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{{#Wiki_filter:~o'plDOll INDIANA&MICHIGAN PDNE8 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  
{{#Wiki_filter:~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:==


==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:
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.
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 REPORT I (PLEASE PAINT ALL FTLGUIRED IMFEIRA4ATIOIII)
Sincerely, D.V. Shaller Plant Manager
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)A II 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
/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.
[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
G. Charnoff, Esq.
~16 Z NA 7 89 10 PUBLICITY NA 7 8 9 7 8 9 FACIL I I Y 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
R. Walsh,           Esq.
[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}}
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 REPORT                               I (PLEASE PAINT ALL FTLGUIRED IMFEIRA4ATIOIII)
LICENSEE                                                                                       LICENSE                  EVENT NAME                                       UCENSE NUMBER                                      TYPF.                   TYPF
[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     REPORT AI I'OAI I)A II Cntt;OOAY           TYPF   SOURCE                OOCKFT NUMBLA                            tVENI OATF 7
~Ol col'I'T 8         57         58       59       80     61 0   5     0   0       3   1     5 68    69 0   1     1   0   7   8 74
                                                                                                                                        ~PLI 75                       80 EVENT DESCRIPTION Qo 2       Reactor Coolant                   S   stem leaka e         rate exceeded the             maximum       allowable         10     m   identified 8 9                                                                                                                                                           80 Ioc3I I   leaka         e   rate.       The   actual leaka           e rate     was   determined to           be a     roxlmately         13     m. A 7   89                                                                                                                                                           80 Ioc4j I   Containment entr                     was made and           the   a   arent source of leakage                   was a     packing       failure 7 8 9                                                                                                                                                             80 Jog       on     the Pressurizer Auxiliar                         S   ra   valve,     HARV-51.
7   8 9                                                                                                                                                           80 Jog                                                                                                                 (RO   50-315/78-08) 7   8 9                                                                       PAME                                                                                 80 SYSTFM           CAUSE                                           COMPONENT              COMPONENT COOE             COOm               COMPONENT CODE               SUPRA               MANUFACTUREA              VOLATION IN8 9LZLCJ 7          10 LSJ 11        12 V
17
                                                                              ~N 43          44 C   6     3   5 47 N
48 CAUSE DESCRIPTION
[oD~]     A   close ins ection of the valve confirmed that the                                           ackin       had   failed     on     RV-51.
80 IoceI 7   8 9                                                                                                                                                           80 pro]
7   8 9                                                                                                                                                           80 FACILI I Y                                                             MLTHOO OF STAIIIS                   POWEA                 OTHER STATUS            OISCOVEAY                          OISCOVEAY OESCAIPTiON Jig           5                 ~10         0         NA 44 a            NA 80 7   8       9                 10             12   13                                   45      46 FORM OF ACTIVITY           COh3TENT AELEASEO           OF RELEASE             AMOUNT OF ACTIVITY                                                   LOCATION OF RELEASE Jig           Z                 Z           NA 44        45                                                                      80 7   8       9                   10     11 PERSONNEL EXPOSURES NUMBER               TYPE       OESCRIPTION pi~]   ~00             0         Z           NA 80 7   89                 11       12     13 PERSONNEL INJURIES NUMBER               OESCAIPTION
[g89 7
        ~oo             o 11   12                                                                                                                                 80 OFFSITE CONSEQUENCES Q~g        NA 7    8 9                                                                                                                                                          80 LOSS OR DAMAGE TO FACILITY TYPE          OESCAIPTION
~16    Z                NA 7    89          10                                                                                                                                                80 PUBLICITY NA 7    8 9                                                                                                                                                          80 ADDITIONAL FACTORS Jig       A   failure of this                   t   e has   not been         reviousl         ex   erienced.           The   valve     was     satisfac-80 7   89 torily repaired                   and no     further action is planned; 7   89                                                                                                                                                           80 David G. >lizner                                                                     616-465-5901 PHONE:}}

Latest revision as of 18:53, 20 October 2019

LER 1978-008-00 Re Exceeded Reactor Coolant System Leakage Rate
ML18219C215
Person / Time
Site: Cook  American Electric Power icon.png
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)
v • d • e


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 REPORT I (PLEASE PAINT ALL FTLGUIRED IMFEIRA4ATIOIII)

LICENSEE LICENSE EVENT NAME UCENSE NUMBER TYPF. TYPF

[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 REPORT AI I'OAI I)A II Cntt;OOAY TYPF SOURCE OOCKFT NUMBLA tVENI OATF 7

~Ol col'I'T 8 57 58 59 80 61 0 5 0 0 3 1 5 68 69 0 1 1 0 7 8 74

~PLI 75 80 EVENT DESCRIPTION Qo 2 Reactor Coolant S stem leaka e rate exceeded the maximum allowable 10 m identified 8 9 80 Ioc3I I leaka e rate. The actual leaka e rate was determined to be a roxlmately 13 m. A 7 89 80 Ioc4j I Containment entr was made and the a arent source of leakage was a packing failure 7 8 9 80 Jog on the Pressurizer Auxiliar S ra valve, HARV-51.

7 8 9 80 Jog (RO 50-315/78-08) 7 8 9 PAME 80 SYSTFM CAUSE COMPONENT COMPONENT COOE COOm COMPONENT CODE SUPRA MANUFACTUREA VOLATION IN8 9LZLCJ 7 10 LSJ 11 12 V

17

~N 43 44 C 6 3 5 47 N

48 CAUSE DESCRIPTION

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

80 IoceI 7 8 9 80 pro]

7 8 9 80 FACILI I Y MLTHOO OF STAIIIS POWEA OTHER STATUS OISCOVEAY OISCOVEAY OESCAIPTiON Jig 5 ~10 0 NA 44 a NA 80 7 8 9 10 12 13 45 46 FORM OF ACTIVITY COh3TENT AELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Jig Z Z NA 44 45 80 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION pi~] ~00 0 Z NA 80 7 89 11 12 13 PERSONNEL INJURIES NUMBER OESCAIPTION

[g89 7

~oo o 11 12 80 OFFSITE CONSEQUENCES Q~g NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCAIPTION

~16 Z NA 7 89 10 80 PUBLICITY NA 7 8 9 80 ADDITIONAL FACTORS Jig A failure of this t e has not been reviousl ex erienced. The valve was satisfac-80 7 89 torily repaired and no further action is planned; 7 89 80 David G. >lizner 616-465-5901 PHONE:

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