05000412/LER-1998-001, :on 980112,failure to Perform Surveillance Testing of Ci Spring Loaded Check Valve Was Noted.Caused by Fact That Ci Spring Loaded Check Valve Was Not Uniquely identified.2CVS-93 Was Successfully Tested

:on 980112,failure to Perform Surveillance Testing of Ci Spring Loaded Check Valve Was Noted.Caused by Fact That Ci Spring Loaded Check Valve Was Not Uniquely identified.2CVS-93 Was Successfully Tested

ML20202H635
Person / Time
Site:	Beaver Valley
Issue date:	02/11/1998
From:	Hart R, Jain S DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-98-030, L-98-30, LER-98-001, LER-98-1, NUDOCS 9802200433
Download: ML20202H635 (5)

LER-1998-001, on 980112,failure to Perform Surveillance Testing of Ci Spring Loaded Check Valve Was Noted.Caused by Fact That Ci Spring Loaded Check Valve Was Not Uniquely identified.2CVS-93 Was Successfully Tested

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)
4121998001R00 - NRC Website

text

. - - -. -_

Duquesne @ Company ggvy r re.< si.t a Shtpingport, F% tt,077 0004 EY.$$$;* "'

eu!!!!!!l!!!a wuci.., e..., oivi,Sn February 10,1998 L-98-030 Beaver Valley Power Station, Unit No. 2 Docket No. 50-412 License No. NPF-73 IJiR 98-001-00 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 In accordance with Appendix A, Beaver Valley Tecimical Specifications, the following Licensee Event Repon is submitted:

LER 98-00100,10 CFR 50.73(a)(2)(i)," Failure to Perfonn Surveillance iesting of Containment isolation Spring Loaded Check Valve as Required by Technical Specification 4.6.3.1.2.e."

hw ?0 >W S. C. Jain I

Jell /ds gjp Attachnient 9802200433 900211 PDR ADOLK 05000412 S

PDR

~

DEllVEilNi

~vV 41 0UAL1iV llllli,ll lll,lll,!!,1ll i,iiiV 4

c-

Februory 10,1998 L-98 030 Page 2 i

4-I cc:

Mr.11. J. Miller, Regional Adininistrator United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. D. S. Brinkman BVPS Senior Project Manager United States Nuclear Regulatory Commission Washington, DC 20555 Mr. David M. Kern BVPS Senior Resident inspector United States Nuclear Regulatory Commission Mr J. A. Ilultz Ohio Edison Company 76 S. Main Street Akron, Oli 44308 Mr. Steven Dumek Centerior Energy Corporation 6670 Beta Drive Mayfield Valley, Oil 44143 INPO Records Center 700 Galleria Parkway Atlanta, GA 30339 5957 Mr. Michael P. Murphy Bureau of Radiation Protection Department of Environmental Protection RCSOB.13th Floor P.O. Box 8469 liarrisburg, PA 17105 8469 Manager, Nuclear Licensing and Operations Support Virginia Electric & Power Company 5000 Dominion Blvd.

Innsbrook Tech. Center Glen Allen, VA 23060

oku Edi U & Nut ti.Aa caxiutAluki etwswuh Al's kot I.9 lis oua No. 3isa-pio4 (4 91) 1.XMklue M'M10 Iu t to.It

• 6 r

I.lcr.NsFJ.1: VENT R1:I' ORT (1J.H)

E E*I= E EE E E E EsE E WM.A.t',,T,n'M,.. A.,,,,3. oc 3.,3 '"

W o,.., u...

.a oo.oro.1.<n.,

.,.i.. uiioa>

,_ ;u A konar 1

W un wa.us as u a NMM th

& A(M. 9)

Ilcaver Valley power Station Unit 2 03000412 1 or 3 ha11ure to Perform Surveillance Testing of Containment Isolation Spring Loaded Check Valve as Required by Tech Spe t VI NI i>A it i9 a 1.1 k Nt %Ihr 6. ifo l

k I h ak i l > A 11 ( 7 e (if HI k p A,'il.iill 5 INyt it vu n ep s

$1 wtml bay v1 As ytAt p omt

,Av vt At 01 12 98 9M 001 00 l (12 11 98 l " " *"'

OPERATING

'5 8'" 8"uneu; n uurm us m kiwoucum+ imm nw.. c.

o o o ggp (g) 3 204u24) 20 40ks)

>O 7kaR2 Aet) 737100 POER 2 *"*""

5 '*"')

5 'h.x2xv>

33 tn.i 1.EVEI, (10)

O(10 ai, aus.ni a.1 su wtin2)

Su 7 5.na nv.,

otiith 20 40%a EI y m)

X SO?hea!RO

$0 7 he E 2)twant A)

(tr.id) * #ah.it 20 4U% a R 17 it) 30 )ha n 2 A u) 30 7 AaR2 Xviu s Dj helse ed o f.e 20 40%s AI NV)

>O 7 he 42 A m)

$O 7 hat 2 Am)

NhC f era l.6Al 1.l' 't N M F ('t d i A(" h ik ist!h l I k,1 D R. D. Ilart, Senior Licensing Superusor

" " " " * " * * ~ ~

(412) 393 52R4 min i ie os+ ust eok i Am mm vi e An m oirkiai o is Tiiis =i n.ki si n (ADte.

