ML18283B431

LER 1977-008-00 for Browns Ferry Nuclear Plant, Unit 3, Relief Valve on Discharge of Standby Liquid Control Pump 3A Was Observed to Open at 1300 Psig Instead of Designed Setting of 1400 Psig & Stuck in Partially Open Position During Perform

ML18283B431
Person / Time
Site:	Browns Ferry
Issue date:	07/14/1977
From:	Fox H Tennessee Valley Authority
To:	Moseley N NRC/IE, NRC/RGN-II
References
LER 1977-008-00
Download: ML18283B431 (15)

Text

U S, NUCLEAR REGULATORv COMMISSION t NRC FoRM 195 IZ-7B)'p NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL DOC T UMB FILE NUMBER ETTER RIG INAL OPY DESCRIPTION 0 OTOR IZED UNCLASSIFIED TO:,'Norman C.Noseley PROP INPUT FORM ENCLOSURE FROM: Tennessee Valley Authority Chattanooga, Tenn H.S.Fox DATE OF DOCUMENT 7/14/77 DATE RECEIVED 7/18/77 NUMBER OF COPIES RECEIVED I e'OZOV@F>0 y,CKZOWLEDG<D PLANT NAIIE:Browns Ferry Nuclear Plant Unit No.3 RBT 7/19/77 Licensee Event Report (50-296/77-8) on 6/21/77 concevhing the releif valve on the discharge of standby liquid control pump 3A which opened at low pressure and stuck in a partially open position during conduct of SI 4.4.A.1.1p++5p FOR ACTION/I NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KRE~R/J.COLLINS ENGC Re~'FO RMATIO INTERNAL D IST Rl BUTION L T EXTERNAL DISTRIBUTION CONTROL NUMBER ACRS 16 SENT AS AT 4 F a h v',~~I"V I a, f t l.

Ol UTIOy 6~o~F'-'~)6-~9<~JUL 14]977~0 TENNESSEE VALLEY AUTHORITY CHATTANOOGA.

TENNESSEE 37401 Hr.Norman C.Hoseley irector U.S.Nuclear Regul ry Comndssion Office of Inspec on and Enforcement Region II 230 Peachtre Street, NM<, Suite 1217 Atlanta, rgia 30303~s...v.'-ZK!&TENNESSEE VALLEY AUTHORITY-BROGANS PERRY NUCLEAR PLANT UNIT 3-DOCKET'NO, 50-296-PACD ITY OPERATING LICENSE DPR&8-REPORTABLE OCCURRPNCE REPORT BPRO-50-296/778 The enclosed report is to provide details concerning the relief valve on the discharge of standby liquid control pump 3A vhich vas observed to open at 1300 psig instead of the designed setting of 1400 psig and which stuck in a partially open position during performance of SI 4.4.A.1;This report is submitted in accordance uith Brooms Fe~Technical Specifications Section,6.

This event occurred on Brovns Ferry unit 3.Very truly yours, TENNESSEE VALLEY AUTHORITY H.S.Pox Director of Power Production Enclosure (3)cc (Enclosure)

Director (3)Office of Hanagement Information a U.S.Nuclear Regulatory Commissio washington~

D.C.20555 Director (40)Office df Xnbgoqtion.~tag) gqgorceme U.S.Nuclear Regulatory Cd'sion Washington, D.C.20555 d Program Control.An Equal Opportunity Employer V~('he tlat hf N I r f(,N H N"I , hl't, I I,h fl I N f f, r f'It h'I I-Ih lh h J I Ih, (I Nl VI f I)hl N Irg'f gl h'P I h'Ol n ns 8i vi'~N~,',*NQJQ Qh PP I Nehlghg J N N Lt4~WtlGCO u>Fi~ba8

~LICENSEE EVENT REPORT 4~01 A L 7 89 CONTROL BLOCK: 1 LCENSEE NAME B R F 3 0 14 15 LCENSE NUMBER 0-0 0 0 0 0-0 EVEN~TYF+LCENSE TYPE 0 4 1 1 1 1 0 25 26 30 31 (PLEASE PRINT ALL REQUIRED INFORIVIATIDN)

REPORT REPORT CATEGORY TYPE SOURCE[os]coMv~7 8 57 58 59 60 EVENT DESCRIPTION

[Oar]7 8 9[OO~]7 89 top~]7 8 9 toom DOCKET NUMBER 0 5 0-0 2 9 6 68 (SEE ATTACHED)EVENT DATE REPORT DATE 0 6 2 1 7 7 69 74 75 80 80 80 80 7 89 QOQ 7 89 SYSTEM CAUSE CODE CODE COMPONENT CODE Icos~I~coo o~o ov A L v E x 7 8 9 10 11 12 17 CAUSE DESCRIPTION

