ML17223A214

LER 89-004-00:on 890605,leak Rate on Containment Penetration 10 Exceeded Allowance,Per Tech Spec 4.6.1.7.3. Caused by Personnel Error.Technical Manual Change Request submitted.W/890705 Ltr

ML17223A214
Person / Time
Site:	Saint Lucie
Issue date:	07/05/1989
From:	Holifield C, Woody C FLORIDA POWER & LIGHT CO.
To:
References
L-89-238, LER-89-004-02, LER-89-4-2, NUDOCS 8907120017
Download: ML17223A214 (5)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8907120017 DOC.DATE: 89/07/05 NOTARIZED: NO DOCKET FACIL:50-389 St. Lucie Plant, Unit 2, Florida Power & Light Co. 05000389 AUTH. NAME 'UTHOR AFFILIATION HOLIFIELD,C.D.. Florida Power & Light Co.

WOODY,C.O.

Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION R

SUBJECT:

LER 89-004-00:on 890605,containment local leak rate exceeds I

TS due to valve closure stop out of adjustment. D DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc. t ~

t NOTES'OPIES RECIPIENT RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 D NORRIS,J 1 1 D

INTERNAL: ACRS MICHELSON. 1 1 ACRS 2 2 ACRS WYLIE 1 MOELLER'EOD/DOA 1 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 '2 DEDRO 1 1 IRM/DCTS/DAB 1 NRR/DEST/ADE, 8H '1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 1"

NRR/DEST/MTB 9H 1 ,.1 NRR/DESTOPSB 8D 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 NRR/DLPQ/PEB 10 1 1 NRR/DOEA/EAB 11 1 NRR~REP/ PB 10 2 2 NUDOCS-ABSTRACT 1 REG 02 1 . 1 RES/DSIR/EIB 1 RES/DSR/PRAB 1 1 RGN2 FILE 01 1 1 EXTERNAL EG&G WILLIAMSg S 4 4 FORD BLDG HOY,A L ST LOBBY 'WARD 1 1 LPDR NRC PDR 1 1 NSIC MAYS,G NSIC MURPHYgG A 1' D

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D NOIR 'ZO ALL RIDS" R1KXEKENIS:

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FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES. REQUIRED: LTTR 43 ENCL 42

P.O. Box14000, Juno Beach, FL 33408.0420 JULY, 5 1989 L-89-238 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: St. Lucie Unit 2 Docket No. 50-389 Reportable Event: 89-04 Date of Event: 'June 5, 1989 Containment Local Leak Rate Exceeds Technical Specifications Due to Valve Closure Sto Out of Ad'ustment Due to Personnel Error The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.

Very truly yours,

.C. 0. Wo Acting nior Vice President Nuclear COW/JRH/cm Attachment cc: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRC

/

-:907120017 S9070 PDR ADGCK 05000389 PDC all I l l a>> < I

NRC fornr 344 U.S. NUCLEAR REOULATORY COMMISSION 94)31 APPROVED OMS NO, 3150410C LICENSEE EVENT REPORT {LER) EXPIRES,'~ /31/$5 FACILITY NAME lll OOCKEt NUMSER (2) PAO I St. Lucie, Unit 2 o s oo o38 1 OF TITLE <<) Contaqnmen oca +a a e xcee s ec naca peer i ca n Closure Sto put of Adjustment Due to Personnel Error EVENT DATE (5I LER NUMSER (5) REtORT DATE (7) OTHER FACILITIES INVOLVED ISI S 4 0 u 4 N 7 I A I. "SYR~ FACILITYNAMES OOCRET NuMEER(s>

MONTe DAY YEAR YEAR NVMSSA NVMSSR MONTH OAY YEAR N/A 0 5 0 0 0 05 989 004 0 0 0 7 8 9 0 5 0 0 0 OPS.AT(NO THIS REPORT IS SUSMITTEO tuRSUANT T 0 THE REOUIREMENTS OF 10 Cf R (Ir IChtce tilt or irioi' 0/ lht ltr/owrnf/ Ill MODE ( ~ I 1 20.402(4) 20AOS(cl 50.7$ (el(2) IN) 7$ .71( ~ I

