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=Text=
=Text=
{{#Wiki_filter:REGULATORY I NFORI"IAT ION DISTRIBUTION, SYSTEN (R IDS)DISTRIBUTION FOR INCONING NATERIAL 50-315 REC: NRC QRG: SHALLER D V DOCDATE: 03/14/78 NRC IN 8c NI PWR DATE RCVD: 03/20/78 DOCTYPE: LETTER NOTARIZED:
{{#Wiki_filter:REGULATORY I NFORI"IATION DISTRIBUTION, SYSTEN ( R   IDS)
NO COPIES RECEIVED  
DISTRIBUTION FOR INCONING NATERIAL                           50-315 REC:   NRC                         QRG: SHALLER D V                     DOCDATE: 03/14/78 NRC                               IN 8c NI PWR                     DATE RCVD: 03/ 20/ 78 DOCTYPE:   LETTER     NOTARIZED: NO                                       COPIES RECEIVED


==SUBJECT:==
==SUBJECT:==
LTR 1 ENCL 1 LICENSEE EVENT REPT (RO 50-315/78-016l03L-0)
LTR 1     ENCL 1 LICENSEE EVENT REPT (RO     50-315/78-016l03L-0) ON 02/15/78 CONCERNING 1AB ENERGENCY DIESEL   GENERATOR   WAS REI"IOVED FROM SERVICE FOR MAINTENANCE AND THE BREAKER ALIGNMENT   VERIFICATION   AS REQUIRED BY TECH SPEC 4. 8. 1. 1. 1A WAS NOT PERFORNED WITHIN ONE HOUR.
ON 02/15/78 CONCERNING 1AB ENERGENCY DIESEL GENERATOR WAS REI"IOVED FROM SERVICE FOR MAINTENANCE AND THE BREAKER ALIGNMENT VERIFICATION AS REQUIRED BY TECH SPEC 4.8.1.1.1A WAS NOT PERFORNED WITHIN ONE HOUR.PLANT MANE: COOK-UNIT 1+~~~~~~~~~HI
PLANT MANE: COOK UNIT   1                                   REVIEWER  INITIAL: X JN DISTRIBUTOR  INITIAL: g, A
~~~~~~~DISTR I BUT ION INCIDENT REPORTS (DISTRIBUTION CODE A002)REVIEWER INITIAL: X JN DISTRIBUTOR INITIAL: g, A OF THIS NATERIAL IS AS FOLLOWS+++~~~~~~~~~~~~~~~
+~~~~~~~~~HI ~~~~~~~ DISTR I BUT ION OF   THIS NATERIAL IS AS FOLLOWS +++~~~~~~~~~~~~~~~
FOR ACTION: INTERNAL: EXTERNAL: EI4CER++W/4 ENCL REG FILE4+W NCL SCHRQEDER/
INCIDENT REPORTS (DISTRIBUTION CODE A002)
IPPQL I TO+4 M/ENCL NQVAK/CHECK++W/ENCL KNIGHT44W/
FOR ACTION:                       EI4CER++W/4 ENCL INTERNAL:        REG FILE4+W     NCL                 NRC PDR++Wf ENCL NIPC++4f/3 ENCL SCHRQEDER/ IPPQL I TO+4 M/ENCL      HOUSTQN4+W/ENCL NQVAK/CHECK++W/ENCL                  GRINES++W/ENCL KNIGHT44W/ENCL                      BUTLER++W/ENCL HANAUER++W/ENCL                      TEDESCO++W/ENCL EI SENHUT~+W/ENCL                   BAER44 WfENCL SHAO++W/ENCL                        VOLLMER/BUNCH++W/ENCL KREGER/ J. COLL INS4 +I Jf ENCL     ROSA'WfENCL K SEYFRIT/IE++W/ENCL EXTERNAL:        LPDR S ST. JOSEPH'I     ++l JlENCL TIC++W/ENCL NSIC+4l J/ ENCL ACRS   CAT B+4 W/1 6 ENCL       I COPIES NOT SUBMITTED PER REGUIATORY GUIDE 10. 1 DISTRIBUTION:     LTR 45     ENCL 45                           CONTROL NBR:      780810  5 SIZE: iP+iP THE END
ENCL HANAUER++W/ENCL EI SENHUT~+W/ENCL SHAO++W/ENCL KREGER/J.COLL INS4+I Jf ENCL K SEYFRIT/IE++W/ENCL LPDR S ST.JOSEPH'I++l JlENCL TIC++W/ENCL NSIC+4l J/ENCL ACRS CAT B+4 W/1 6 ENCL NRC PDR++Wf ENCL NIPC++4f/3 ENCL HOUSTQN4+W/ENCL GRINES++W/ENCL BUTLER++W/ENCL TEDESCO++W/ENCL BAER44 Wf ENCL VOLLMER/BUNCH++W/ENCL ROSA'Wf ENCL I COPIES NOT SUBMITTED PER REGUIATORY GUIDE 10.1 DISTRIBUTION:
