ML20012C727

LER 90-002-00:on 900217,steam Generator B Channel 3 Pressure Transmitter Failed Low & Declared Inoperable.Caused by Failure to Complete Tech Spec Required post-maint Test. Post-maint Test Procedure revised.W/900314 Ltr

ML20012C727
Person / Time
Site:	Beaver Valley
Issue date:	03/14/1990
From:	Noonan T DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-002-02, LER-90-2-2, ND3MNO-2042, NUDOCS 9003230129
Download: ML20012C727 (5)

Text

F ,

s l

4T i '7 T ier.none 9in apaa.aac Ng*go,roun 9,in.nono,t rA ison.oao4 l

March 14, 1990 l ND3MNO 2042 Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 LER 90-002-00 United States Nuclear Regulatory Commission -

Document Control Desk Washington, DC 20555 Gentlemen:

In accordance with Appendix A, Beaver Val.1.ey Technical Specifications, the following Licenseo Event Report is submitted:  ;

LER 90-002-00, 10 CFR 50.73.a.2.1.B, " Failure to Perform  ;

Time Response Testing".

Very truly yours, T.

, a -

P. Noonan 5"6 f/'a General Manager Nuclear Operations s1 Attachment 9003230129 900314 F- >

FDR ADOCK 05000412 [i S PDC (j 16pp

/ //

p

. March 14, 1990 )

CD3MNot 2042 i Page two 6

. E cc: Mr. William T. Russell c

Regional Administrator '

United States Nuclear Regulatory Commission Region 1 ,

475 Allendale Road t

King of Prussia, PA 19406 i C. A. Roteck, Ohio Edison L t Mr. Peter Tam, BVPS Licensing Project Manager United States Nuclear Regulatory Commission i Washington, DC 20555  !

J. Beall, Nuclear Regulatory Commission, l l BVPS Senior Resident Inspector Dave Amerine

• Centerior Energy ,

6200 Oak Tree Blvd.

Independence, Ohio 44101 .

INPO Records' Center  ;

Suite 1500 1100 Circle 75 Parkway j Atlanta, GA 30339 G. E. Muckle, Factory Mutual Engineering, Pittsburgh Mr. J. N. Steinmetz, Operating Plant Projects Manager Mid Atlantic Area Westinghouse Electric Corporation Energy Systems Service Division Box 355 l Pittsburgh, PA 15230 American Nuclear Ir.surers c/o Dottie Sherman, ANI Library i- The Exchange Suite 245 270 Farmington Avenue Farmington, CT 06032 Mr. Richard Janati Department of Environmental Resources P. O. Box 2063 16th Floor, Fulton Building Harrisburg, PA 17120 Director Safety Evaluation & Control Virginia, Electric & Power Co.

E P.O. Box 26666 One James River Plaza Richmond, VA 23261 V

O

, a sent e e ame u a msCL6 s me put,.ipay Consuns6eDN

! :etnovae ous No tinoeios LICENSEE EVENT REPORT (LER) * * *'a'

• C 8' "

.ACitn ,NA. en mc.i s ==n n is, **a+

Beaver Valley Power Station Unit 2 0 lb 101010141112 1 ]od O l 3 v o ts ..,

Tailure to Perform Time Rer,ponse Testing IVlNT Davl IDI Ll h MMBt R I.F RlPORT DAf f 171 DiHi k 9 ACILivit $ INVOLVID (Si ussN t > bar itAR Yl A81 S 8[,M ,' '" "'

, , $,) MD%19 DA) ilAt ' *( ' L 'i ' h a Yll DM

• I T M'Wht "'I' N/A 0l6l0l0l0 1 j j

~ ~

O! 2 1l2 9 0 9l 0 0l 0l 2 0l 0 d3 1l4 9l0 0 1 6toIoioi i I

,,,,,,,,,, twis mcome is evs ut,io consuANt to in a6 oui iwiNn o io C. a t rC, . . ., ,, .. ., ,, ,wwn, o n M* I to 4o:461 to 406541 to 73611:14 i 73 7ithi n mi.inini no wi.im no ni.nin.i n m.i 019 l 0 a mi.m na so wi.nsi no ni.nen.io gw,e a <j, ,) ,;,,

, .;ge, ni,.

so mi.inumi X So ni. anno so.ni.nin. nai mA, so ai.uno. so n nsn.n no ni.nin.mnoi na eu.in n., no n.nzn .n .o ni.nsu.i LICINLil CONI ACT FOR THl$ Llh nel

8. '.M t il LGPH(th4 NUMht et Aht A (Opl T. P. Noonan. General Manager Nuclear Operations 4l1l2 6l 4 i 3 l -i l1 2 1518 COMta tif DNI LINE 8 OR E ACH COMPONE NT f AtLUDI Di&CRI510 IN THit SEPORT 1131 C&U64 S v 51 t v CourchtNT ", f "' ,g

'D",'[g*{

y I CAu64 5* Sit M CovPONt % f

"" C

" 8,'O Pm D Si B PIT I I 1101 017 Y 1 i i i 1 l 1 1 I l l l l I s_,, I I I I I I f even.ut Ni At ai. cat ..lCn o n.,

,,,y, l uom ., o. n o ..

w.o ,0N

] ui v, .. .