~ DIVER 20A05( ~ )(IIIII 50.$ 5( ~ ) Ill 50.7 $ (e) 12)(y) 7$ .71I ~ I y p p Ill(yl 20.405( ~ )(I l(4)

(10) 50.35(c)LTI 50.7 $ (el (2) (or( ) 0'tHER ISotciry in icollrtcl Ot/Ory end in Ttet, NRC FOnn 20AOS( ~ I (I l(ryl) 50.73( ~ I (2(III 50.7$ (c l(2) (ySI ) (AI 3FFll 20A05 (e I llI I ItI 50.7$ (e)(2)(4) 50.73(e)12)(y(4) ( ~ I 20A05(c I 50.73(e l(21(9(l 50.7$ ( ~ l(2)(el LICENSEE CONTACT FOR THIS LER 02)

NAME TELE/ NONE NUMSER Charles D. Holifield, Shift Technical Advisor AREA CODE 407 465 - 35 p COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRI ~ EO IN THIS REtOR'T (1$ l MANUFAC. ftORtASLE MANVFAC EPORTASLE CAUSE SYSTEM COMPONENT TVRER TO NPROS A CAVSf SYSTEM COMtONENT Y TVRER TO NPROS SuttLEMKNTAL RftORT EXtECTEO (1iu MONTii OAV YEAR EXPECTED SUSMISSION DATE USI YES III yn, Ctetrtrt EXPECTED SUSMISSIOAI DATE/ NO ASSTRACT ILieit lo lc00 roectl, I ~,, toproeietltry Irlletn petit Iotct cyotwn(Nn rinNI ll~ I On June 5, 1989, at 1220, with Unit 2 in Mode 1 at, 100% power, a routine local leak rate surveillance test was performed on Containment Penetration 10. This penetration, which contains the exhaust line for the Containment. Purge System, is subject to Type C testing and revealed an "as-found" leakage rate across FCV-25-5 in excess of 3,171,840 standard cubic centimeters per minute (SCCM) . This leakage rate is in excess of the allowable leakage of .05 La, or 48,500 SCCM, as per Technical Specification 4.6.1.7 '

root cause of the high measured leakage was personnel error in

'he that the valve adjustment stop was not properly locked down by contractor personnel when the valve was previously adjusted. A contributing factor was lack of guidance in the technical manual on how to tighten the adjustment screw locknut.

Corrective actions included confirming that the fuses for FCV 6 (a second valve in the containment purge exhaust line) were pulled, leak testing FCV-25-6, adjusting and locking down the stop for closing of FCV-25-5, and re-testing FCV-25-5, with satisfactory results. A technical manual change request will also be submitted.

N RC fore 344

/9 53 ~

NRC Form 3SSA U.S. NUCLEAR RECULATORY COMMISSIC (943(

LICENSEE EVENT REPORT tLER) TEXT CONTINUATION APPROVED OMB NO, 3150-0(04 EXPIRES.'8/31/88 FACILITY NAME ((I DOCKET NUMBER (2( LER NUMBER (SI ~ ACE (3)

~ YEAR >>M SECUCNTIAI IN/I RCvrsroN NUMBER NUMSC/I St. Lucie, Unit 2 o s o o o 89 0 04 00 02 oF 03 TEXT llfmore srrese is eorrired, rrso sddrdorro/ HRC %%drm 3/(SA's/ ((TI DESCRIPTION OF THE EVENT On June 5, 1989, at 1220, with Unit. 2 in Mode 1 at 1004 power, a routine local leak rate surveillance test on Containment Penetration 10 revealed a leakage rate across FCV-25-5 (EIIS:ISV) in excess of 3,171,840 Standard Cubic Centimeters per Minute (SCCM) which is the capacity of the test equipment. Penetration 10 contains a 48 inch exhaust line for the Containment Purge System, with three butterfly valves, two of which (FCV-25-4 and FCV-25-5) are subject to Type C testing, as per Unit 2 Technical Specification 3.6.1.2.b, Table 3.6.-1 and Surveillance 4.6.1.7.3.