LTR 45 ENCL 45 SIZE: iP+iP CONTROL NBR: 780810 5 THE END 0 I 1 II i yO M mertoan OI HA 8 NICHIGAIlI POIEER CONPAIIIY IE>gQig)P P()~li~f'I'frn DONALD C.COOK NUCLEAR PLANT'8 P.O.Bov 458, Bridgman, Michigan 49106 March 14, 1978 Hr.J.G.Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Comnission Region III 799 Roosevelt, Road Glen Ellyn, IL 60137


==Dear Hr.Keppler:==
I 1
u,s'"mc p 79pg COAIAIEG GEO'~~ESS Qa l~C'perating License DPR-58 Docket No.50-315 Pursuant to the requirements of Appendix A Technical Specifications the following report is submitted:
RO 78-016/03L-O.
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: I I I R.C.Callen HPSC P.W.Steketee, Esq.R.Walsh, Esq.G.Charnoff, Esq.G.Olson J.M.Hennigan PNSRC J.F.Stietzel Dir., IE (30 copies)Dir., HIPC (3 copies)780810015]gooa./~%/ji R NRC FRORhl 366 I7.77)LlCENSEE EVENT REPORT~01 8 CONTROL BLOCK:{PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I 6 N I 0 C C 1QE 0 0 0 0 0 0 0 0 0 0 0 QE4 1 1 1 1 OR~OR 9 LICENSEE CODE 14 15 LICENSE NUhIBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T~01 7 8 SOU CE L~JQG 0 Q 60 61 DOCKET NUMBER 68 69 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 UNIT WAS OPERATING NORMALLY IN M D 1.T EVENT DATE QB 74 75 REPORT DATE 80 OB~03 FROM SERVICE AT 0130 HOURS ON 2 15 78 FOR MAIf]TENANCE.
H R TION AS RE UIRED BY APPENDIX A TECH.SPEC.4...W~OG HOUR.THE CORRECT BREAKER ALIGNMENT WAS VERIFIED AT 10 5 H UR~OG REMAINED AT STEADY~07 CALLED UPO.T~OB 7 8 80 7 8 SYSTE'M CAUSE CAUSE COMP.VALVE.CODE CODE SUBCODE COMPOiVENTCODE SUBCODE SUBCODE~ZZ Q>>~AQ>>~AQ>>Z Z Z Z Z Z Qi~ZQEE~Z Q's 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER)RO EVENT YEAR REPORT NO.CODE TYPE NO.Q17 RERRRE~78~~01 6~~~03~L-~P 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDX PRIME CohIP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS~22 SUBMITTED FORM'SUB.SUPPLIER MAiNUFACTURER
~HS~ZQ L~JQ20 LZJO~023~Q24 MQ26 Q26 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 027 o THE EVENT WAS CAUSED BY THE UNIT SUPERVISOR FAILING TO RE UIRE HAVING THE BREAKER ALIGNMENT VERIFIED.THE SHIFT OPERATING ENGINEER REINSTRUCTED THE UNIT P THE REQUIREMENTS FOR REMOVING VITAL EQUIPMENT FROM SERVICE WITH RESPECT TO PERFORM-3 ING SURVEILLANCE AS DIRECTED BY THE TECH.SPECS.AND OPERATING DEPARTMENT INSTRUCTIONS 4 7 8 9 FACILITY~30 hIETHOO OF STATUS%POWER OTHER STATUS~DISCOVERY 6 Oss~io o OE>>A~AQ>>P ANT STAT 7 8 9 10 12 13 44 45 ACTIVITY CONTENT RELEASED OF REI.EASE AhIOUNT OF ACTIVITY~36 Z Q33~ZQ34 NA 7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUi4IBER TYPE DESCRIPTION Q3B~77~00 0 0 Z Oss NA 7 8 9 11 12 13 PERSONNEL INJURIES 7 8 9 11 12 LOSS OF OR OAhIAGE TO FACILITY Q43 TYPE DESCRIPTION
~IB 7 8 9 10 PUBLICITY ISSUED DESCRIPTION
~~O44 7 8 9 10 NAME OF PREPARER R.S.Keith DISCOVERY DESCRIPTION Q32 Y 80 80 80 80 NRC USE ONLY 80 ER 0 68 69 PHDNE.61 6 465 5901 ENG INEER Bo LOCATION OF RELEASE Q 80 h~.RECEIVEO OOCUVFN~CO>CIRCE BESIDE U.S.NRC DIS TRIBUT ION SERVICES BRANCH CoP//W>ee~~L, i~Nolcw I NIGHIG 8 PDIYE4 coN IN DONALD C.COOK NUCLEAR PLANT P.O.Box 456, Bridgman, Michigan 49106 March 14, 1978 Mr.J.G.Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Comnission Region III 799 Roosevelt Road Glen Ellyn, IL 60137


