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)

Text

'r~oiuTloh O'~~e-19<~0 TENNESSEE VALLEY AUTHORlTY t CHATTANOOGA TENNESSEE>7401 f.'o gC'eptember 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

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~~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)-*~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)

+01 LICENSEE NAME AL B R F 3 0 (f 89 14 15 REPORT AEPOAT CATEGORY,, TYPE SOURCE~ci corn'8 57 58 59 60 61 EVENT DESCFIIPTION, Z3 89 0+3 ee 0+4 8 9 LICENSE.TYPE 1 1 1 DOCKET NUMBER EVENT DATE 68 69 LICENSE NUMBER'0 00 0 0 0 0'4 25 26 EVENT TYPE~o 30 31 32 REPORT DATE 0 9 2 2 7 74 75 80 80 80 80 8 9 3+6 8 9 SYSTEM CAUSE CODE CODE K~I LmJ'M"hJ 8 9 10 11 12 CAUSE.DESCRIPTION-0+8 (SEE ATTACHMENT) 8 9+09 8 9+10 COMPONENT CODE h r 17 PAMIE COMPONENT lzJ COMPOI4ENT MANUFACTURER,'GLATGN 80 80 80 OTHER STATUS 89 LOSS OR DAMAGE'O FACILITY TYPE DESCRIPTION

[Jz-NA 89 10 PUBLICITY NA 8 8 ADDITIONAL FACTORS 89 LzJ L(ALxJ 8~8 10.12 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY HH LJ Lzl 8 8 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

~oo 0~Z'A 89 11 12 13 PERSONNEL INJURIES K4]LRLQL'Ql 89 11 12 OFFSITE CONSEQUENCES 1/5 NA METHOD OF OSCOVERY LaJ., 44 45, 46 44 45 DISCOVERY DESCRIPTION utine 0 eration LOCATION OF RELEASE 80 80 80 80 80 80 80 80 Qe 89/19 89 NA eo 80 0: '}EVENT DESCRIPTION (Continued)

'\J During routine operability checks, primary containment i:solation valve 3-FCV-77-2A on C*the drywell floor drain sump pump discharge line 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 I solenoid valve in the air supply to the FCV-77-2A air operator.Previous solenoid failures axe reported on BFAO-7351W and BFAO-50-260/7414W; CAUSE DESCRIPTION (Continued)

'he air supply line oilex cracked, thus 1osing lubrication to the solenoid control'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.I