ML19325C632

LER 89-025-00:on 890910,high Temps on Steam Generators B & C Auxiliary Feedwater Lines Identified.Caused by Improper Seating of Auxiliary Feedwater Check Valves.Procedure Initiated to Verify & Correct condition.W/891010 Ltr

ML19325C632
Person / Time
Site:	Beaver Valley
Issue date:	10/10/1989
From:	Noonan T DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-025, LER-89-25, ND3MNO:1974, NUDOCS 8910170118
Download: ML19325C632 (7)

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P.O Don 4 I t,h.ppinoport PA nonaam October 10, 1989 i ND3MNO:1974 l V j i

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Beaver Valley Power Station, Unit No. 2

$' Docket No. 50-412, License No. NPF-73 LER 89-025.00 V

l United States Nuclear Regulatory Commission .

Document Control Desk Washington, DC 20555 i

Gentlemen:- -

In accordance with Appendix A, Beaver Valley Technical -

' Specifications, the following Licensee Event Report is submitted:  !

LER 89-025-00, 10 CFR 50.73.a.2.ii.A, " Auxiliary l

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Feedwater Intra-System Recirculation - Unanalyzed Condition".

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T. P. Noonan General Manager Nuclear Operations cj  ;

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cci Mr. William T. Russell l Regional Administrator tUnited States Nuclear Regulatory Commission J Region.1  ;

475 Allendals Road  !

King of Prussia, PA 19406 J i

C. A. Roteck, Ohio Edison '

Mr. Peter Tam, BVPS Licensing Project Manager United States Nuclear Regulatory Commission

-Washington, DC 20555 ,

J. Beall, Nuclear Regulatory Commission, BVPS Senior Resident Inspector j CAPCO Nuclear Projects Coordinator Toledo Edison j INPO Records Center Suite 1500 -

1100 circle 75 Parkway Atlanta, GA 30339 i I

I G. E. Muckle, Factory Mutual Engineering, Pittsburgh ,

I Mr. J. N. Steinmetz, Operating Plant Projects Manager ,

Mid Atlantic Area Westinghouse Electric Corporation Energy Systems Service Division ,

Box 355 Pittsburgh, PA 15230 American Nuclear Insurers c/o'Dottie Sherman, ANI Library  !

The Exchange Suite 245' 270 Farmington Avenue Farmington, CT 06032 ,

i Mr. Richard Janat3 Department of Environmental Resources P. O. Box 2063 16th Floor, Fulton Building ,  !

Harrisburg, PA 1*i120 Director, Safety E'ialuation & Control Virginia Electric & Power Co. ,

P.O. Box 26666 One James River P1.aza -

Richmond, VA 23251 4

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APPROVED DMS NO 3100 4'04 UCENSEE EVENT REPORT (LER) "aa'

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N1We TELEPHONE NuM018I Thomas P. Noonan, General Manager Nuclear Operation 41112 61413 l- l 1121518 COMPLtit ONE Liht F08i E ACM COMPONtNT P AILUht DthCRIDED IN TMit AtPORT 1936 t gay,g Cault tvsit u cou'ONtNY "$%l AC- Mjr0{,1Agg n ,, g7 g , goy,pggg, vggjAC nto,tAggt n

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on 9/10/89 at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />, Ope 13tions personnel identified high temperatures on the "B" and "C" Steam Generator (SGB and SGC)

Auxiliary Feedwater (AFW) lines. Pyrometer readings (250 degrees Fahrenheit (F) to 328 F) indicated recirculation within the SGB and SGC AFW lines, apparently the result of AFW check valves not properly seated. Operations personnel initiated a procedure to verify and ccrrect this condition by flushing the AFW line with an AFW pump to reseat the check valves. Due to thermal considerations and potential waterhammer, engineering support was requested prior to performance of this procedure. The train I

"B" hydraulic control valve in the SGB AFW line was closed, at 1640 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.2402e-4 months <br />, to limit the backleakage. Engineering recommended that flushing be performed after the piping was below 200 F. At 2003 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.621415e-4 months <br />, after the piping temperature was less than 200 F, I the "B" AFW line was flushed for two minutes, reducing the l piping temperature to 85 F and rescating the check valves. A l periodic trend of AFW piping temperature was initiated to verify no further leakage occurred. There were no safety implications as a result of this event. An Engineering evaluation showed that the elevated temperatures would not have impacted the AFW system's ability to perform its design function.