.n e . A C i n ~,, n, .

tureno sv wssroN ver,

.. . . ,. ., .y.

1w

. . ,, , ,. , . ,. .v n . ,

l 1 l On 1/17/90, the "B" Steam Generator Channel 3 Pressure Transmitter failed low and was declared inoperable. The transmitter was replaced and the channel was returned to service on 1/19/90. During supervisory review of the completed work package, it was discovered that the channel had been returned to service without completing the required time response testing on the new transmitter. The channel was immediately declared inoperable and out of service until the time response testing could be completed. This testing was performed and verified that the transmitter response was within the required specifications. The channel was declared operable and returned to service at this time. Review of the event determined that the post-maintenance testing program did not have a requirement for time response testing. The post-maintenance testing is being revised to require time response testing on required components. There were no safety implications due to this event. .The time response testing verified that the channel was capable of performing its required function for the entire time when it was in service.

ug,, . n.

IsshC f orm an6a U 6 tuCLLD CL;UL& TORY COMMIT & LOW LICENSEE EVENT REPORT (LE] TEXT CCNTINUATION uniono ow wo v60-m awas Smo D ALILitv swamt sti gogg g g geganggg a gp p

- "a  %;!?P." 0,*3 Maver Valley Power Station Unit 2 0lt,l0l0l0l4l1l2 9l0 -

0l 0l 2 -

0l 0 0l 2 0F 0l3 TEKT M swe arme e reqpuwed. var eA8mprint AMC ,sym A164 W Uh Descrintion of Event On 1/17/90, steam pressure channel 3 for the "B" Steam Generator failed low. The channel was declared inoperable and its associated bistables tripped, as required by Technical Specification 3.3.2.1. As per the requirements, operation could continue under these conditions until the channel's next functional test, which was due 1/24/90. Investigation determined that the channel had failed due to a fault in its associated steam pressure transmitter (2 MSS-PT485). The transmitter was replaced and channel recalibrated. The channel was declared operable and returned to service on 1/19/90.

On 2/12/90, during supervisory review of the completed work package, it was discovered that time response testing had not been performed on the new pressure transmitter. Technical Specification 3.3.2.1 requires time response testing as a condition of operability. The channel was immediately declared inoperabic and removed from service. Time response testing was initiated and completed on 2/13/90. The results of the test showed that the transmitter had an acceptable time response. It was determined that the channel was operable and capable of performing its design function. The channel was then returned to service.

cause of Event The event occurred because of a failure to complete a Technical Specification required post-maintenance test (i.e. time response test). The station's post-maintenance testing program did not specifically identify the need for time response testing as a normal operability verification for transmitters. At the time the pressure tranmnitter was replaced, the involved supervisors did not identify the requirement to complete time response testing.

Corrective Actigns The requirement to perform time response testing is being incorporated lato the post-maintenance testing procedure and formal review prceeen. All maintenance supervisory personnel will receive training on this revised procedure.

Previous Similar Events There has been one previous reportable event involving a missed time response surveillance (Unit 1 LER 85-009). In this previous event, a scheduling error resulted in the Train "A" Reactor Trip Response Time Test not being performed within its required frequency. There has also been one previous event (Unit 2 LER 87-012) caused by inadequate post-maintenance testing. In LER ,87-012, the Rod Control System was returned to service after regulation failure without post-maintenance testing. The fault recurred, resulting in a reactor trip.

.# m ,2, ,

"gc . c= =..

I NRC f anen an64 U S NUCLEI itTULC. TORY CDMMIS$tDN i LICENSEE EVENT CEPORT ILER) TEXT CONTINUATION arraovf o oMe No mino-om tXPiktS 6 31'88

1. AC4Lt1Y e.aut (16 pocati Nuestita sas LIR NUMBER 16 PAGEtal

, nae "uz ::' :v:x:

B: aver Valley Power Station Unit 2 01510 l 01014l1 l 2 9l 0 -

010 l 2 -

010 01 3 OF 013 vert <n-N ..- - - wer mmenm I

S3fety Analysis There were no safety implications due to this event. Testing performed on 2/13/90 verified that the transmitter's response time was within the required specifications. This demonstrated that the associated channel was capable of performing its design function for the entire period when it was in service.

l l

l i NaC DOIM 346a att.$. CPoe 1988-529 589'00976' l 0 834