ML18283A992

LER 1978-006-00 for Browns Ferry Nuclear Plant, Unit 2, Check Valve 2-73-603 in High-Pressure Coolant Injection System Was Found in Open Position During Maintenance Inspection After Failing Local Leak Rate Test

ML18283A992
Person / Time
Site:	Browns Ferry
Issue date:	05/05/1978
From:	Fox H Tennessee Valley Authority
To:	O'Reilly J NRC/IE, NRC/RGN-II
References
LER 1978-006-00
Download: ML18283A992 (8)

Text

REGULATORY INFORNATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-260 REC: OREILLY J P ORG: FOX H S. DOCDATE: 05/05/78 NRC TN VALLEY AUTH DATE RCVD: 05/09/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR i LICENSEE EVENT REPT 078-006 ON 3/25/78 CONCERNING CHECK VALVE 2-73-603 IN ENCL i HIGH-PRESSURE COOLANT INJECTION SYSTEI"l WAS FOUND IN OPEN POSITION RESULTS NO HAZARD TO PUBLIC HEALTH OR SAFETY.

PLANT NAME: BROWNS FERRY UNIT 2 REVIEWER INITIAL: XRS DISTRIBUTOR INITIAL:

ssss+w+++>++~~++w+4~~~ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS

( DISTRIBUTION CODE A002)

FOR ACTION: BR CHIEF LEAR 4W/4 ENCL INTERNAL: EG FILE++M/E CL NRC PDR+4M/ENCL NIPC++W/3 ENCL SCHROEDER/I PPOL I TO4 +W/ENCL HOUSTON++M/ENCL NOVAK/CHECK++M/ENCL EEB+~~W/ENCL KN I GHT<4 W/ENCL BUTLER+4W/ENCI HANAUER4+W/ENCL TEDESCO>~W/ENCL E I SENHUT+4 W/ENCL BAER++W/ENCL SHAG+>W/ENCL VOLLEYER/BUNCH++W/ENCL KREGER/J. COLL INS~4l VENCL ROSA++M/ENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR S ATHENS AL+<W/ENCL TIC++W/ENCL I

NS C4~4~W/ENCL ACRS CAT B+>W/ih ENCL PFR COPIES NOT SUB~IITXED

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REGULATORY GUIDE 10.1 DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 78i300004 SIZE: iP+2P HHf+%0l+%%%%+SHHM%%%%%%%%%%%%%%%%%%%% THE END

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TENNESSEE VALLEY AUTHORITY GHATTANooGA. TENNEssEE 37401 MAY q )978 r v:,

Mr. J'ames P. O'Really, Director U.S. Nuclear Regulatory Commission j~:

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CC O'C Office of Xnspection and Enforcement ~cn;a Region XX j>1 Kl 230 Peachtree Street~ Ef.> Suite 12l7 CD AtLanta, Georgia 30303 C7 rcc CA Deax Mr. O'Re~:

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'KINESSEE VAXL1KAVKORXTY BEES XZRHY IjlUCLEAR PXAIG UNXT DOCKET NO 50 260 + PACXXZTY OPEHATIKr LICENSE DPR+52 REPORTAKE OCCURRENCE REPORT 3PRO 50-260/786 ghe enclosed report provides details concerning check valve 2-73-603 in the high-pressure coolant injection system that was found in open position during the maintenance inspection after failing a local leds rate test.

Tbis xeport is submitted in accox'dance srlth 3h'cans Perry unit 2 Technical Spec9.fications, Section 6.7.2.'b. (2) .