[OOe]PRME COMPONENT SUPPLER N 43 44 C 7 1 0 LNI 47 48 80 80 7 89[OO~]7 89 (SEE ATTACHED)80 80 7 89 FACIUTY S'TATUS TO POWER OTHER STATUS~11~E~06 5 NA 7 8 9 10 12 13 FORM OF ACTIVITY COATENT RELEASED OF RELEASE AMOUNT OF ACTIVITY~a~H~a NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION P~~j~oo o~o 7 89 11 12 13 PERSONNEL IN JURIES NUMBER DESCRIPTION

~4~oo o 7 89 11 12 OFFSITE CONSEQUENCES 7 89 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION

~a 7 89 10 PUBLICITY 7 89 ADDITIONAL FACTORS tj1I 7 89 7 89 NAME'ETHOD OF DISCOVERY B 44 45 46 44 45 NA NA NA NA NA NA NA PHONE'ISCOVERY DESCRIPTION NA LOCATION OF RELEASE NA 80 80 80 80 80 80 80 80 80 80 GPO 001~007 3~q~>v~E'$~

C"'NORTHERN STATES POWER COMPANY 00/t t'Il M I NNKA POLI S.'M I NN 5 SQTA'55401 l)gf July<<13, 1977 t Mr J G Keppler, Director, Region III Office of'nspection 6 Enforcement U S,Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Mr Keppler:

A k PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No.50-282 License No.DPR-42 Ino erabilit of 812 AUG'ischar e Valve The Licensee Event Report for this occurrence is reproduced on the back of this letter.Enclosed are three copies.Yours very truly, LOMay, PE Manager of Nuclear Support Services 4 LOM/LLT/deh cc:director, IE, USNRC (30)Director, MIPC, USNRC (3)G Charnoff MPCA Attn: J W Ferman, k I-over-LICENSEE EVENT REPORT CONTROL BLOCK: (PLEASE PRINT ALL REQUIRED INFDRMATIDN)

LICENSEE NAME Pg M NP 1 N 1 0 7 89 14 15 LICENSE NUMBER 0-0 0 0 0 0-0 0 EVENT TYPE LCENSE TYPE 4 1 1 1 1~0 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE[oagcowr~L L 7 8 57 58 59 60 DOCKET NUMBER EVENT DATE 0 5 0-0.28 2 0 61 8 7 7 61 68 69 74 REPORT DATE~OZ EJVV~J 80 75 EVENT DESCRIPTION Jog'urin hot shutdown, while feeding the steam generators with No.12 Auxiliary 7 89 80 I Feedwater Pum'he um dischar e valve motor o erator failed.The redundant 7 89[oO~]7 8 9[oas)7 8 9 foOg 7 8 9 SYSTEM CAUSE CODE CODE-COMPONENT CODE~07~OH E'V A L V 0 P 7 8 9 10 11 12 17 CAUSE DESCRIPTION

~08 PRME COMPONENT SUPPUER 43 COMPONENT MANUFACTURER L 2 0 0 44 47 48 80 80 80 80 7 8 9 Qo I a random failure).Lead was repaired and valve tested for operabilit

.80 OTHER STATUS 7 8 9[iso]7 89 FACILITY STATUS POWER~G~00 0 NA 7 8 9 10 12 13 FORM OF ACTIVE COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY@~2 Z Z NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE, DESCRIPTION

~13~00 0~Z NA 7 89 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION

~14~00 0 NA 7 89 11 12 OFFSITE CONSEQUENCES Qqg NA 7 89 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION

