ML20012C065

LER 90-003-01:on 900110,determined That Recirculation Spray HX River Water Radiation Monitor Sample Line Lacked Automatic,Remote Manual or Locked Shut Containment Isolation Valve.Request for Exemption Submitted to NRC.W/900308 Ltr

ML20012C065
Person / Time
Site:	Beaver Valley
Issue date:	03/08/1990
From:	Noonan T DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-003, LER-90-3, ND3MNO:2030, NUDOCS 9003200033
Download: ML20012C065 (5)

Text

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' March 8, 1990 ND3MNO:2030 ,

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Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 LER 90-003-01 United States Nuclear Regulatory Commission Document Control Desk  ;

Washington, DC 20555

' Gentlemen:

In accordance with Appendix A Beaver Valley Technical Specifications, the following rev1 sed Licensee Event Report is submitted:

LER 90-Od3-01,.10 CFR 50.73.a.2.ii.B, " Condition Outside:

%.i the Design Basis for the Recirculation Spray System". ,

Thiscrevision'is-being issued to revise the evaluation of the ,

safety-implications of th~ts event. This revised report' indicates

- that there were no safety' implications as a result of this event.

This-is due to tne procedure guidelines in-place for the isolation of an affected heat exchanger and maintenance of heat exchange

- tube integrity as described in the Justification For Continued Operation submitted January 11, 1990.

Very truly yours, t

T. P. Noonan General Manager Nuclear Operations s1 Attachnent L

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.ND3MNO:2030-E

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. ce ': Mr.nWilliam T.-Russell

: Regional Administrator. '

United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 C. A. Roteck, Ohio Edison i

'Mr. Peter Tam,,BVPS Licensing Project Manager  !

United States Nuclear Regulatory Commission Washin ton, DC 20555' J. Bea 1, Nuclear Regulatory Commission,  !

BVPS Senior Resident Inspector

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oy Dave Amerine ,

Centerior Energy

'6200 Oak Tree Blvd. >

Independence,FOhio 44101 INPO Records Center- '

Suite 1500 1100 Circle 75 Parkway ,

Atlanta, GA 30339 G. .E. Muckle, Factory Mutual Engineering, Pittsburgh j Mr. J. N. Steinmetz, Operating Plant Projects Manager Mid Atlantic Area Westinghouse Electric Corporation

. Energy Systems: Service Division Bcx 355 ~

-Pittsburgh', PA 15230 ,

American Nuclear Insurers j' c/o Dottie-Sherman, ANI Library L ~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 ,

i Harrisburg, PA 17120 Director, Safety Evaluation & Control Virginia' Electric &-Power Co.

P.O. Box'26666 One James River Plaza >

Richmond, VA 23261 >

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f ActLITY hAME lH DOCElf NUM9th (2) PAGE G Beavcr Valley Power Station, Unit 1 IITLE tel 015lo[0l0l3l3l4 1 lorl 013 Condition Outside the Design Basis for the Recirculation Spray System IVEN1 DATE lli LIR NUMBER lel REPORT DATI 17) OTH{ R F ACILillf $ INVOLVID ($1 MONTH DAY YEAR YLAR Hjj ( yf,4,7 MONTH day ygAR s AcsLiv y Nauss Docagt svMagpigi N/A 0l5l0l0l0l l l 0l1 1l0 9I 0 9l 0 0l 0 l3 0l 1 0l3 0l8 9l0 N/A 0 1 5l0 l0 t 0 i l l o,,,,,, ims RiPoRT is sunwTuo PURauANT To Tus RLouiRtM :m Os iO C, A e rew. .-. .,- ., e , u...wi ou MOOT m 1 20 402tti 20 406tel 50.73 eH2 Heel 73 f tthi if0 406teHiltH S0 3edeHu 60.736aH2 Hit 73 71tel n01 1l 0l0 20 40saHuw _

