ML18283B342

Licensee Event Report Concerning MSIV 1-38 Which Closed in 1 Second Exceeding Limiting Condition of Operation

ML18283B342
Person / Time
Site:	Browns Ferry
Issue date:	05/31/1978
From:	Fox H Tennessee Valley Authority
To:	O'Reilly J NRC/IE, NRC/RGN-II
References
Download: ML18283B342 (8)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM < RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-296 REC: OREILLY J P DOCDATE: 05/31/78 NRC DATE RCVD: 06/07l78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT <RO 50-296/78-013) ON 05/13/78 CONCERNING WHILE SURVEILLANCE TESTINGS MSIV 1-38 CLOSED IN 1 SECOND EXCEEDING LIMITING CONDITION OF OPERATION SPECIFIED IN TECH SPEC TABLE 3. 7. Ar CAUSED BY LOW OIL IN S/N 12-919 DASHPOT... W/AT PLANT NAME:BROWNS FERRY UNIT 3 REVIEWER IN1TIAL: X JM DISTRIBUTOR INITIAL:QQ woeoewww++o++++ww DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS

<DISTRIBUTION CODE A002)

FOR ACTION: BR CHIEF ORBN3 BC44W/4 ENCL INTERNAL: /ENCL 'NRC PDR++W/ENCL I 5 E++W/2 ENCL MIPC4+W/3 ENCL I 5 C SYSTEMS BR4~W/ENCL EMERGENCY PLAN BR4~W/ENCL NOVAK/CHECK++W/ENCL EEB>~W/ENCL AD FOR ENG+%W/ENCL PLANT SYSTEMS BR+<W/ENCL HANAUER~~W/ENCL AD FOR PLANT SYSTEMS'>W/ENCL AD FOR OPER TECH44W/ENCL REACTOR SAFETY BR<~W/ENCL ENGINEERING BR4+W/ENCL VOLLMER/BUNCH+>W/ENCL KREGER/J. COLLINS4+W/ENCL POWER SYS BR+4W/ENCL K SEYFR IT/IE>+W/ENCL EXTERNAL: LPDR S ATHENS, AL4<W/ENCL TIC~~W/ENCL I

NS C4 +W/ENCL ACRS CAT B>+W/16 FNCL COPIES NOT SUB".1ITTED PER REGULATORY GUIDE 10.1 DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 781600297 SIZE: iP+iP+iP THE END 44%%%%%%% 4%

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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 87401 Me 311978 Nr. James P, O'Rei y, Director U.S. Nuclear Regu tory Commission

'Office of Inspec on and Enforcement Region II 230 Peachtree S r'eet, NM., Suite 1217 C3 ~

Atlanta, Georg'a 30303 o

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Dear Nr. O'Re ly:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT V >>

DOCKET NO. 50-296 - FACILITY OPERATING LICENSE DPR REPORTABLE OCCURRENCE REPORT BFRO-50-296/7813 The enclosed report provides details concerning NSIV 1-38 rihich closed in 1 second exceeding the limiting condition of operation specified in Technical Speci ficatioh table 3.7.A,during normal operation while surveillance testing. This report is submitted in accordance <vith Brows Ferry unit 3-Technical Specification 6.7.2.b.(2).

Very truly yours, TENNESSEE VALLEY AUTHORITY H. S. Fox Director of Power Production Enclosure (3) cc (Enclosure):

Director (3)

Office of Itanagement Information and Progr Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Director (40)

Office of Inspection and Enforcemen U,.S. Nuclear Regulatory Commission Was ton DC 20555 An Equal Opportunity Employer

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ICENSEE EVENT REPORT O'ONTROL BLOCK:

Ia Qi (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I LBRF3Q200 Qa~

~0 A 0 0 0 0 0 0 0 Q3 4 1 1 1 1 QE 7 8 0 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T

~01 ~LOB 0 5 0 0 0 2 9 6 Oy 0 5 1 3 7 8 B 0 5 3 1 QB 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 010 Durin normal o eration while surveillance testin , MS?V 1-38 closed in 1 second exceeding th'e limiting condition of operation specified in,T.ST table 3 '.A.

The valve was immediately closed to ailow continued operation under T.ST 3 '.D.2 ~

~0 5 No significant event resulted, There was no effect on public health or safety.

B Previous occurrences were BFR0's 259/742, 7412, 7438 and 7450 and BFRO's 26 7412 and 7423 ~

~08 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~00 ~CD OTE LJ 073 LJ 073 V A L, V 3 X OTR ~F QEE, ~D Q78 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION 077 LERIRO REP0RT ACTION .FUTURE EVENT YEAR

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22 EFFECT

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23 SHUTDOWN

~<1 24 REPORT NO.

3 26

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~03 28 ATTACHMENT CODE 29 NPRDX TYPE

~L 30 PRIME COMP.

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31

~0'1 32 NO.

COMPONENT TAKEN ACTION 33 I~QIB 34 ON PLANT MQ20 35

'02 METHOD 36 37 0

HOURS i+22 0 0 0 40 SUBMITTED 41 Y Q23 FORM SUB.

~YQ24 42 SUPPLIER

~NQ25 43 44 MANUFACTURER A 5 8 5 47 Q2B CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 027 0 The Atwood and Morrill valve ty e 01036 S/N 12-919 dashpot was found .low on oil.

The dash ot was refilled with oil and retested and met testin re uirements 3

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~O 80 8

0 7 9 FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q32 CC3 s F 280 ACTIVITY CONTENT 0 4 5 29 N/A ~BQ31 45 46 Operator observation 80

~is RELEASED OF RELEASE AMOUNT OF ACTIVITYQ3 N/A LOCATION OF RELEASE Q L~JO>> L~JO34 ,

7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~00 0 Q37 3 Q38 N/A 7 8 9 11 12 13 80 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE To FACILITY TYPE DESCRIPTION Q43 L~IO42 N/A 7 8 9 10 80 ISSUED PUBLICITY DESCRIPTION ~ NRC USE ONLY A,'HONE.

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0 ~NO44 N 8 9 10 68 69 80 a 0

NAME OF PREPARER a 13

SUPPLEMENTARY REPORT BFRO-50-296 7813

,I During normal operation while performing S.I. 4.1.A.ll, it was ound that the outboard MSIV FCV 3-1-38 closed in 1 second which is not within T.S. Limit of 3 to 5 seconds.

The valve was placed in the closed position per T.S. 3.7.D.2. The inboard MSIV FCV 3-1-37, which is on the same steamline, was tested per S.I. 4.1.A.ll and was within the T.S. limit of 3to 5 seconds. The malfunction of the valve was due to a low oil level in the dashpot, cylinder. The cause of the low oil level is unknown.

There were no noticeable cracks or loose fittings to account for the loss of oil.

The valve was refilled with oil and retested per S.I. 4.1.A.ll and found operable.

There was no significant occurrence that took place as the result of this event, and there was no effect on public health or safety.

JGD:SGS 5/31/78

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