05000316/LER-2078-008, Re Exceeded Reactor Coolant System Leakage Rate

Re Exceeded Reactor Coolant System Leakage Rate

ML18219C215
Person / Time
Site:	Cook
Issue date:	02/15/1978
From:	Shaller D Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-008-00
Download: ML18219C215 (2)

LER-2078-008, Re Exceeded Reactor Coolant System Leakage Rate

Event date:
Report date:
3162078008R00 - NRC Website

text

~o' plDOll INDIANA& MICHIGANPDNE8 CONPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 456, Bridgman, Michigan 49106 February 15, 1978'r.

J.G.

Keppler, Regional Director Office of Inspection 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 Commission Regulatory Guide 1.16, Revision 4, Section 2.b, the following report is submitted:

RO 50-315/78-08.

Sincerely, D.V. Shaller Plant Manager

/bab CC:

J.E.

Dolan R.W. Jurgensen G.E.

Lien R. Kilburn R.J.

Vollen BPI K.R. Baker RO:III R.C. Callen MPSC P.W. Steketee, Esq.

G. Charnoff, Esq.

R. Walsh, Esq.

G.

Olson J.M. Hennigan PHSRC J.F. Stietzel Dir., IE (30 copies)

Dir., MIPC (3 copies)

FEB )7t978

Form No. 4494 CONTROL BLOCK:

ICENSEE EVENT REPORTI (PLEASE PAINT ALLFTLGUIRED IMFEIRA4ATIOIII)

LICENSEE NAME LICENSE TYPF.

EVENT TYPF UCENSE NUMBER [oa'] LII[ I 0IC 0 Il 0

0 0

0 0

0 0 0 0

4 1

1 1

1

~03 7

89 25 26 30 31 32 AEronr Cntt;OOAY TYPF

~Ol col'I'T~

7 8

57 58 59 REPORT SOURCE 80 OOCKFT NUMBLA tVENI OATF AI I'OAI I)AII 0

5 0 0 3

1 5

0 1

1 0

7 8

~PLI 61 68 69 74 75 80

EVENT DESCRIPTION

Qo 2 Reactor Coolant S stem leaka e rate exceeded the maximum allowable 10 m identified 80 m.

A 8 9 Ioc3I I leaka e rate.

The actual leaka e rate was determined to be a

roxlmately 13 7

89 80 Ioc4j I Containment entr was made and the a

arent source of leakage was a packing failure 7

8 9 Jog on the Pressurizer Auxiliar S ra

valve, HARV-51.

7 8 9 Jog (RO 50-315/78-08) 80 80 COMPONENT MANUFACTUREA VOLATION 48 17 43 80 7

8 9 PAME 80 SYSTFM

CAUSE

COMPONENT COOE COOm COMPONENT CODE SUPRA IN LZLCJ LSJ V

~N C

6 3

5 N

7 8 9 10 11 12 44 47

CAUSE

DESCRIPTION [oD~]

A close ins ection of the valve confirmed that the ackin had failed on RV-51.

IoceI 7

8 9 pro]

OTHER STATUS OFFSITE CONSEQUENCES Q~g NA 7

8 9 LOSS OR DAMAGE TO FACILITY TYPE OESCAIPTION

~16 Z

NA 7

89 10 PUBLICITY NA 7

8 9 7

8 9 FACILIIY STAIIIS POWEA Jig 5

~10 0

NA 7

8 9

10 12 13 FORM OF ACTIVITY COh3TENT AELEASEO OF RELEASE AMOUNT OF ACTIVITY Jig Z

Z NA 7

8 9

10 11 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION pi~] ~00 0

Z NA 7

89 11 12 13 PERSONNEL INJURIES NUMBER OESCAIPTION [g ~oo o

7 89 11 12 MLTHOO OF OISCOVEAY a

NA 44 45 46 44 45 OISCOVEAY OESCAIPTiON LOCATION OF RELEASE 80 80 80 80 80 80 80 80 80 ADDITIONAL FACTORS Jig A failure of this t e has not been reviousl ex erienced.

The valve was satisfac-7 89 torily repaired and no further action is planned; 80 7

89 David G. >lizner PHONE: 616-465-5901 80