ML18283B001

LER 1977-012-00 for Browns Ferry Nuclear Plant, Unit 2, Two Hydraulic Snubbers Were Found Inoperable During the Performance of Surveillance Instruction 4.6.H

ML18283B001
Person / Time
Site:	Browns Ferry
Issue date:	09/20/1977
From:	Fox H Tennessee Valley Authority
To:	O'Reilly J NRC/IE, NRC/RGN-II
References
LER 1977-012-00
Download: ML18283B001 (4)

Text

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TENNESSEE VALLEY AUTtdgRlTY 0

CHATTANOOGA. TENNESSEE 37401

'~~s-is<a September 20~ 1977 Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 230 Peachtree Street,'NW., Suite 1217 Atlanta, Georgia 30303 l

Dear Mr. O'Reilly:

TENNESSEE VALLEY AUTHORITY - BROtlNS FERRY NUCLEAR PLANT UNIT 2 DOCKET NO. 50-260 FACILITY OPERATING LICENSE DPR-52 - REPORTABLE OCCURRENCE REPORT BFRO-50-260/7712 The enclosed report provides details concerning two hydraulic

. snubbers which. were found inoperable. during the pe'rformance of Surveillance Instruction 4.6.H. This report, is submitted .in.

accordance with Browns Ferry unit 2 Technical Specifications, Section 6.7.2.b(2) .

Ve truly yours, TE VALLEY AUTHORITY

.S: ox ~

D tor of Power Production Enclosure (3) cc (Enclosure):

Director (3)

Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Dir'ector (40)

Office of Inspection, and Enforcement U.Si Nuclear Regulatory Commission Washington, DC 20555 An Equal Opportunity Ernpioyer

LICENSEE EVENT REPORT CONTROL BLOCK: ~

(PLE PRINT ALL REQUIRED INFORMATION) 1 . 6 UCEN SEE UCENSE EVENT NAME UCENSE NUMBER TYPE TYPE

]g89 'A L B R F -2 0 0 .

0 0 0 0 0 0 0 4 1 1 1 1 LOOOB~I

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14 15 ~

25, 26, 30 31 32 REPORT REPORT

'ATEGORY, TYPE SOURCE DOCKET NUMBER -EVENT DATE REPORT DATE 0

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Qll CONT L L 0 5 0 2 6 0 0 8 1 8 7 7 00 20 7 7 8 57 58 59 60 61 68 69 74 75 60

- EVENT DESCRIPTION i+2 (SEE ATTACHMENT) 8 9 80 80 8 9 80 (BFRO-50<<260/7712) 8 9 80 8 9 PEA E SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPLER MANUFACTURER VIDLATKIN

+27 ~BR,- ~E' A -N 0 E B 2 1 0 8 9 10 11' 12 ~ 17 44 47 I

CAUSE DESCRIPTION 3+6 8 9 Fluid leakage occurred at the oil fill lu s. The accessible snubber is a Ber en-80 I

Model HSSA size 30. 'We inaccessible snubber is a Grinoetl Modej F16-200 8 9 80

+10 89 FACILITY METHOD OF 80 STATUS  % POWER OTHER STATUS DISCOVERY DSCOVERY DESCRIPTION ZI Lal -

LOOool LaJ 8 9 10 12 13 45 46 80 FORM OF ACTIVffY COATENT RELEASED OF RELEASE AMOUNT OF ACTNITY LOCATTON OF RELEASE lB '~a ~a NA NA 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER . TYPE 'ESCRIPTlON l+B ~OO O ~E NA 8 9 11 12 13 80 PERS'ONNEL INJURIES 89 11 12 80 OFFSITE,CONSEOUENCES

~I5 NA 89 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION II'H NA 89 10 80 PUBLICITY 89 ADDITIONAL FACTORS 1+6 Similar failures were reported o'n BFRO-50-260/741T (Unit 2 7/31/74) 89 8<

ATTACHMENT BFRO 50"260/7712 EVENT DESCRIPTION (Continued)

During the performance of SI 4.6.H which was completed on August 18, 1977, two

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hydraulic snubbers were found inoperable. On August 13, 1977, with the unit shut down, r

one "inaccessible" snubber in the drywell on recirculation system piping was found with low fluid level. The snubber was made operable prior to reactor startup as I

required by Technical Specification 3.6.H,5.

On August 16,,1977, with the unit operating at approximately 447. power,'one "acces-sible" snubber on RHR piping was found with low fluid level. The snubber was made t

operable within the 72-hour period allowed by Technical Specification 3,6.H.3. This

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is a repetitive failure.

The tvo snubbers vere refilled vith fluid and leaking fillplugs were replaced.

JOD<SSN 9/2O/77

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