ML18283B417

LER 1977-017-00 for Browns Ferry Nuclear Plant, Unit 3, Primary Containment Isolation Valve 3-FCV-77-2A on Drywell Floor Drain Sump Pump Discharge Line Would Not Operate as Required by Tech Spec 3.7.D.L During Routine Operability Checks

ML18283B417
Person / Time
Site:	Browns Ferry
Issue date:	09/26/1977
From:	Fox H Tennessee Valley Authority
To:	O'Reilly J NRC/IE, NRC/RGN-II
References
LER 1977-017-00
Download: ML18283B417 (3)

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f.'o TENNESSEE VALLEY 26, 1977 Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 230 Peachtree Street, NM., Suite 1217 Atlanta, Georgia 30303 AUTHORlTY t CHATTANOOGA TENNESSEE >7401 0

gC'eptember

Dear Mr. O'Reilly:

r TENNESSEE VALLEY AUTHORITY - BROWNS PERRY NUCLEAR PLANT UNIT 3-DOCKET NO. 50-296 - PACILITY OPERATING LICENSE DPR-68 - REPORTABLE OCCURRENCE, REPORT BPRO-50-296/7717 The enclosed repoit.provides details concerning the'primary containment isolation valve 3-FCV-77-2A on the drywell floor drain sump pump discharge line which would 'not operate as required by Techni'cal Specification 3.7.D.l during routine operability checks. This report is submitted in accordance. with Browns Perry unit 3 Technical Specifications, Section 3.7.2.b;(2).

Very truly yours, TENNESSEE VALLEY AUTHORITY

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H. S. Pox Director of Power Production Enclosure cc (Enclosure):

Director (3)

Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Vashington, DC 20555 Director (40) - *

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

LILiLIVUCC CVCI'II I MCI UM I CONTROL BLOCK: (PLEA RINT ALL REOUIRED INFDRMATIONI)

LICENSEE LICENSE EVENT NAME LICENSE NUMBER .TYPE TYPE

+01 AL B R F 3 0 (f '0 00 0 0 0 0 '4 1 1 1 ~o 89 14 15 25 26 30 31 32 REPORT AEPOAT CATEGORY,, TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE

~ci corn' 0 9 2 2 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCFIIPTION, Z3 89 80 0+3 ee 80 0+4 8 9 80 8 9 3+6 8 9 PAMIE 80 SYSTEM CAUSE COMPONENT COMPOI4ENT CODE CODE COMPONENT CODE MANUFACTURER, 'GLATGN K~I LmJ'M "hJ lzJ 8 9 10 11 12 17 CAUSE. DESCRIPTION- h r 0+8 (SEE ATTACHMENT) 8 9 80

+09 8 9 80

+10 89 METHOD OF 80 OTHER STATUS OSCOVERY DISCOVERY DESCRIPTION 8 ~ 8 LzJ L(ALxJ 10 .12 13 44 LaJ 45, 46 utine 0 eration 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE HH 8 8 LJ Lzl 10 11 44 45 80 PERSONNEL EXPOSURES 89

~oo NUMBER 0

11 TYPE

~Z 12 13

'A DESCRIPTION 80 PERSONNEL INJURIES K4] LRLQL'Ql 89 11 12 80 OFFSITE CONSEQUENCES 1/5 NA 89 80 LOSS OR DAMAGE'O FACILITY TYPE DESCRIPTION

[Jz- NA 89 10 80 PUBLICITY NA 8 8 80 ADDITIONAL FACTORS Qe NA 89 eo

/19 89 80

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EVENT DESCRIPTION the drywell (Continued) floor drain J

0:

sump pump

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During routine operability checks, primary containment i:solation valve 3-FCV-77-2A on discharge line C

would not operate as required by Technical Specification 3.7.D.1.. Reactor operation was continued by deactivating the valve in the closed position as allowed by Technical Specification 3.7.D.2. .Repairs were made by fixing a cracked .air line oiler and replacement of a sticking flow I

air air operator.

I solenoid valve in the supply to the FCV-77-2A Previous solenoid failures axe reported on BFAO-7351W and BFAO-50-260/7414W; CAUSE DESCRIPTION (Continued) air line oilex 1osing lubrication to the solenoid control

'he supply cracked, thus 'I valve (FSV-77-2A). Lack of lubrication caused FSV-77-2A to fail to operate properly-therefore, the primary containment isolation valve was inoperable. The oilex was

- manufactured by Dyna-Quip O'X-11-6, mcdel M7; the solenoid valve is a Versa 4

model VSG"3521.

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