~1 Z NA 7 89 10 PUBLICITY NA 7 89 METHOD OF DISCOVERY 44 45 NA 44, 45 46 DISCOVERY DESCRIPTION LOCATION OF RELEASE 80 80 80 80 80 80 80 80 80 ADDITIONAL FACTORS PQB, 7 g 9~~Qgg 7 88'a A.A.Hunstad lOI~gHS~3 g0gd 80 80 PHONE.612 388-4767 ,~GPO IS1 OeT

~~~y~/~4'" Event Descri tion During performance of SI 4.4.A.l, the relief valve on the discharge of standby liquid control pump 3A was observed to open at 1300 psig instead of the designed setting of 1400 psig and stuck in a partially open position.The relief valve was removed from the system, disassembled, and the plug, plug guide, and seat were replaced.The valve was tested and was observed to open at 1400 psig.It was then re-installed in the system, and SI 4.4.A.l was performed satisfactorily.

All redundant systems were available.

A similar event occurred on this same pump on January 22, 1977, when another relief valve which was subsequently replaced, also opened prematurely.(BPRO-50 Q9$/77g)Cause Descri tion The inside surface of the plug guide and outside surface of the plug both had a scored area of approximately one-quarter inch square.The scored places caused the relief valve to stick in the open position.It is not known what caused the valve to open at a pressure lower than designed;because after the valve was removed from the system, before parts were replaced, it was tested and found to open at 1400 psig.It is possible that during the throttling process there was a pressure spike s Ij causing the valve to lift at its set pressure and stick in the open position.The scoring appears to have been caused by foreign material which worked in the small clearance between the plug and plug guide.The relief valve is a"Crosby" 1 x 2 style JMWK.Replacement parts were installed as indicated in the"Event Description".

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• O<VTIQy~'.'~as-is<~TENNESSEE YALLEY AUTHORITY CHATTANOOGA.

TENNESSEE 37401 Zu1y 14, 1977 Mr.Norman C.Moseley, Director U.S.Nucleax'egulatory Commission Office of Inspection and Enforcement Region II 230 Peachtree Street, NW., Suite 1217 Atlanta, Georgia 30303

Dear Mr.Moseley:

Revelatory Docket pg4 TENNESSEE VALLEY AUTHORITY-BROWNS FERRY NUCLEAR PLANT UNIT 3-DOCKET NO.50-296-FACILITY OPERATING LICENSE DPR-68-REPORTABLE OCCURRENCE REPORT BFRO-50-296/778 The enclosed report is to provide details concerning the relief valve on the discharge of standby liquid control pump 3A which was observed to open at 1300 psig instead of the designed setting of 1400 psig and which stuck in a partially open position during performance of SI 4.4.A.l.This report is submitted in accordance with Browns Ferry Technical Specifications Section 6.This event occurred on Browns Ferry unit 3.Vex'y 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 f (, Qg>~An Equal Opportunity Employer xodo)xk(f,yf)Iaaf'l) fra.".Xo',l.x"!aoiBRi.'x Ioi)g'xoSG Ju,"',,!)i XBQIc)rlui

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REPORT REPORT CATEGORY TYPE SOURCE IVD1]coNT~L L 7 8 57 58 59 60 EVENT OESCRIPTION, DOCKET NUMBER 0 5 0-0 2 9 6 68 61 EVENT DATE REPORT DATE 0 6 2 1 7 7 69 74 75 t 80[oO~]7 89 I 7 89 Qp~]7 8 9~05 7 8 9 Jog OTHER STATUS NA AOOITIONAL FACTORS Pge 7~89 7 89 7 89 SYSTEM CAUSE CODE CODE COMPONENT CODE[QQ7]~EEF F~E EV A L V E E 7 8 9 10 11 18 17,, CAUSE OESCRIPTION Jog 7 89 tOOI 7 89@co]7 89 FACIUTY, STATUS%POWER E~OS E 7 8 9 10 18 13 FORM OF ACTIVITY COATENT RELEASED OF RELEASE AMOUNT OF ACTIViTY ED>M L~J NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

~SHOO O E 7 8 9 11 18 13 PERS'ONNEL IN JURIES NUMBER DESCRIPTION

[iia]~oo o 7 89 11 18 OFFSITE CONSEQUENCES Q~g 7 89 LOSS OR OAMAGE TO FACILITY TYPE DESCRIPTION 7 89 10 PUBLICITY cn 7 8 9 PRME COMPONENT SUPRXA N 43 44 COMPONENT MANUFACTURER C 7 1 0 (SEE ATTACHED)METHOD OF DISCOVERY B 44 45 46 44 45 NA NA NA NA NA NA NA (SEE ATTACHED)N 47 48 06COVERY DESCRIPTION NA LOCATION OF RELEASE NA 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 NAME: PHONE: GFO eeT~eeV t,MP~',"~Event Descri tion During performance of SI 4.4.A.1, the relief valve on the discharge of standby liquid control pump 3A was observed to open at 1300 psig instead of the designed setting of 1400 psig and stuck in a partially open position.The relief valve was removed from the system, disassembled, and the plug, plug guide, and seat were replaced.The valve was tested and was observed to open at 1400 psig.It was then re-installed in the system, and SI 4.4.A.l was performed satisfactorily.

All redundant systems were available.

A similar event occurred on this same pump on January 22, 1977, when another relief valve which was subsequently replaced, also opened prematurely.(BFRO 50 Q9$/77[)Cause Descri tion The inside surface of the plug guide and out'side surface of the plug both had a scored area of approximately one-quarter inch square.The scored places caused the relief valve to stick in the open position.It is not known what caused the valve to open at a pressure lower than designed;because after the valve was removed from the system, before parts were replaced, it was tested and found to open at 1400 psig.It is possible that during the throttling process there was a pressure spike causing the valve to lift at its set pressure and stick in the open position.The scoring appears to have been caused by foreign material which worked in the small clearance between the plug and plug guide.The relief valve is a"Crosby" 1 x 2 style JMMK.Replacement parts were installed as indicated in the"Event Description".

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