ML18219C218

From kanterella
Jump to navigation Jump to search
LER 1978-005-00 Re Low Boric Acid Transfer Pump Discharge Pressure
ML18219C218
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 02/06/1978
From: Shaller D
Indiana Michigan Power Co
To: James Keppler
NRC/RGN-III
References
LER 1978-005-00
Download: ML18219C218 (10)


Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 02/06/78 NRC IN 5 MI PWR DATE RCVD: 02/10/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 0 ENCL 1 LICENSEE EVENT REPT (RO 50-315/78-05) ON 01/16/78 CONCERNING NO 2 BORIC ACID TRANSFER PUMP DISCHARGE PRESSURE WAS 4 PSIG LOWER THAN MINIMUM REQUIRED'UE TO LEAKING MECHANICAL SHAFT SEAL.

PLANT NAME: COOK UNIT REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:

w++ww++++++4+++++ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION: BRANCH=-CH'I'EF=B S++W/4 ENCL INTERNAL: REG FILE4+W/EN NRC PDR44W/ENCL

8. E+'>W72 ENC MIPC++W/3 ENCL SCHROEDER/I PPOL I TO++M/ENCL HOUSTON44W/ENCL NOVAK/CHECK++W/ENCL GR IMES++W/ENCL KNIGHT@4 W/ENCL BUTLER++W/ENCL HANAUER++W/ENCL TEDESCO++W/ENCL EISENHUT4+W/ENCL BAER+4W/ENCL SHAO++W/ENCL VOLLMER/BUNCH++W/ENCL KREGER/J. COLLINS44W/ENCL ROSA44W/ENCL L. CROCKER++W/ENCL K SEYFRIT/IE4+W/ENCL EXTERNAL: LPDR'S ST. JOSEPH) MI4+W/ENCL T I C++W/ENCL NSIC4+W/ENCL ACRS CAT B++W/16 ENCL COPIES NOT SUBifITTED PER REGULATORY GUIDE 10.1 DISTRIBUTION: LTR 46 ENCL 46 CONTROL NBR: 780410038 SIZE: iP+1P THE END

I a ~

I't

~ a k

.-it1a r

t' I H.'a r l 4 r I

'I I

~, I ~ I" 4 ~ II a I

I I

aa P

t 'kkka ( I r a a ~ - l ti" I ~ I r' tt ra a t I4 r II II H ~ It

l P merlcsn D iV ICH f'omma DONALD C. COOK NUCLEAR PLANT C~ofa ~~

P.O. Box 458, Bridgman, Michigan 49106 i'

'"+ +<o++4 ~

February 6, 1978 Mr. J.G. Keppler, Regional Director e Office of Inspection and Enforcement 8 United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating Li cense DPR-58 Docket No. 50-315

Dear Mr. Keppl er:

Pursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Cormission Regulatory Guide 1.16, Revision 4, Section 2.b, the following report is submitted:

RO 50-315/78-05.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan R.W. Jurgensen G.E. Lien R. Kilburn R.J. Vollen BPI R.C. Callen MPSC K.R. Baker RO:III P.W. Steketee, Esq.

R. Walsh, Esq.

G. Charnoff, Esq.

G. Olson PNSRC 78OP$ 0038 J.F. Stietzel Dir., IE (30 copies)

Dir., MIPC (3 copies)

]Bog, s N/I

l V

J

Farm No. 4494 LICENSEE EVENT REPORT 14 'ONTROL BLOCK: (PLEASE PAINT ALL AEOUIAEO IMFOAMATION) 1 6 LICENSEE LLCENSE EVENT NAME LICENSE NUMBER TYPC TYPF K1 N I D C C 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~03

~

7 89 14 15 85 30 31 38 REPORT REPORT CATEGORY TYPE SOURCE OOCKET NUMBER EVENI OATF AI PORT OAII

[OD1]rosrt L L 0 5 0 0 3 1 5 0 1 1 5 7 8 7 8 57 58 59 80 81 88 69 74 75 00 EVENT DESCRIPTiON joOa] Durin surveillance test k'2 Boric Acid Transfer Pum dischar e ressure was 4 si 7 8 9 80

[0D3] lower than the minimum re uired. The pump mechanical seal was leaking and was re-7 89 80

[ouai L placed. The um was retested satisfactorily. The dl pump was operable. This con-7 8 9 80

[oOs] dition did not re resent a substantial safety hazard. (RO 50-315/78-05) 7 8 9 80 Jog 7 6 9 PRM E 80 SYSTEM CAUSE COMPONENT COMPONENT

~or 7 8 9 COBE Lppi 10

~

COOE 11 18 P

COMPONENT COOE 0 M P X X 17 SUPPUER L~I 43 44 G

MANUFACTURER 2 0 0 47 VN3IATCN N

48 CAUSE DESCRIPTION

[oaf The cause of the low dischar e ressure was a leakin mechanical shaft seal. The 7 8 9 80

[ouei L seal failure was attributed to normal wear.

