ML17223A746

LER 90-003-00:on 900110,determined That Recirculation Spray HX River Water Radiation Monitor Sample Lines Lacked Automatic,Remote Manual or Locked Shut Isolation Valve. Exemption Request from GDC 57 initiated.W/900209 Ltr

ML17223A746
Person / Time
Site:	Beaver Valley
Issue date:	02/09/1990
From:	Noonan T DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-003, LER-90-3, ND3MNO:2025, NUDOCS 9002230028
Download: ML17223A746 (7)

Text

ACCELERATED DISTRIBUTION DEMONSTIRATION SYSTEM e

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9002230028 AOC.DATE: 90/02/09 NOTARIZED: NO DOCKET g FACIL:50-334 Beaver Valley Power Station, Unit 1, Duquesne Light C 05000334 AUTH. NAME AUTHOR AFFILIATION NOONAN,T.P. Duquesne Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 90-003-00:on 900110,condition outside design basis for recirculation spray sys.

W/8 , ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), Inciden Rpt, etc.

NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-4 LA 1 1 PD1-4 PD 1 1 TAM,P 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 3.'

AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 DEDRO 1 1 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB9H3 1 1 NRR/DET/ESGB 8D 1 1 NRR/DLPQ/LHFB11 1 ' 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB11 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR~SX/S LB8D1 1 1 NRR/DST/SRXB 8E 1 1 MG FWE 02 1 1 RES/DSIR/EIB 1 1 GN'I N' 1 1 1 EXTERNAL: EGGG WILLIAMS,S 4 4 L ST LOBBY WARD 1 1 LPDR 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIFS,REQUIRED: LTTR 37 ENCL 37

~<V~

Duquesne bcfrt Telephone (412) 393 6000 Nuclear Group P.O. Box,4 Shippingperh PA 15077-0004 February 9, 1990.

ND3MNO:2025 Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 LER 90-003-00 United States Nuclear Regulatory Commission Document, Control Desk Washington, DC 20555 Gentlemen:

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

LER 90-003-00, 10 CFR 50.73.a.2.ii.B, "Condition Outside the Design Basis for the Recirculation Spray System".

Very truly yours, T. P. Noonan General Manager Nuclear Operations Cg Attachment

~0022-"-'0028 F~DR 90020/

0500C>'34 AXIOCK 1= DC: r>>~

February 9, 1990 ND3MNO:2025 Page two cc: Mr. William T.. Russell Regional Administrator Un>ted States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 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 Dave Amerine Centerior Energy 6200 Oak Tree Blvd.

Independence, Ohio 44101 INPO Records Center Suite 1500 1100 Circle 75 Parkw'ay 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 Pittsburgh, PA 15230 American Nuclear Insurers c/o Dottie Sherman, ANI Library 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 6 Control Virginia Electric 6 Power Co.

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

NRC Form 388 U.S. NUCLEAR REGULATORY COMMISSION (943)

APPROVED OMB NO, 3)504104 LICENSEE EVENT REPORT (LER) EXPIRES:

8/31/88'ACILITY NAME (I) DOCKET NUMBER (2l PA E 3 Beaver Valley 'Power Station, Unit 1 0 5 0 0 0 3 3 4 1 OF P-3 TI'TLE (Cl Condition Outside the Design Basis for the Recirculation Spray System EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR 4 Ã SEOVENTIAL >r" Revved MONTH DAY YEAR FACILITYNAMES DOCKFT NUMBERIS)

1'/>)1 NUMBER VC> NUMBER N/A 0 5 0 0 0 0 1 1 0 9 0 9 0 003 00 02 09 9 0 N/A 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT T 0 THE RLOUIREMENTS OF 10 CFR (): /Cnecp ont or mort of tht follow/np/ (ll MODE (0) 20A02(5) 20A05(c) 60.7 3(c I (2 I (iv) 73.7((5)

POWER 20.405 (~ ) (I ) (i) 60.38(c)(1) 60.7 3 I ~ I I 2)( v I 73.71(c)

LEVEL 1 p p 20.405( ~ ) (1)(ill 50.38(cl(2) 60.73( ~ l(2) (vill OTHER /Specify /n Atrsttect Oelew tnd ln Teer, f/RC Form 20.805( ~ ) (I) (i'll 50.73( ~ l(2)li) 60.73( ~ I (2) lviii)(Al 366A/

20A05(e)(1)(iv) 2E 60.73( ~ I(2)(ii) 50.73( ~ l(2)lviiil(B) 23.C 8(el(1)(vi 50.73( ~ l(2) liii) 50.73 (~ I I2 I I x'I LICENSEE CONTACT FOR THIS LER (12(

NAME TELEPHONE NUMBER Thomas P. Noonan, General Manager Nuclear Operations AREA CODE 41 2 643 -12 58 COMPLETE ONE LINE FOR EACH COIIiIPONENT FAILURE DESCRIBED IN THIS REPOR'7 (13)

CAUSE SYSTE(li COMPONENT MANUFAC TURE'R (0 N Ri> i>48+Cr

, <<<<>P<F("r rLIIE

<<'fr>>.'V%/re CAUSE SYSTEM COMPONENT MANUFAC.

