ML19209B105
| ML19209B105 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 08/13/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| References | |
| NUDOCS 7910090177 | |
| Download: ML19209B105 (1) | |
Text
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sa nscuq'o UNITED STATES 8"
NUCLEAR REGULATORY COMMISSION
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GLEN ELLYN,ILLINols 60137 Docket No. 50-409 gy 3 g Dairyland Power Cooperative ATTN:
Mr. F. W. Linder General Manager 2615 East Avenue - South La Crosse, WI 54601 Gentlemen:
The enclosed IE Bulletin No. 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, M O 12 amesG.Keppler/g Director s
Enclosures:
1.
List of IE Bulletins Issued in the Last 6 Months cc w/encls:
Mr. R. E. Shir.shak, Plant Superintendent Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Anthony Roisman, Esq.,
Attorney a
1115 351 I
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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 EFFFCTS 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 npor1, 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, 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:
F,or 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; 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 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 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 ambient temperatures encoun instrumentation, including accident these setpoints.
DUPLICATE DOCUMENT ntire document previously entered i' Boiling water reactors have been reque r
7 NRC to provide similar information.
nto syster under:
ANO 1115 352 C
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June 22,1979 KS-TMA-d O4 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:
Subject:
Steam Generator Water Level This is to confirn my telephone conversation of Ju e 21, 1979 with Mr.
Norman C. Moseley, Director, Division of Reactor 0 '. ration and Inscec-tion and Mr. Samuel E. Bryan, Assistant Director for Field Coordination.
In that conversation, I reported that Westinghouse had informed its utility customers of corrections that should be applied to indicated steam generator water level and recomended that they incorporate those ccrrectiens in the steam generatcr low water level protection system 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 leg 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 adverse 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 adverso containment environment:
overtemperature delta T; high
~ pressurirer pressure; containment p safety injection.
For
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other high energy line breaks which bias to the steam generator water le DUPLICATE DOCUMENT 1evel does not provide the primary t would not interfere with needed prot Entire docum intosystem$nof usly entered hhh
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