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"# 'AC "I TA g yO NPR g TO NPp B Bl E XI XI X IX XIX IX IX N I I I I I I I I I I I I I I i l I I I i i SUPPLEMENTAL REPORT E RPECTED 1941 l MONTH DAY YEAR SUOMisSION 4KS (19 yes e.moiste EMPECTED SUBwSSION DATEI NO l l l Ann R ACT a,- e. ,co .-,, 4. . ..,.. , u ,y. .- ..~ . o n ei On 1/10/90, it was determined that the Recirculation Spray Heat Exchanger-(RSHX) river water radiation monitor sample lines do not have a containment isolation valve that is automatic, remote manual or locked shut. This configuration does not meet General Design Criteria (GDC) 57, and no exception had previously been taken in the Updated Final Safety Analysis Report (UFSAR). The RS System is designed to provide the cooling and depressurization of the containment (CNMT) after Ony Loss Of Coolant Accident (LOCA). The River Water (WR) system is designed to supply cooling water to at least twc of the four RS heat exchangers. DurincJ accident conditions, the RSHX radiation monitors analyze a continuous sample obtained from each heat exchanger river water outlet. The outside CNMT river water lines discharging from the RSHXs contain a one inch branch line, to the RSHX radiation monitors between the CNMT penetration and the CNMT motor operated isolatkon valve. This branch line does not meet the requirements of GDC 57. The cause for this event was a deficiency in the UFSAR documentation. A Justification for Continued Operation and an exemption to GDC 57 have been issued. There were no safety implications as a result of this event. In the event of a RSHX tube failure, provisions exist for isolation of the pathway outside of containment.

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.0' LICENSEE EVENT REPORT (LER) TEXT CONTINUATION arPaovio ove No. sisoaio4 EXPIRt6: 8.'3ila8 9 ActLaTY NAML (11 DOCKti NUMetR (2l Ltfl NUMBEft 161 PAGE (3) via" "$!.O OL"llf Beaver Valley Power Station, Unit 1 0 l6 l0 l0 l0 l 3l 3l 4 9lU -

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DESCRIPTION On 1/10/90, it was determined that the Recirculation Spray Heat '

Exchanger (RSHX) river water radiation monitor (RM-RW-100A, '

100B, 100C, 100D) sample lines do not have a containment

. isolation valve that is automatic, remote manual or locked shut. This-configuration does not meet General Design Criteria  ;

(GDC) 57, and no exception had previously been taken in the Updated Final Safety Analysis Report (UFSAR). The systems involved are the Recirculation Spray (RS) System, the River Water (WR) System and the. Radiation Monitoring System. The RS System is designed to provide the cooling and depressurization of the containment (CNMT) after any Loss Of Coolant Accident (LOCA). The WR system is designed to supply cooling water to at least two of the four RS heat exchangers. During accident s conditions, the RSHX radiation monitors, one monitor for each heat exchanger, analyze a continuous sample obtained from each heat exchanger water outlet. The outside CNMT river water lines discharging from the RSHXs contain a one inch branch line, to the RSHX radiation monitors, between the CNMT penetration and the CNMT motor operated isolation va3ve. This branch line does not meet the requirements of GDC 57.

CAUSE OF THE EVENT The cause for this event was a deficiency in the UFSAR documentation. The system design is sufficient to address the

-technical aspects of this concern, however, the UFSAR Section 5.3.3 does not describe this deviation from General Design Criteria 57.

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CORRECTIVE ACTIONE i The following corrective actions have been taken as a result of I

this event:

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1. A Justification for Continued Operation (JCO) has been  ;

orepared to address the deviation from GDC 57.

L 2. An request for exemption to GDC 57 has been initiated through a letter from J. D. Sieber dated, January 11, 1990.

3. Operating procedures were reviewed and were found to ensure isolation of the affected heat exchanger and monitoring path in the event of a tube failure during a postulated accident.

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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION cenoveo ove wo mo ow IXPiRIS: 8 '31'98 P Actkl1Y NAME Of DOCKET NUMBtn (2) gg g gyggg g (gg pagg (3g ve^a " 30";l'. -

%*.W Bsaver Valley Power Station, Unit 1 YEXT C puws spece e eeuwed use ecutoonst MC 7orm JsECsJ 07) 0l5 0l0l0 3l3)4 9l0 -

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0l1 0l3 OF 0l3 SAFETY IMPLICATIONS There were no safety implications to the public as a result'of l',

this event. The existing plant configuration presents no adverse effects as a result of postulated accidents since flow of contaminated fluid through the sample line would require that a passive failure be assumed (recirculation spray heat exchanger ,

tube leak) in the short term following the initiating accident.

Assumption of this type of failure is not within the Beaver Valley Power Station Unit 1 licensing basis (

Reference:

UFSAR Section 1.3.1). Assumption of the tube failure presents no adverse effects in the long term since existing operating procedures contain provisions for shutdown of the recirculation spray pump. This removes the driving force for the leak since the containment is subatmospheric and provides time for operators to complete manual isolation of the sample lines as well.

REPORTABILITY This. event has been reported in accordance with 10CFR50.72.

This written report is being submitted in accordance with 10CFR50.73.a.2.ii.B, as a condition that is outside the design basis of the plant as described in the Updated Final Safety

~ Analysis Report.

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