TURER i>OR>*Bi>

Q>/PE.

B E XXX XXX XX N SUPPLEMENTAL REPORT EXPECTED (ICI IXONTH DAY YEAR EXPECTED SUBMISSION DATE (151 YF S //f yts, corr piete fXPECTED SUBM/SS/0/Y DA TE/

ABSTRACT /timlt to tt00 ssoctL / ~ ., et>prox/merely littten slnplt sotto typewritten lined (18)

On 1/10/90, v

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)'fter any Loss Of Coolant Accident (LOCA). The River Water (WR) system is designed to supply cooling water to at least two of the four RS heat exchangers. DurincI 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 line and the CNMT motor operated isolation valve. This branch 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. ln the event of a RSHX tube failure, provisions exist for isolation of the pathway outside of containment.

NRC Form 385 (9 831

NRC Form 366A (983) U.S. NUCLEAR REOULATORY COMMISSION LICENSEE T REPORT (LER) TEXT CONTINUA APPROVEO OMB NO. 3IEOW(04 EXPIRFSI 8/31/88 FACILITY NAME (ll COCKET NUMBER (2)

LER NUMBER (6) PACE (3)

YEAR SEOUENZIAL ~~~:g REVISION NUMBER '.48'UMBER Beaver Valley Power Station., Unit 1 0 5 0 0 0 3 3 4 9 0 0 0 3 0 0 0 2 0" 0 3 TEXT /// more epeoe /e rer/o/red, ore edditione/ //RC Form 366/I 'e/ (17)

DESCRIPTI ON On 1/ 1 0/9 0, it was determined that the Recirculation Spray Heat Exchanger (RSHX) river water radiation monitor (RM-RW-100A, 1 OOB, 1 OOC, 1 OOD) sample lines do not have a containment isolation valve that z.s aut omatic, 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 Sa fety Analysis Report (UFSAR) ~ The systems involved are the Recirculation Spray (RS ) System, the River Water (WR) System and the Radiation Monitoring System. The RS is designed to provide the of the containment ( CNMT) after anycooling System and depressurizat ion

~

Loss Of Coolant Accident The WR system is designed to cooling water to at least two of the four RS heat exchangerssupply

( LOCA) ~

. During accident conditions, the RSHX radiat,ion 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 b'ranch line, to the RSHX radiation monitors, between the CNMT penetration the CNMT motor operated iso 1 ation valve . This branch line and 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'he technical aspects of this concern, however, the UFSAR Section 5 3 3 does not describe this deviation from General Design

~ ~

Criteria 57 ~

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

A Justification for Continued Operation JCO) has been repared to address the deviation from GDC( 57 ~

2 ~ An request for exemption to GDC 57 has been initiated through a 1 etter from J D S ieber dated, January 1 1,

~ ~

1990 ~

3 ~ Operating procedures were reviewed and were found t'o ensure isolation of, the affected heat exchanger and monitoring path in the event of a tube failure during l

postu ated accident .

a NRC FORM 3664 ~ 0 6, CPOg (999 $ 20 $ 99r00070 (9 83)

U.S, NUCLEAR REOULATORY COMMISSION NRC'Form 366A 3)50M)04 (8.83 I LlCENSEE E T REPORT (LER) TEXT CONTlNUAT APPROVEO OMB NO.

EXPIRES: 8/31/88 DOCKET NUMBER (2) LER NUMBER (6) I AOE (3)

FACILITY NAME (I)

SEQUENTIAL REVISION YEAR NUMBER NP5 NUMBER Beaver Valley Power Station, Unit 1 0 5 0 0 0 3 3' 9 0 003 00 03 OF 0 3 TEXT /// more epeee le reou/red, uee eddlr/one/ hfRC Form 3664'4) ((7)

SAFETY IMPLICATIONS There were safety implications to the public as a result of 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.zi.B, as a condition that is outside the design basis of the plant as described in the Updated Final Safety Analysis Report.

~ I 5 CPCg IeEII 3 ( SSB IIBIITI NRC CORM SBBA (8 8",