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FActu1V esamt en DOCM1 NUMDEn (H tt h WUMet fl 16) PAGE L38 vtaa "T8[,[,  : [,N Be:ver Valley Power Station, Unit 2 0F 1 l510 l o l0 l 4 l1 l2 81 9 0 l215 -

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DESCRIPTION i

on 9/10/89 at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />, Operations personnel were notified of an l

unusual oder in the South safeguards Area. Operators investigated '

and found that the odor was the result of the effects of high j temperatures in the "B" and "C" Steam Generator (SGB and SGC)

Auxiliary Feedwater (AFW) lines. The high temperatures were believed to be the result of backleakage past check valves 2FWE-100 and 2FWE-43B. The valves apparently did not resent after an earlier AFW surveillance test. The leakage flowpath was from the "B" Steam Generator AFW line, into the Train "B" AFW header  ;

and into the "C" Steam Generator via the Train "B" AFW header.

This was determined via pyrometer readings on the AFW piping. The l-AFW line temperature at the containment penetration for the "B" Steam Generator was measured at 328 degrees Fahrenheit.

Temperatures gradually decreased along this flowpath due to ambient cooling, until at the penetration for the "C" Steam  ;

l Generator the temperature was 250 degrees Fahrenheit (see Figure i 1). No backleakage was detected past the check valves into the

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Train "A" AFW header or past the "B" Motor Driven Auxiliary Feedwater Pump discharge check valve.

I Operations personnel than began preparations to perform a procedure to verify and correct this condition. This procedure would flush the AFW line, using an AFW pump, and reseat the check

' valves. Due to thermal considerations and potential waterhammer, engineering support was requested prior to performance of this procedure. Engineering recommended that flushing be performed -

after the piping was below 200 F. The hydraulic control valve in the "B" AFW line was closed, at 1640 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.2402e-4 months <br />, to stop the backleakage and allow the piping to cool. This action isolated Train "B" AFW to the "B" Steam Generator and placed the station into the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Action Statement for Technical Specification 3.7.1.2 (one inoperable train of AFW). Train "B" AFW was still available to the other Steam Generators. Train "A" AFW was l operable and available to all Steam Generators throughout this event.

At 2003 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.621415e-4 months <br />, after the piping temperature had decreased to below 200 degrees F, the hydraulic control valve was reopened and the station exited Technical Specification 3.7.1.2. The "B" AFW line was flushed using throttled flow, as per procedure, for two minutes. This reduced the maximum piping temperature to 85 F.

Operations personnel then initiated a periodic trend (once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) to monitor the AFW piping temperatures to ensure that the check valves were seated. On 9/11/89, after verification that the AFW piping temperature was steadily decreasing to ambient area temperatures, the periodic trend frequency was decreased to a shiftly frequency.

NRC PoRM 368A *U.S. GPOs 1985.$20-599 000 70 C431 -

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'l The cause for this event was attributed to check valves in the SGB AFW line (2FWE-100: Walworth Co. Model 5350 WE valve, and 2FWE-43B: Atwood & Morrill Co. Inc. Model 1350-16H valve) which

'were not properly seated, allowing main feedwater flow into the ~

AFW piping. After flushing, the check valves reseated a.nd the leakage was eliminated. Work requests have been initiated to inspect these valves and perform any necessary corrective actions.

CORRECTIVE ACTIONS The following corrective actions have been or will be taken as a result of this event:

1. The hydraulic control valve for the SGB AFW line was closed to limit the backleakage in the piping.

2. Operations personnel performed procedure OM 2.24.4Q, to flush the SGB AFW line and reseat the check valves. '

3. A periodic trend was initiated to monitor AFW piping '

temperatures. i

4. Maintenance Work Requests were generated to inspect and repair the SGB AFW check valves (2FWE-100 and 2FWE-43B).

5. AFW piping temperatures are currently monitored at the ,

Auxiliary Feedwater Pumps to check for steam binding of the pumps. This practice will be revised to monitor the temperatures near the AFW containment penetrations. This will identify both steam binding and/or intra-system recirculation.

6. This event will be. included in the Operator Licensed Retraining Sessions and in the Technical Personnel Training for Testing personnel.

SAFETY IMPLICATIONS There were no safety implications as a result of this event. An Engineering evaluation of this event indicated that the high temperatures experienced by the AFW piping had no detrimental effects.

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0l 0 0l4 0F 0 l5 isxt w -e w a nea.< anaw unc r.m. snuw on REPORTABILITY This event was determined to be reportable in accordance with the requirement of 10CFR50.73.a.2.ii.A, as an unanalyzed condition.

An Engineering evaluation determined that plant safety was not significantly compromised, therefore this event was not reported in accordance with 10CFR50.72.b.ii.A.

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