ML18283B420

LER 1977-013-00 for Browns Ferry Nuclear Plant, Unit 3, SLC Pump 3A Discharge Relief Valve Lifted at 1275 Psig During Surveillance Testing When Pump Was Started Against Throttled Test Valve Set at That Pressure

ML18283B420
Person / Time
Site:	Browns Ferry
Issue date:	08/19/1977
From:	Fox H Tennessee Valley Authority
To:	O'Reilly J NRC/IE, NRC/RGN-II
References
LER 1977-013-00
Download: ML18283B420 (7)

Text

U.S. NUCLEAR REGULAT MISSION Do ET NUMB R NRC FORM 195 I2.76 I FILE NUMBER

'"',<,NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL FROM: DATE OF DOCUMENT TO:

Tennessee Valley Authority 8/19/77 Mr. James P O'Reilly Chattanooga, TennE DATE RECEIVED H+ ST Fox 8/26/77 0 LETTER 0 TOR IZ E D NO PROP INPUT FORM NUMBER OF COPIES RECEIVED OORIGINAL 0 UN C LASS F I E D I

OCOPY DESCRIPTION ENCLOSURE Licensee Event Report (RO 50-296/7713) on 7/25/77 concerning the SLC pump 3A discharge g <<hC~g%I g( gpg09EED<<D relief valve which lifted at 1275 psig during surveillance testing when the pump was started against a throttled test valve set at that pressure+ ~ ~ ~ ~

PLANT NAME: Browns Ferry Unit No 3 R JL 8/26/77 (1-P) (1-P)

NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS E I FOR ACTION/INFORMATION INTERNAL D ISTRI BUTION EXTERNAL DISTRIBUTION CONTROL NUMBER 7725 ACRS 16 SENT AS AT B

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'TENNESSEE VALLEY AUTHORITY O m CHATTANOOGA. TENNESSEE 37401

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August 19, 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

Dear Mr. O'Reilly:

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.gerbil $L TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT 3 DOCKET NO. 50-296 - FACILITY OPERATING LICENSE DPR-68 REPORTABLE OCCURRENCE REPORT BFRO-50-296/7713 The enclosed report provides details concerning the SLC pump 3A discharge relief valve which lifted at 1275 psig during surveillance testing when the pump was started against a throttled test valve set at that pressure.

This report is submitted in, accordance with Browns Ferry Technical Specifications Section 6. This event occurred on Browns Ferry unit 3.

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

Director (3)

Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Director (40)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 An Equai Opportunity Employer

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OLICENSEE EVENT REPORT ~

CONTROL BLOCK: [PLEASE PRINT ALL REQUIREO INFORMATION) 6 LCENSEE LCENSE EVENT NAME LCENSE NUMBER TYPE TYPE

@01 A L B R F 3 0 0 0 0 0 0 0 0 0 4 1 1 1 1 LOOI

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7 88 14 15 25 28 30 31 32 RDTOIIT REPORT CATEGORY TYPE ~ SOURCE OOCKET NUMBER EVENt OATE REPORI OATE

[QDij CQN'T L ~L 0 5 0 0 2 9 6 0 7 2 5 7 7 7 8 57 58 59 80 61 68 69 74 75 80 EVENT DESCRIPTION Q~ 2 During surveillance testing, the SLC pump 3A dischar e relief valve lifted at 1275 7 89 80

[OD3] si when the um was started a ainst a throtthAd test valve set at that ressure 7 89 80 du de m 7 8 9 80

[pg~] daily thereafter until the inoperable component was repaired. This is a repetitive 7 8 9 80

[ODg occurrence The valve was re aired and retu d t se 7 8 9 80 SYSTEM CAUSE COOE COBE COMPONENT COBE

[oDTI LEEEI ~E v 4 L v E N C 7 1 0 N 7 8 9 10 11 12 17 43 44 47 48 CAUSE OESCRIPTION Qg A crosb valve and a e Co 1 x 2 st le val e a 1 d 7 89 80 because the di,sc guide was galled with the valve disc.

7 8 9 80

~10 7 89 FACIUTY METHOD OF 80 STATUS POWER OTHER STATUS OISCOVERY OISCOVERY OESCRIPTION

[ii~j E ~o NA NA 7 8 9 . 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT RKLEASEO OF REI.EASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Qg ~s z, NA NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION IDTVI ~oo NA 89 11 12 13 80 PERSONNEL INJURIES NUMBER OESCRIPTION

~4 ~oo 7 89 11 12 80 OFFSITE CONSEQUENCES 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION

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7 89 10 NA 80 PUBLICITY 7 89 80 AOOITIONAL FACTORS 7

$ 89 1 8 Previous LER's and dates were BFRO-50-296/771 1-22-77 BFRO-50-296/778 6-21-77 80 Q~g 7 89 80 NAME: PHONE:

GPO GET ~ GOT

0 ATTACHMENT

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I BFRO-50-296/7713 EVENT DESCRIPTION (Continued) 7 day limits (BFRO-50-296/7713)

RECEIVED DOCUt'IEHT PRCCESSIHG UHIT

$ 9(f AUG R5 PM 5 4d