==Dear Mr.Keppler:==
IIyO i
Operating License DPR-58 Docket No.50-315 Pursuant to the requirements of Appendix A Technical Specifications the following report is submitted:
Mmertoan OI HA 8 NICHIGAIlIPOIEER CONPAIIIY DONALD C. COOK NUCLEAR PLANT IE>gQig)P      P()
RO 78-016/03L-O.
                                                                        ~li ~f'I'frn
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.R.Walsh, Esq.G.Charnoff, Esq.G.Olson J.M.Hennigan PNSRC J.F.Stietzel Dir., IE (30 copies)Dir., MIPC (3 copies)i~~~l,)S78 II'I~~I t I''li U.S.NUCLEAR REGULATORY COMMISSION NRC FORM 366{7-77)+~~~-~0 7 8 CON'T~0 7 8 LICENSEE EVENT REPORT O1{PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6 1Qs 0 0 0 0 0 0 0.0 0 0 0 Qs4 1 1 1 1 Q4~Qs 14 15 25 26 I.ICENSE'TYPE 30 57 CAT 58 CONTROL BLOCK: I M I D C C LICENSEE CODE 0 SOURCE L~JQ 0 60 61 DOCKET NUMBER 68 69 EVENT DESCRIPTION AND PROBABI.E CONSEQUENCES QIO UNIT WAS OPERATING NORMALLY IN ODE 1.EVENT DATE 74 75 REPORT DATE 80~03 FROM SERVICE AT 01 30 HOURS ON 2 1 5 78 FOR MAIl TENANCE.THE~04 TION AS RE UIRED BY APPENDIX A TECH.SPEC~os HOUR.THE CORRECT BREAKER ALIGNMENT WAS VERIFIED AT 1 5 UR~06 REMAINED AT STE D~0 7 CALLED UP~OB 80 7 8 9 g SYSTEM CAUSE CAUSE COMP.VALVE.CODE CODE SUBCODE COMPONENT CODE SVBCODE SUBCODE~ZZ Q>>A Q>>~AQ>>Z Z Z Z Z Z Qs~ZQs~ZQs 7 8 9 10 11 12 l3 18 19 20 SEaUENTIAL OCCURRENCE REPORT REVISION LERIRP EVENT YEAR REPORT NO.CODE TYPE NO.Q17 REpoRT~78 Q~01 6 Qx~03 QL[J QQ 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDP PRIME COMP.COMPONENT TAKEN ACTION ON PLANT~METHOD HOURS Q22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER
                                                                                                '8 P.O. Bov 458, Bridgman, Michigan 49106 u,s    '"mc        p 79pg March 14, 1978                                                                        COAIAIEGGEO
~HO>>~ZO>>~ZO20&O21 MQss LzLIQ4[zJQss O26 33 34 35 36 37 40 41 42 43 44 47 , CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 027 o THE EVENT WAS CAUSED BY THE UNIT SUPERVISOR FAILING TO RE UIRE HAVING THE BREAKER ALIGNMENT VERIFIED.THE SHIFT OPERATING ENGINEER REINSTRUCTED THE UNIT S P THE REQUIREMENTS FOR REMOVING VITAL EQUIPMENT FROM SERVICE WITH RESPECT TO PERFORM 1 3 ING SURVEILLANCE AS DIRECTED BY THE TECH.SPECS.AND OPERATING DEPARTMENT INSTRUCTIONS 4 7 8 9 FACILITY M30 METHOD OF STATUS%POWER OTHER STATUS 0 DISCOVERY 6 Q>>~l0 0 Qss NA'AQ>i PLA T 8 9 10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF REI.EASE AMOUNT OF ACTIVITY~Z Q33 Z Q34 NA 7 8 9 10 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q3g~00 0$ZQss NA 7 8 9 11 12 13 PERSONNEL INJURIES DISCOVERY DESCRIPTION 032 T R 80 80 80 ENGINEER 80 LOCATION OF RELEASE Q 7 8 7 8 o 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION Ir JQs 9 10 PUB L I CITY ISSUED DESCRIPTION
                                                                                          '~~ESS      Qa l~
~4.~Q44 7 8 9 10 NAMF PF PREPARER R" S~Ke'I th NRC USE ONLY 80 68 69 PHoNE'16 465-5901 80 80 o 0 L 0 I 4,.IW I}}
