ML18219C365

LER 1976-007-00 Re Pin Hole Weld Leak

ML18219C365
Person / Time
Site:	Cook
Issue date:	03/15/1976
From:	Jurgensen R Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1976-007-00
Download: ML18219C365 (12)

Text

NRC FORM'I95 IS-7S)Pi U.S.NUCLEAR REGULATORY CO SION NRC DISTRIBUTION FDR PART 50 DOCKET MATERIAL DOCKET NUMBER 50-315 FILE NUMBER INCIDENT REPORT J.G.Keppler Indiana 8 Michigan Power Co.Bridgman Michigan R.W.Jurgensen DATE OF DOCUMENT 3-15-76 DATE RECEIVED 3-19-76 E3LETTER ABORIGINAL GCOPY 0 NOTOR IZ E D UNCLASSIFIED PROP INPUT FORM NUMBER OF COPIES RECEIVED DESCRIPTION Ltr.trans the following......

ENCLOSURE ROk'6-07, on 12-25-75,Concerning a pin hole weld leak that was discovered.......

(I Cy.received)L PLANT NAME: Cook 8 1 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY:0 iWSGER/J, COLLINS SAFETY BRANCH CHIEF: M 3 CYS FOR ACTION LIC ASST: V/CYS ACRS CYS FOR ACTION/INFORMATION niemann ENT TO LA ENVIRO RE FL NRC PDR ISE 2 INTERNAL DISTRIBUTION SCHROEDER/IPPOLITO NOVAK CHECK TEDE CO MACCA BAER SHAO VOLLMER BUN KREGER OL NS LPDR: t.Ose TIC NSIC EXTERNAL DISTRIBUTION CONTROL NUMBER 2806 4~E I 44 P 0@loan INDIANA&MICHIGAN PDt/I/E8 COMPANY I t!i='ONALD C.COOK NUCLEAR+PL'ANT P.O, Box 458, Bridgman, Michigan'~49106 kc i,,~()March 15, 1976 Mr.J.G.Keppler, Regional Dir~ector Office of Inspection and Enforce.~egt Uni,ted States Nuclear Regulatory orgmipsion Qo Region III~I j/'Ig~799 Roosevel t Road Glen Ellyn, IL 60137 I ala Cy~p'l e<~g/Pp~~+~r4t p 8~~l~~>sgg~ro j'~Operating License DPR-58 Docket No.50-315

Dear Mr.Keppler:

Pursuant to the requirements of Appendix A Technical Specifications and United States Nuclear Regulatory Cormnission Regulatory Guide 1.16, Revision 3, the following report is submitted:

RO 50-315/76-07 At the time of the event it was reviewed and determined not to be reportable under Regulatory Guide 1.16, Revision 3, Section 2.a(3)and a report was not submitted.

However, after subsequent review of the event by the Plant Nuclear Safety Review Committee and discussion with NRC RO: III Resident Inspector, Mr.K.R./Baker, we determined the event should have been reported under the crigeria of Regulatory Guide 1.16, Revision 3, Section 2.b(4).Sincerely, (.W.J gen en Plant Manager/bab cc: RES.Hunter J.E.Dolan G.E.Lien R.Kilburn R.C.Callen MPSC R.J.Vollen BPI K.R.Baker RO: III P.W.Steketee, Esq.R.Walsh, Esq.G.Charnoff-, Esq.G.Olson J.M.Hennigan PNSRC R.S.Keith Dir., IE (30 copies)Dir., MIPC.(3 copies)

M4 i b l

,.XlP CONTROL OLOCK: LCENSEE NAME LCENSE NUMBER I[aa~]I!I 0 CCr:2 0 0-PP 0 PP P 7 89 14 15 0 4 1 25"'6 LICENSEE EVENT REPORT (PLKMSE PRINT ALL REQUIREO INFORMATION) 6 LCENSE EVENT 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBEA[00~]coN'T

~22 L L 0 5 0-0 3 2 5 7 8 57 58 59 60 61 68 EVE'NT DATE 1 2 2 5 7 69 REPORT DATE 5 0 3 1)5'6 74 75 80 EVENT DESCRIPTION Qo g Durin'normal o eration a in hole weld leak was discovered, at high pressure side of 7 89[0D3]FI-200.The leakin of the weld was round out and rewelded on 1-2-76.Another 7 89 Qo4]section of the weld failed on 1-10-76.This was re aired b chanqin the pi in 80 80 7 8 9 Qg confi uration to reduce vibration.

7 8 9 Qom 44.47 7 8 9 PAME SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUER MANUFACTURER

[on~I~I0 E P I P 5 X X Z Z 9 9 9 7 8 9 10 11 12 17.43 CAUSE DESCRIPTION

[oOs)Failure was caused by fatigue due to vibration.

RO 050-315/76-07 48 80 80 80 7 8 9[oOs), 7 89~10 7 89 FACILITY STATUS 95 POWER OTHEA STATUS Qg~E~08 I!II/A 7 8 9 10 12 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY Z~2!I/A 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

~is~00 0 2 II/A 7 89 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION Q>4j~00 0 II A 7 89 11 12 PROBABLE CONSEQUENCES Qsg N/A 7 8 9 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Q~g Z N A 7 89 10 PUBLICITY N/A 7 89 ADDITIONAL FACTORS Q1g N/A 7 89 METHOD OF DISCOVERY DISCOVERY DESCRIPTION A Durin routine lant ins ection.44 45.,46 LOCATION OF RELEASE N/A 44 45 80 80, 80 80 80 80 80 80 80 80 80 7 89 David G.Wizner PHONE.465 5901 80 Gr 0 8ST 60T J',J I'4.1 U.S.NUCLEAR REGULATORV COMMISSION NAC I'ORM 195 I2.7SI NRC DISTRIBUTION FDR PART 50 DOCI<ET MATERIAL DOCKET NUMBER<o-gl g FILE NUMBER XNCXDENT REPORT TO: S MR J G KEPPLER FROM:INDIANA

&MICH POWER CO BRIDGMAN, MICH R JURGENSEN DATE OF DOCUMENT 3-lS-z4 DATE RECEIVED 4 5IJ ETTER ABORIGINAL QCOI V DESCRIPTION 0 N0 TO R I Z E D+UNCLASSIFIED PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED l LTR TRANS THE FOLLOWING.......

