ML18142B244

LER 1976-027-00 for R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line

ML18142B244
Person / Time
Site:	Ginna
Issue date:	01/04/1977
From:	White L Rochester Gas & Electric Corp
To:	O'Reilly J NRC/IE, NRC Region 1
References
LER 1976-027-00
Download: ML18142B244 (12)

Text

U.S.NUCLEAR REGULATORY C ISSION NRC FORM 195 I2-76)~4 NRC DISTRIBUTION FQR PART 50 DOCKET MATERIAL DOCKET NUMBER 50-244 FILE NUMBER INCIDENT REPORT TO: James P.0" Reilly FROM:GE Rochester N.X.14649 Z,.D.White Jr.DATE OF DOCUMENT~1-4-77 DATE RECEIVED 1-10-77 LETTE R Q IP INAL OPY 0 NOTOR IZE D NCLASSIFIED PROP INPUT FORM NUMBER OF COPIES RECEIVED 30 copies DEscRIP7IDN Ltr.Trans The Following:

Licensee Event Report (RO-$0-244/76-on 12<<16-76 concerning liqui>flowing through insulation on 2" let<azn<iversion lineue to pinhole leak between.pipe an<elbow...7)PLANT NAME: ROCHESTER G R.E GINNA UNIT$1 D0 NOT REMOVE ACKNOWLFDGF~

NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J, COLLINS FOR ACTION/INFORMATION BRANCH CHIEF!W 3 CYS FOR ACTION LIC", ASST'g CYS ACRS CYS+'EG FI DR I6cE (2 MIPC SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES CASE BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SHAO VOLLMER/BUNCH KREGER/J COLLINS INTERNAL D ISTRI BUTION LPDR!IC: N~EXTERNAL ISTR IBUTION CONTROL NUMBER J~J WI~~~'I I r c TT~~~~

~~e'<ZiZZis n'>VZiÃH HH~D\H.-~.j,i!!i ihip'/ge Uleto Docket Ite Zk irZH'Hii lii.'IiIHII ROCHESTER GAS AND ELECTRIC CORPORATION

~89 EAST AVENUE, ROCHESTER, N.Y.14649 LEON D.WHITE.JR.VICE PRE5IOENT OOGREEED PSIIRC nuary 4, 1977 7 EL EPHI ON E AREA COOE 7I5 546.2700 oI~I~<II'V.S.IIVCEEAR REGlMTOR COMMISSION I Sodion 6 Mr.James P.O'Reilly, r I5 U.S.Nuclear Regulatory Co on Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 CQ~~,'i O'gag g

Subject:

Reportable Occurrence 76-27 (30-day report), Leak in letdown diversion line R.E.Ginna Nuclear Power Plant, Unit No.1 Docket No.50-244

Dear Mr.O'Reilly:

In accordance with Technical Specifications, Article 6.9.2b, the attached report of Reportable Occurrence 76-27, 30-day, is hereby submitted.

Two additional copies of this letter and the attachment are enclosed.I Very truly yours,-L.D.White, Jr.Attachment cc: Dr.Ernst Volgenau (30)Mr.William G.McDonald (3)r 2RP H

'W LER 76-27/3L'LICENSEE EVENT REPOR'Qog N 7 89~01 CON'T 7'8 CONTROL BLOCK: 1 UCEN SEE NAME Y R E G 1 0 0 14 15 REPORT REPORT 57 58 , 59 60 , 61 EVENT TYPE LICENSE NUMBER 0 0 0 0 0-0 0 4 1 1 1 1~03 30 31 32 25 26 EVENT OATE 1 2 1 6 7 6 REPORT CATE 0 1 0 4 7 7 OOCKET NUMBER 0-0 2 4 4 74 75 68 69 80 (PLEASE PAINT ALL AEOVIAED INFORMATION) 7 8 9 I diversion line., Upon return to steady state letdown condition, line was isolated.7 89 t00j4 (Reportable Occurrence 76-27,.30-day).7 8 9 COOM 7~8'9 Ioag 7 8 9 FAME'YSTEM CAUSE COMPONENT COBE COOE COMPONENT CODE SUPPLER VCULTKIN Pop>~CG.~B P I P E X X~N K 0 5 5 N 7 8 9 10 11 12 17 47 48 CAUSE DESCRIPTION COOM A pinhole leak was found in socket weld between pipe and elbow.Weld was built up COMPONENT MANUFACTURER 43 44 EVENT DESCRIPTION Qpg During normal rounds operator noticed liquid coming through insulation on.2" letdown.80 80 80 80 80, 7 8 9 80[opg]in area of leak, and a visual inspection performed upon return of system to service ver 80 7 89 FACIUTY STATUS 55 POWER gg~E~io o 7 8 9 10'2 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE@~3 B~d 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION

~3~OO O~B 7 89 11 12 13 PERSONNEL INJURIES[iran)~0~0 0 7 89 11 12 METHOO OF DISCOVERY OISCOVERY OESCRIPTION b Operator making rounds 44 45 46 OTHER STATUS NA 80 LOCATION OF RELEASE AMOUNT OF ACTIVITY NA NA 44 45 80 NA 80 NA 80 OFFSITE CONSEQUENCES

.~15 ,NA 7" 89 80 Qqg ified leak was stopped.This section-of line will be (cont'd.under Additional Factors), I 7 89 LOSS OR DAMAGE TO FACILITY, TYPE OESCRIPTION K~1 L~I 7 89 10 PUBLICITY 7 89 NA NA 80 80 80 ADDITIONAL FACTORS'I Q~g (cont'd.from.Cause Description) replaced at next refueling shutdown to remove weld 7 89.which had been leaking.CAR 1111 was issued to document this corrective action.80 7.89 80 ames Witte/D.Hamelink PHDNE 7 1 6 546 2700, ext~29 1-2 1 S GPO dd'I 667 t:-g~0+C~