Local leak rate testing is performed by pressurizing the piping between FCV-2S-4 and FCV-25-5. Test instrumentation is connected to a test tap between the two valves, and the change in pressure over time is recorded and used to calculate the leakage rate. The as-found leakage of the penetration was in excess of the allowable leakage of .05 La, or 48,500 SCCM. In accordance with Technical Specification 3.6.1.1.7, action was undertaken to restore the leakage rate to within the specified limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Also in accordance with Technical Specification 3.6.3., the fuses on FCV-25-6, an additional valve .in series with FCV-25-5, were verified to be pulled and this valve was leak tested. Following an adjustment, the valve seat stop adjustment screw was locked down-, and the leakage rate across FCV-25-5 was reduced to 200 SCCM.

CAUSE OF THE EVENT The root cause of this event was personnel error by contractor maintenance personnel in that the valve travel adjustment screw locknut was only hand tightened the last time the valve travel was adjusted. A contributing factor to this event is the lack of guidance in the Technical Manual on how to tighten the adjustment drift and resulted in the tight screw locknut. The hand locknut allowed the valve travel to excessive leakage across FCV-25-S. There were no unusual characteristics of the work location that directly contributed to the personnel error.

NRC form 344A U.S. NUCLEAR REOULATORY COMMISSIO I9431 LICENSE ENT REPORT ILER) TEXT CONTIN ION APPROVEO OMS NO. 3I 50&I04 EXPIRES: 4/31/bb PACILITY NAME III OOCKET NUMSER IEI LER NUMSER ISI PACE I3)

YEAR IN+l 44ovENTIAL

'>+r NVM44R gP'lfvleloN

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NVM44R St. Lucie, Unit 2 o s o o o3 89 89 0 04 00 0 3oF 0 3 TEXT /// move opoce ro oovrvorL ooo ~ /enovvo///RC fr>>rrr 3/34A9/ I I TI ANALYSIS OF THE EVENT This, event has been deemed reportable as per the requirements of 10 CFR 50.73(a) (2) (i) (B), any operation or condition prohibited by the plant's Technical Specifications. local leak rate testing on Penetration 10 was performed previous The with satisfactory results during the normally scheduled refueling outage which ran from early February through April of 1989. Unit 2 Technical Specification Surveillance Requirement 4.6.1.7.3"requires testing of .the Purge Valves to be conducted at -intervals of at least once per 6 months on a staggered test basis. Therefore, the containment leakage rates, according to the requirements of this Technical Specification, were tested well within the bounds of the specified surveillance interval.

The limits for containment leakage rates in the Unit 2 Technical Specifications are derived from the requirements of Appendix J to 10 CFR 50. Since the other two valves in the Containment Purge exhaust lines (FCV-25-4 and FCV-25-6) were operable, the, containment isolation safety function was maintained and the health and safety of the public was not threatened.

CORRECTIVE ACTIONS Operations personnel confirmed that the fuses were pulled on FCV-25-6.

2) The Technical Staff Test Group leak tested FCV-25-6.

3) I & C adjusted and locked down the stop for closing of FCV-25-5.

4) The Technical Staff Test Group re-tested FCV-25-5.

5) The Instrument - & Control department will submit a change request to vendor Tech Manual 2998-4508 to provide more guidance on adjusting the valve travel and locking down the adjustment screw..

ADDITIONAL INFORMATION 1~ Com onent Identif'cat'on This event did not involve an NPRDS reportable component failure.

2 ~ Previous Similar Events r For a similar event, see LER N335-87-005, which pertains to excessive leakage past a containment purge valve on Unit. Nl.

II N/lc PO/IM 344A I943 I