ML19207B746

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Forwards Draft of IE Bulletin & Cover Ltr That Should Be Dispatched for Action on 790813 to All PWRs W/Ol.Discusses Temp Effects on Level Measurements
ML19207B746
Person / Time
Issue date: 08/09/1979
From: Moseley N
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Engelken R, Grier B, James Keppler, James O'Reilly, Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML19207B741 List:
References
REF-SSINS-6820 NUDOCS 7909050189
Download: ML19207B746 (5)


Text

ENCLOSURE 2

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g August 9,1979 MEMORANDUM FOR:

B. H. Grier, Director, Region I J. P. O'Reilly, Director, Region II J. G. Keppler, Director, Region III K. V. Seyfrit, Director, Region IV R. H. Engelken, Director, Region V FROM-Norman C. Moseley, Director, Division of Reactor Operations Inspection, IE SUEJECT:

IE SULLETIN NO. 79 TEMPERATURE EFFECTS ON LEVEL MEASUREMENTS The subject IE Eulletin should be dispatched for action August 13,1979, to all 4 Rs with an operating license.

The Bullet.in should be sent for information

c EWRs ar.d to facilities with a construction permit.

The text cf the Eulletin and draft letter to licensees are enclosed for this urpose.

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NormanC.Moseley,Directo[,

Division of Reacter Operations Inspection Office of Ins::ection and Enforcement Enclos u,res:

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Draft iransmittal Letter 2.

IE Bulletin No. 79-21 CGNTACT:

H. A. Wilber, IE 49-25150 790905o13?

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(Draft letter tc SWR power reactor facilities with an operating license and

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all power reactor facilities with a construction permit)

IE Bulletin No. 79-21 Addressee:

The enclosed Bulletin 79-21 is forwarded to you for information.

No written response is required.

If you desire additional inform,aticn regarding this atter, please contact this office.

Sincerely, Sicnature (Rigional Director)

Enc 7 0sures:

1.

IE Euiietin No. 79-21 2.

Listing of IE Eulletins Issued in Last 6 Months

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(Draft letter to PWR power reactor facilities with an operating license)

IE Bulletin fio. 79-21 Addressee:

Enclosed is IE Bulletin 79-21 which requires action by you with regard to your PWR pc er reactor facility (ies) with an operating license.

Should you have any questions regarding this Bulletin cr the actions required by you, please contact this office.

Sincerely, Signature (Regional Director)

Enc'esures:

1.

IE Bulletin No. 79-21 2.

List of IE Bulletins Issued in the Last 6 Months o < ". C:

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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.

20555 August 13, 1979 IE Bulletin No. 79-21 TEM 3ERATURE 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 repcrt, Enclosure No. 1, addresses the effect of increased containment ter:e a:Jre on the reference leg water column and the resultant effect on the i.dicated steam generator water level.

This effect wculd cause tne indicated 5 ear generatcr level tc be higher than the actual level anc coulc ceiay or

e.ent :rctection signals and could, also, provice errcneous information during
st-accicent ;cnitoring.

Enclosure Nc. I adcresses only a Westingncese steam gen ratcr reference leg water column; however, safety related liquid level Teasuring systems utilized on other steam generators anc reactor ccolant systems

uld be affected in a similar manner.

Acti:ns Tc Ee Taken By Licensees:

Icr all cressurized water pcwer reactor facilities witn an cperating license:*

1.

Review :ne iicuid level measuring systems witnin containment to cetermine if tne signals are used to initiate safety actions or are used to provide

cs -accicent monitor ng information.

Provide a cascription of systems inat are so employed; 4 description of the type of reference leg shall De included, i.e., cpen column or sealed reference leg.

2.

On those systems described in Item 1 above, evaluate the effect of post-acciden-ambient temperatures on the incicated water level to determine any change in incicated level relative to actual water level.

This evaluation must inclJce other sources of error including the ef fects of varying fluid

essure anc flashinc cf reference leg to steam en the aater level measureme. s e esults of tnis evaluation snculd be prese tec 'n a tabular fctm similar
~icles 1 and 2 cf Er. closure 1.

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E. i-all safety anc centrol setpcints ceri.e: # cm le.<el signais :: veri'y 1^11 ;

se'.;;i.ts Wil' in# tiate the actiCr "e

t y '.ne Dlant safet) i~i ses IP' Lg ;ut tF.e "ange Of a*:ient tem e'ali'es ent untere: ;;. One a;;i e ; le~; era!.'is.

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IE Bulletin No. 79-21 Page 2 of 2 August 13, 1979 If the above reviews and evaluations require a revision of setpoints to ensure safe operation, provide a description of the corrective action and the date the action was ccmpleted.

If any corrective action is temporary, submit a description of the proposed final corrective action and a timetable for implementation.

4.

Review and revise, as necessary, emergency procedures to incluce specific i.1 formation cbtained from the review and evaluaticn of Items 1, 2 and 3 to ensure that the operators are instructed on the pctential for and magnituce of erroneous level signals.

All taoles, curves, or correction f actors that would be applied to post-accident monitors should De readily available to the operator.

If revisions to procedures are required, provide a comoletion date for the revisions and a completion date for operator training on the revisions.

, report of the abcse actions shall be setmitted witnin 30 cays of the receipt of this Bulletin.

Espcrts s c' lc be submitted to the Director of the accrceriate NRC Regional Of# ice anc a cc;y shculc ce forwarced to tne NRC Offica of Inspection and Enforcement, Division of Reactor Operations Inspection. Washington, D. C.

20555.

For ceiling water reactors witn an operating license anc El' ;cter reactors aith a construction permit, tnis Bulletin is for infornation curposes and no e'itten response is required.

Approvec by GAO,.E180225 (R007:); clearance expires 7/31/E0.

"cproval was given under a blanket clearance specifically for icentifiec generic Oroblems.

Enclosure:

Memo Westinghouse Electric Ccrp.

to Victor Stclio dated June 22, 1979 m,-..

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