSION r,,3%',,}.
J REGION IV d
611 RYAN PLAZ A DRIVE, SUITE 1000
$ 74Q '
c#
ARLINGTON, TE XAS 76012 O
g.. '...
August 13, 1979 In Reply Refer To:
RIV Docket No.
ST'I 50-482/IE Sulletin 79-21 Kansa.3 Gas a Electric Co.
Atto:
- h. Glenn L. Koester Vice President-Operations Post Office Box 208 Wichita, Kansas 67201 Centle,an:
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, f
n 't
~~
Karl
. Seyfri Director
Enclosures:
1.
Listing of IE Bulletins Issued in Last 6 Months cc: w/ enclosures Messrs.
Nicholas A. Petrick, SNUPPS D. T. McPhee, Kan;as City Power and Light Company Gerald Charnoff, Shaw, Pittman, Potts & Trowbridge E. W. Creel, Kansas Gas and Electric Company 933144 P00R OR11hAI 2eoe1oo;;g
UNITED STATES NUCLEAR REGULATORY COM?tISSION OFFICE 6F INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No. 79-21 Date:
August 13, 1979 Page 1 of 2 TEMPEE Q E EFFECTS ON LEVEL MEASUREMENTS Descripnan of Circumstances:
On June 2.
1979, Westinghouse Electric Corporation 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 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, sa fety related liquid level measuring systems utilized on other steam generators and reactor coolant systems could be af fected 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 description of systems that are so employed; Jescription 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 ef fect of post-accident ambient temperatures on the indicated water level to determine any change in indicated level relative to actual water level. This evaluatiou 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 verify that t h e s e t u o i nt s w i l l i n i t i a t3 --"~~7Tm'MN
-~
x -
.~.
w analyses enroughout +he range <
instrumentation, incit. ling acc DUPLICATE DOCUMENT (y
',,3 these setpoints.
Entire document previously entered into system under:
kBoiling water reactors have baen r
)hOhgg g/g }
ANO the NRC to provide similar inform.
No. of pages:
-