I 1 LICENSEE EVENT REPORT 50-'15/76-07 ON 12-25-75 RE A PIN HOLE WELD LEAK WAS DIS-COVERED AT HI-PRESSURE SIDE OF OFI-200......

PLANT NAIIH: Comic.4<NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J.COLLINS SAFETY BRANCHA CHIEF: W 3 CYS FOR ACTTON LXC~ASST: W/CYS ACRS CYS HOLDXNG/HNT TO LA FOR ACTION/INFORMATION ENVXRO L'Q FILE PDR I&E 2 INTERNAL DISTRIBUTION SCHROEDER/IPPOLXTO

'~NO~VAK CHECK CLJalmm IMUH'-BAHR SHAO VOLLMER BUNCH KK!G~ER 1 COL.NR naagQ Hx,.TXC NSIC LXTERNAL DISTRIBUTION CONTROL NUMBER NfiC FORM 195 (2-7G)

I~'~~.)

),+'o IllfDIANA 8 MICHIGA/V POWER COMPANY DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 p March 15, 19?6 Mr.J.G.Keppler, Regional Director Office of Inspection and Enforcement Uni.ted States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137~~I;I:)h~Man 17 19761 P~ggQEAR RKV~i 0j Ne5~Operating License DPR-58 Docket No.50-315

Dear Mr.Keppler:

Pursuant to the requirements of Appendix A Technical Specifications and United States Nuclear Regulatory Commission Regulatory Guide 1.16, Revision 3, the following report is submitted:

RO 50-315/76-07 At the time of the event it.was reviewed and determined not to be reportable under Regulatory Guide 1.16, Revision 3, Section 2.a(3)and a report was not submitted.

However, after subsequent review of, the event by the Plant Nuclear Safety Review Committee and discussion with NRC RO: III Resident Inspector, Mr.K.R.Baker, we determined the event should have been reported under the criteria of Regulatory Guide 1.16, Revision 3, Section 2.b(4).Sincerely, (.W.J gen en Plant Manager/bab g 0 9 QIIigh~, gyp'~CC: R.S.Hunter J.E.Dolan G.E.Lien R.Kilburn R.C.Callen MPSC R.J.Vollen BPI K.R.Baker RO: III P.H.Steketee, Esq.R.Halsh, Esq.G.Charnoff, Esq.~G.Olson J.M.Hennigan PNSRC R.S.Keith Dir., IE (30 copies)Dir., MIPC (3 copies)cog~y(y'll

'I 1(p h't CONTROL 8LOCK: LlCENSEE EVENT REPORT SE PAINT ALL AEQUIAED INFOAIVIATION)

UCENSEE NAME[oa~]N I 0 C C 1 0 0 7 89 14 15 LICENSE NUMBER OO O OO-0 0 EVENT TYPE LICENSE TYPE 4 1 1 1 0 26 30 3'I 32 REPORT, CATEGORY TYPE~01 CQN'T~gp.L 7 8 57 58 59 REPORT SOURCE L 0 60 61 DOCKET NUMBER EVENT DATE REPORT DATE 5 0-0 3).5 1 2 2 5 7 5 0 3 1 5 7 6 68 69 74 75 80 EVENT DESCRIPTION toOI Durin'ormal o eration a in hole weld leak was discovered at high pressure side of 7 89 Qo 4j section of the weld failed on 1-10-76.This was re aired b chanqin the piping 7 89 Qg confi uration to reduce.Vibration.

7 8 9 Jog 7 8 9 PRME SYSTEM CAUSE COMPONENT CODE CODE COMPONENT CODE SUPPUER~a~LIIDI~Z 7 8 9 10 11 12 17.43 CAUSE DESCRIPTION IDOI Failure was caused by fatigue due to vibration.

COMPOI4ENT MANUFACTURER Z 9 9 9 P I P E X X 44.47 RO 050-315/76-07 VCLAIION 7'9 I FI-200.The leakin of the weld was round out and rewelded on 1-2-76.Another 80 80 80 80 80 7 8 9 Jog 7 89~10 7 89 FACIUTY STATUS POWER OTHER STATUS Q~g E~08 1 N/A 7 8 9 10 12 13 FORM OF ACTIVITY COAT)MT RELEASEO OF RELEASE AMOUNT OF ACTIVITY Q1g Z~Z N/A 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

~is~00 0~Z N/A 7 89 11 12'3 PERSONNEL INJURIES NUMBER DESCRIPTION

~44~00 0', NA 7 8 9 11/12 PROBABLE CONSEQUENCES Q~g N/A 7 89 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Q~g Z N A 7 89 10 PUBLICITY 7 89 ADDITIONAL FACTORS[>is]N/A 7 89 METHOD OF DISCOVERY DISCOVERY DESCRIPTION

~A Durin routine lant ins ection.44 45 46 LOCATION OF RELEASE N/A 44 45 80 80.80 80 80 80 80 80 80 80 7 89 NAME.David G.Ilizner PHONE.465-5901 80 CPO bb I 667 4 l~s~~II)1