Very tr~ yours, TENNESSEE VAIZZY AUTHORXTY E. 8. Pox Director of Power Production Enclosure (3}

cc (Enclosure):

Director Office of Management Xnformation and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Director {40}

Office of Xnspection and. Enforcement U.S. Nuclear Regulator Comission Washington,'DC 20555 781300004 An Equal Opportunity Employer

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.771 LfCENSEE EVENT REPORT

, p CONTRO'-. SLOE: IPLEASE PRINT OR TYPE EQUIRED INFORMATION) 6 O 1 8 9 A L B R LICENSEE CODE P 2 14 P2 15 0 0 - 0 0 0 LICENSE NUhlBER 0 0 0 0 26 Qs 26 fp 1 1 LICENSE TYPE 1 1 30 Qn~ Q 57 CAT 68 CON'T

" " 0 5 0 0 0 2 6 0 07 0 3 2 5 7 8 0 5 0 5 7 8 09 o 1 SOURCE ~LQs 8 8 60 61 DOCK ET N Vhi 8 E R 68 69 EVENT DATE 74 76 REPORT DATE 80 EVENT DESCRIPTION ANO PROBABI.E CONSEQUENCES 010 o 2 Following failure of local leak x'ate test (Reference Technical Specifications performed

~O3 4. 7 .A. 2 . g and h) va lve maintenance was . During the maintenance inspection~

check valve 2"73-603pin high~ zesusezcoolant injection systempwas Bound in open position. A redundant valve was operable. 'Zhere was no hazard to the T7ublic health 6 or safety. (See attached sheet. )

~O8 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE, COMPONENT CODE SVBCODE SUBCODC

~CE Q11 ~B Q12 ~C Q13 V A L V E E Q14 ~C Qns ~A Qs 7 8 9 1O 12 13 18 I9 20 SEQUENTIAL OCCURRENCE

'YPE REPORT REVISION QET LERIRO REPoRT EVENT YEAR

~7/ ~ ~00 REPORT NO.

6 ~~ ~03 CODE

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'4 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHhlENT NPRD4 PRIhlE COMP, COMPONENT TAKEN ACTION GN PLANT hIETHOD HOURS 022 SUBMITTED FORM BVB. SUPPLIER hlANUFACTURER

~Bpls ~Zpfs ~ZQ20 '~ZQ21 0 0 0 0 ~Yfp23 ~NQ24 ~NQ29 0 2 6 Qs 33 34 35 36 31 40 41 42 43 47 CAUSE OESCRIPTION ANO CORRECTIVE ACTIONS 27 o The cause of the open position was a dimensional errox in component interference clearance. The corrective action t'aken was to machine the valve component to provide interference clearance. ~ I 3

The valve data is: Nfg: Crane Chapman .'ize; 20 inch. Type: Swing check; 4 Rating l50 lb ~

7 8 9 80

~ps FACILITY ' h'IETHOD DF STATUS POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 1 5 NQ 28 0 0 0 9 N/A ~BQ31 45 46 Nozmal maintenance 80 ACTIVITY CONTENT ,f RELEAS'EO OF RELEASE AMOUNTOF ACTIVITY LOCATION OF RELEASE EKI 7 8 9

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Q ufp IO 44 45 N/A PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION A3

~00 0 Q31 Z Qss N/0 7 & 9 11 12 13 80 PERSONNEI. INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACIUTY 43 9

7 8 9 Io BO PUBLICITY

~5 NRC USE ONLY IS" UED DESCRIPTION N/A o ~N Qnn 2

8 9 10 68 69 80 0

NAME OF PREPARER PHONE:

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SUMMARY

OF VALVE 2-73-603 ON UNIT 2 FAILURE TO CLOSE Following failure of local leak rate test (Reference Technical Specifications 4.7.A.2.g and h) valve maintenance was performed. During maintenance inspection of high-pressure injection coolant system, check valve 2-73-603 was found in open position. Investigation found the cause of failuxe to be a mechanical interference between t'e end caps and t'e hinge pin.

Coxrective action was taken by machining the end caps to provide an interference clearance. Following corrective action, the valve operability was checked and found wi.thin acceptable limi,ts.

It should be noted another valve FCV 2-73-23, which was operable, is upstream of the valve in question. Under this consideration no apparent safety function was inhibi.ted.

JGD: SGS s/s/78