6 % 8! LAB HibOW.tXI 644NLe AJn kf A f dJ

• 44 4 40WtW bl4NVS ACitki k kl 4 1

N/A Mt fiti i AUW1 Al. k1.h ik 1 l-X}b *II.o f I e i 1.XitClLD

, j k >NIil DAY Yl. Ak YES x

NO

'['g8887 o%,icm.mnm m no nas utaen o

.a io i u>.m. i...n-.n..iy o..w. m.a nremi.n kn.o o.1 On January 12,1998 at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, with Unit 2 in Mode 5, an ongoing Technical Specification (TS) Surveillance Review identified that Containment isolation Spring Loaded Check Valve (CISLCV) 2CVS 93 was not being tested in accordance with the requirements of Unit 2 TS 4.6.3.1.2.c. This TS requires that each weight or spring loaded containment isolation valve be demonstrated operable during the cold shutdown or refueling mode at least once per 18 months by cycling each valve through one complete cycle of full travel and verifying that cach check valve remains closed when the differential pressure in the direction of flow is less than 1.2 psid and opens w hen the difTerential pressure in the direction of flow is greater than or equal to 1.2 psid but less than 6.0 psid. Contrary to this requirement, CISLCV 2CVS 93. Containment Radiation Monitor Discharge Check Valve, was not included in the Containment isolation Check Valve Test Program and consequently not tested. Failure to perform a Surveillance Requirement in the TS is a condition prohibited t)y TS and is thus reportable pursuant to the requirements of 10 CFR 50.73(a)(2)(i). There were no automatically or manually initiated safety system responses as a result of this event.

The apparent cause of this event was the fact that CISLCV 2CVS 93 was not uniquely identified on controlled prints, the controlled Master Equipment List, or in the UFSAR. This appears to be the main reason that CISLCV 2CVS 93 was not included in Containment Isolation Valve Surveillance Test (ST) 2DYT 147.3. Additionally, the Unit 2 preoperational test procedures, upon which the development of ST 2DVT 1.47.3 was based, did not identify this valve as a spring loaded check valve.

As completed corrective actions: (1) CISLCV 2CVS 93 was successfully tested on 01/16/98 in accordance with TS 4 6.3.L2 c, (2) ST 2DVT I 47.3 was revised to include testing of CISLCY 2CVS 93 on 01/15/98; (3) penetrations listed in the respective unit Licensing Requirements Manual ' Containment Penetrations' Tables and UFSAR ' Containment Isolation Arrangements' Tables were reviewed to verify that all applicable Containment isolation Weight and Spring Loaded Check Valves are identified and tested per Surveillance Tests. This was completed on 01/19/98. As a future corrective action, controlled prints and the controlled Master ' uipment List will be changed. and a UFSAR change request will be prepared, to identify all Containment Isolation Checi

s as either ' weight loaded' on jring loaded'.

The safety implications of this event are minimal. as CISLCV 2CVS 93 tested satisfactorily.

m n.,,

wecir wm ev%v

a NRCIORhtM6A U s. NUCLLAR RLut'LAIORY CohlhtisslON

.4 95)

I LICENhEF I: VENT REPORT (LER) l lWT C')E'it'AT ION 1 Acil.!!Y NAAlt(1)

IM ntT Nt'A1HER (2) 1.1 R NUAtlu.R (6) l PAUL (3)

SLQUEN!!AL klVISION l

Beaver Valley Power Station Unit 2 05000412 YEAR NUhtnLR NUMDER l

98 001 2OF3 an.

. u

- m y PLAJT AND SYSTEM IDENTIFK'ATION Westinghouse Pressurized Water Reactor (PWR)

Containment Isol tion Control System / isolation Valve (JM/ISV)*

• Energy industry identification System (Ells), system and component function identifier codes appear in the text as { S/CC).

CONDITIONS PRIOR TO OCCURRENCE Unit 2: Mode $, 0 percent Reactor Power IDENTIFICATION OF OCCURRENCE Discovery Date: January 12,1998 Event Date: This event has existed since Unit 2 startup.