U,S.NUCLEAR REGULATORY CO SION NRCyonM 195 I2.70 I~~4~NRC DISTRIBUTION FoR PART 60 DOCKET MATERIAL DOCKET NUMBER O-244 FILF.NUMBER INCIDENT REPORT TO: I James P.0 ReilXy FROM: 'GE Hochester N.Y.146II9 L.D.White Jr.DATE OF DOCUMENT 12-21-6 DATE RECEIVED 12-2-6%LETTER@ORIGINAL gSjgOP Y ONOTORIZED)A[UN C LASS I F I E D PROP INPUT FORM NUMBER OF COPIES RECEIVED 1 co~DE c o Itr Hef their p8 19 76 ltr concer QGLosURE 23D Power Cabinet (Drop of Two Control ROIis)..~DO NOT REMOVE PLANT NAI,IE: H.E.GINNA.$1 ACKNOWLED(xED

'OTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J, COLLINS BRANCH CHIEF'-W 3 CYS FOR ACTION LICo ASSTo W CYS ACRS CYS HOLDING S NT FOR ACTION/INFORMATION NCER P cm 12-2 REG F g NRC PDR r I G,E 2 MIPC I SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES CASE BUTLER HANAUER TEDESCO/MACCARY

'EISENHUT BAER SHAO VOLLMER/BUNCH KREGER/J, COLLINS INTERNAL DISTRIBUTION

~~~LPDR: TIC: ons EXTERNAL DISTRIBUTION CONTROL NUMBER 13024 4~4~4 P,~V c 4 4 r~4 r ROCIIESTER GAS 1'~hr~hhr~h'4 LEON D.WHITE.JII VICE PRESIDCNT Mr.James P.O'Reilly, Dire'c'tor U.S.Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 651 Park Avenue King of Pru ssia, Pennsylvania 19406 Supplemental Report on Reportable Occu Two Control Rods.R.E.Ginna Nuclear Power Plant, Unit No.1 Docket No.50-244 (5l 6-21, Drop of Subject~~AHD ELECTRIC CORPORATION

~89 EAST AVEHU-, ROCHESTER, N.Y.14649 4~~TCLIrPrrONF RrrCR COOC 7Ir.54G 2700~>R'~~09'0Cf(et File December 2 1976r, OI",,,.~8Pe

Dear Mr.O'Reilly:

In the August 19, 1976 Reportable Occurrence LER 76-21/3L it was stated that Westinghouse specialists assisted in the investigation of the problem with the 2BD power cabinet.Although no exact"ause could be iden-..tified at that time, Westinghouse provided further recommendations for con-sideration.

All these proposals were reviewed by the Ginna Station I&C Group and the PORC.EWR-1646 was issued for design review and safety analysis by the RG&E Engineering Department for these proposals, and they will be followed as conditions warrant.h~~*h Subsequently, the Westinghouse PWR Engineering Group has examined and tested the fuses and sampling resistors which had been removed and reported that only one fuse had any sign of deterioration.

It was determined that this would not have caused the dropped rod problem.Further, the sampling resistors could not be faulted.Two new recommendations concerning the.sampling resistors will be carried out during the next refueling outage.CAR 1082, issued previously for the investigation of the dropped rods associated with the 2BD Power Cabinet, remains in effect.r Two additional copies of this letter are enclosed to conform to the original submittal of LER 76-21/3L.cc: Dr.Ernst Volgenau (30)Mr.William G.McDonald (3)Very truly yours, g':;,S.sP.

L.D.White, Jr.18024 hl AAP tOtt It~P'IIA'It ROCIIESTER GAS AND ELECTRIC CORPORATION o S9 EAST AVENUI"., ROCHESTER, N.Y.14649 LEON D.WHITE.JH.VICE PIIESIIIENT TSLf P>1011F A1ISA COOL'14 5d6.2700" December 21, 1976 Mr.James P.O'Reilly, Director U.S.Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Supplemental Report on Reportable Occurrence 76-21, Drop of Two Control Rods R.E.Ginna Nuclear Power Plant, Unit No.1 Docket No.50-244

Dear Mr.O'Reilly:

In the August 19, 1976 Reportable Occurrence LER 76-21/3L it was stated that Westinghouse specialists assisted in the investigation of the problem with the 2BD power cabinet.Although no exact cause could be iden-tified at that time, Westinghouse provided further recommendations for con-sideration.

All these proposals were reviewed by the Ginna Station I 6 C Group and the PORC.EWR-1646 was issued for design review and safety analysis by the RG6E Engineering Department for these proposals, and they will be followed as conditions warrant.Subsequently, the Westinghouse PWR Engineering Group has examined and tested the fuses and sampling resistors which had been removed and reported that only one fuse had any sign of deterioration.

It was determined that this would not have caused the dropped rod problem.Further, the sampling resistors could not be faulted.Two new recommendations concerning the sampling resistors will be carried out during the next refueling outage.CAR 1082, issued previously for the investigation of the dropped rods associated with the 2BD Power Cabinet, remains in effect.Two additional copies of this letter are enclosed to conform to the original submittal of LER 76-21/3L.Very truly yours, cc: Dr.Ernst Volgenau (30)Mr.William G.McDonald (3) 4 L I!1I~'1 1~'g4 I