7 8 9 80 Qo]

7 89 FACAII Y METHOO OF 80 STAIIIS POWER OTHER STATUS OISCOVERY DISCOVERY OESCRIPTION 7 8 9 5 ~l0 10 0

18 13 NA 44 b

45 46 NA 80 FORM OF ACTIVITY COAT ENT RELE*SEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Qg Z ~Z NA 44 NA 7 8 9 10 11 45 80 PERSONNEL EXPOSURES NUMBER TYPE OCSCRIPTION

~00 0 X NA 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER OESCRIPTION

~<4 69

~00 0 NA 7 11 12 80 OFFSITE CONSEQUENCES Jig NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRlPTIOP7P/

Q~g Z NA 7 89 10 80 PUBLICITY NA 7 89 80 ADDITIONAL FACTORS Q~g NA 7 89 80 7 89 80 NAME; Da G. Wi zner PHDNE. 61 6 465 5901 CiPO 88 I ~ 88T

HOHV88 ssolnuss voiina~uxsio sew's'n 6C l Nd 6 83d8J-6l MS3Q 10ULH03

<Nsvgaoo aanaosg

Mmeman DJjg@ & G G N PDWER D~DIPUUIZI DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 February 6, 1978 Mr. J.G. Keppler, Regional Director Office of Inspect i on and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-58 Docket No. 50-315

Dear Mr. Keppler:

Pursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Comnissi,on Regulatory Guide 1. 16, Revision 4, Section 2.b, the following report is submitted:

RO 50-315/78-05.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan R.W. Jurgensen G.E. Lien R. Kilburn R.J. Vollen BPI R.C. Callen MPSC K.R. Baker RO: III P.W. Steketee, Esq.

R. Walsh, Esq.

G. Charnoff, Esq.

G. Olson PNSRC J.F. Stietzel F~ 8 91978 Dir., IE (30 copies)

Dir., MIPC (3 copies)

ri> s

>~

Form No. 4494 OLICENBEE EVENT REPORT CONTROL BLOCK: fPLEABE PAINT ALL REQUIRED INFDRIVIATIDM) 1 LICENSEE

~ Qr Ill I lrl p +Ul LICENS EVENT NAME LICENSE NUMBER TYPF

~o~ II I O C C 0 0 0 0 0 0 0 0 0 4 1 1 1 1 L0003~J 89

~

7 14 15 25 26 30 31 32 AEPORT REPORT

( f'g E.'/ G~~

g CATEGORY TYPE SOURCE DOCKET NUMBER FVENI OATF RII>OAT OATr:

IQD1Icorrr L L 0 5 0 0 3 1 5 0 1 1 6 7 8 0 2 0 6 7 8 7 8 57 58 59 60 61 JB 69'ra.4. (;.IJ 74 75 00 odOIYflMl<OITUQlfli8fo EVENT DESCRIPTION tQilARO Qo 2 Durin surveillance test ¹2 Boric Acid Transfer Pum dischar e ressure was 4 si 7 89 80

[0D3] lower than the minimum re uired. The pump mechanical seal was leaking and was re-7 8 9 80

[oa4I LJrlaced. The um was retested satisfactorily. The ¹I pump was operable. This con-7 8 9 80

[os dition did not re resent a substantial safety hazard. (RO 50-315/78-05) 7 8 9 80 QOQ 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT

~07 7 8 8 10 p '~

CODE

~

CODE 11 12 P

COMPONENT COOE U M P X X 17 SUPPUER N

43 44 G

MANUFACTURER 2 0 0 47 VIOLATION 48 CAUSE DESCRIPTION

[oOs] The cause of the low dischar e ressur e was a leakin mechanical shaft seal. The 7 8 9 80

[QD9j 7 8 L seal failure was attributed to normal wear.

9 80 Qo]

7 89 METHOO OF 80 FACILITY STATUS POWER OTHER STATUS OISCOVERY OISCOVERY OESCRIPTION Irrrj 7 8 9

~~ ~io 10 o

12 13 44 b

45 46 NA 80 FORM OF ACTIVITY COATENT AMOUNT OF ACTIVITY LOCATION OF AELEASE NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTIO Qg LoaooJ z 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER OESCAIPTION IrDaI LoaooJ IIA 7 89 11 12 80 OFFSITE CONSEQUENCES Qg NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION

~16 Z NA 7 89 10 80 PUBLICITY NA 7 89 80 ADDITIONAL FACTORS Qjs] NA 7 89 80 Q~g 7 89 80 NAMEI Da G. Wizner PHONE. 616-465-5901 GPO 88T

RECDVEQ OOCUHENT CONTROl. OESK 3978FEB l5 PM 2 22 U.S. NRC OISTRlBUTION SERVlCES BRANCH