DESCRIPTION OF EVENT

On January 12,1998 at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, a Technical Specification (TS) Surveillance Review (SR) team composed of Management and System Engineering representatives identified that Containment Isolation Spring Loaded Check Valve (CISLCV) 2CVS 93 (JM/ISV) was not being tested in accordance with the requirements of Unit 2 TS 4.6.3.1.2.c. This TS requires that cach weight or spring loaded containment isolation valve be demonstrated operable during the cold shutdown or refueling mode at least once per 18 months by cycling cach valve through one complete cycle of full travel and verifying that cach check valve remains closed w hen the differential pressure in the direction of flow is less than 1.2 psid and opens when the differential pressure in the direction of flow is greater than or equal to 1.2 psid but less than 6.0 psid. Contrary to this requiicment, CISLCV 2CVS 93, Containment Radiation Monitor Discharge Check Valve, was not included in the Containment Isolation Check Valve Test Program and consequently not tested. Further review has revealed that this condition has existed since Unit 2 startup.

Upon discovery, Condition Report Number 980050 was initiated to document the event.

This has been determined to not be applicable to Unit 1.

There were no automatically a manually initiated safety system responses as a result of this event.

l REPORTABil ITY TS 4.6.3.1.2.c requires that cach weight or spring loaded containment isolation valve be demonstrated operable during the cold shutdown or refueling mode at least once per 18 months by cycling cach valve through one complete cycle of full travel and verifying that cach check valve remains closed when the differential pressure in the direction of flow is less than 1.2 psid and opent when the di!Terential pressure in the direction of flow is greater that or equal to 1.2 psid but less than 6.0 psid. Contrary to tk requirement, CISLCV 2CVS 93, Containment Radiation Monitor Discharge Check Valve, was not included in the Containment isolation Check Valve Test Program and consequently not tested. Failure to perform a Surveillance Requirement in the TS is a condition prohibited by TS and is thus reportable pursuant to the requircrnents of 10 CFR 50.73(a)(2)(i).

,am.m..n

e d

hkC iURM 366A U.S NUCl,lAR kl.UU[A]ORY COMht1ssRJN (4 93) l.I(T.NhEE I;vEN1 Hl;l' ORT (I.l:H) l i'.XT (UNT INIWI ION I ACilJ1 Y N AML(1) t uf f! NUMHER (2)

El R N1'Mlu R (6)

I j' AOL O) 5tQUI.NilAL M.Y151UN Ucaver Valley Power Station Unit 2 05000412 Yl ^R NUht!!LR NUhtllLR 98 (Kil (X) 3OF3 nn

.,,,.c r m o n

)

CAUSF The apparent cause of this event was the fact that CISLCV 2CVS 93 was not uniquely identified on controlled prints, tl c controlled Master Equipment List, or in the UFSAR. This appears to be the main reason tiet CISLCV 2CVS 93 was not included in Containment Isolation Valve Surveillance Test 2DVr 1.47.3. There was only one spring loaded check valve on Unit 2, and this wasn't tested because Surveillance Test 2DVT 1.47.3 only tested weight loaded check valves. Additionally, the Unit 2 preoperational test procedures, upon which the development of Surveillance Test 2DVT 1.47.3 was based, did not identify this vah; as a spring loaded check valve.

CORRECTIVF ACTIONS COMPl.ETED:

1. CISLCV 2CVS 93 was successfully tested on January 16,1998 in accordance with the requirunents of TS 4.6.3.1.2.c.

2. Containment Isolation Check Valve Sury-illance Test 2DVT 1.47.3 was revised to include testing of CISLCV 2CVS 93 on January 15,1998.

3. Penetrations listed in the respective unit Licensing Requirements Manual ' Containment Penetrations' Tables and UFSAR

' Containment Isolation Arrangements' Tabics were reviewed to verify that all applicable Containment isolation Weight and Spring Loaded Check Valves are identified and tested per STs. This was completed on January 19,1998.

FUTURE:

4. Controlled prints and the controlled Master Equipment List will be changed, and a UFSAR change request will be prepared, to identify all Containment Isolation Check Valves as either ' weight loaded' or ' spring loaded'. This will be completed by March 20, 1998.

SAFETY IM Pl.ICATIONS The safety implications of this event are minimal, as CISLCV 2CVS 93 tested satisfactorily.

PREVIOUS SIMil.AR EVENTS A resiew of LERs for the past two years reviewed the following similar event:

1. LER 197-019-00," Containment Penetration Check Valves Not in Accordance with the Design Basis", dated August i1,1997.

hhs h44. leM q4 99)