ML19209B094
| ML19209B094 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 08/13/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| References | |
| NUDOCS 7910090160 | |
| Download: ML19209B094 (1) | |
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NUCLEAR REGULATORY COMMISSION
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GLEN ELLYN, ILLINOIS 60137 AUE13 59 Docket No. 50-440 Docket No. 50-441 The Cleveland Electric Illuminating Company AITN:
Mr. Dalwyn R. Davidson Vice President - Engineering P. O. Box 5000 Cleveland, OH 44101 Gentlemen:
The enclosed IE Bulletin No. 79-21 is forwarded to you for information.
No written response is required.
If you desire additional information reg.rding this matter, please contact this office.
Sincerely,
/
James G. Keppler Director
Enclosures:
1.
List of IE Bulletins Issued in the Last 6 Months cc w/encls:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Harold W. Kohn, Power Siting Commission Mr. Daniel D. Wilt, Attorney 1115 324 yetoo9e
Accession No:
7908090193 SSINS No:
6820 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 13, 1979 IE Bulletin No. 79-21 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, Enclosure No. 1, addresses the effect of increased containment temperature on the reference leg water column and the resuitant 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 signais and could, also, provide erroneous information during post-accident monitoring.
Enclosure No. I addresses only a Westinghouse steam generator refertace 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 description of systems that are sc 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 temperatu.es 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 measurements.
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 the setpoints will initiate the action required by the plant safety analyses throughout the range of amb' instrumentation, including accident these setpoints.
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" Boiling water reactors have been reques into system under:
NRC to provide similar information.
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June 22,1979 NS-TPA-2104 Mr. Victor Stello Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Comission
. East West Towers Building 4350 East Wes.t Highway Bethesda, Maryland 20014
Dear Mr. Stello:
Suoject:
Steam Generator Water Level This is to confirm my telephone conversation of June 21, 1979 with Mr.
Norman C. Moseley, Director, Division of Reactor Operation and Inscec-tion and Mr. Samuel E. Bryan, Assistant Director for Field Coordinetion.
In that conversation, I reported that Westinghouse had informed its utility customars of corrections that should be applied to indicated steam generator water level and reconmended that they incorporate those ccrrecticns in the steam generator low water level protection system
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setpoints and emergency operating procedures for operating plants as appropriate.
High energy line breaks inside containment can result in heatup of the steam generator level measurement reference leg.
Increased reference 1eg water column temperature will result in a decrease of the water column density with a consequent apparent increase in the indicated steam generator water level (i.e., apparent level exceeding actual level). This potential level bias could result in delayed protection signals (reactor trip and auxiliary feedwater initiation) which are based on low-low steam generator water level.
In the case of a feedline rupture, this adyt:rse environment could be present and could delay or prevent the primary signal arising from declining steam generator water level (low-low steam generator level).
The following is a list of backup signals available in those Westinghouse plants which take credit in their Final Safety Analysis Reports for steam generator water level trip with an adverse containment environment:
overtemperature delta T; high
' pressurizer pressure; containment pressure and safety injection. For other high energy line breaks which bias to tiie steam generator water 1 level does not provide the primary DUPLICATE DOCUMENT would not interfere with needed pro Entire document previously entered into system under:
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