Hr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Comnission Region    III 799  Roosevelt,    Road Glen  Ellyn, IL      60137                                            C'perating License DPR-58 Docket No. 50-315
 
==Dear Hr. Keppler:==
 
Pursuant to the requirements        of  Appendix A Technical Specifications the following report is submitted:
RO  78-016/03L-O.
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: I I I R.C. Callen HPSC P.W. Steketee,  Esq.
R. Walsh, Esq.
G.      Charnoff, Esq.
G.      Olson J.M. Hennigan                                                  780810015 PNSRC J.F. Stietzel Dir.,    IE (30 copies)
Dir.,    HIPC (3  copies)
                                                                                            ]gooa./~ %
                                                                                              /ji
 
R NRC FRORhl 366 I7.77)
LlCENSEE EVENT REPORT CONTROL BLOCK:                                                                      {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I                                  6
~01 8    9 N    I    0 C C LICENSEE CODE 1QE 14      15 0    0  0    0    0    0    0 LICENSE NUhIBER 0    0    0    0 25 QE4 26 1      1    1 LICENSE TYPE 1
30 OR~OR 57 CAT 58 CON'T
~01 7        8 SOU CE      L~JQG 60            61 0
DOCKET NUMBER              68 Q  69      EVENT DATE              74 QB 75      REPORT DATE            80 OB EVENT DESCRIPTION AND PROBABLE CONSEQUENCES                                Q10 UNIT      WAS      OPERATING NORMALLY IN                      M D      1.      T
~03              FROM SERVICE AT                    0130      HOURS ON 2        15 78 FOR MAIf]TENANCE.                        H      R TION AS          RE    UIRED BY APPENDIX A TECH. SPEC.                                4...                W
~OG              HOUR.        THE CORRECT BREAKER ALIGNMENT WAS VERIFIED AT 10 5 H UR
~OG              REMAINED AT STEADY
~07              CALLED UPO              . T
~OB                                                                                                                                                                                  80 7        8 SYSTE'M              CAUSE        CAUSE                                                        COMP.            VALVE.
CODE                CODE      SUBCODE                  COMPOiVENTCODE                      SUBCODE          SUBCODE 8
                                  ~ZZ 9          10 Q>>        ~AQ>>
11
                                                                          ~AQ>>
12            13 Z    Z    Z    Z    Z    Z 18 Qi        ~ZQEE 19
                                                                                                                                                        ~Z 20 Q's 7
SEQUENTIAL                          OCCURRENCE              REPORT                        REVISION Q17 LER)RO RERRRE ACTION FUTURE EVENT YEAR
                                    ~78 21          22 EFFECT
                                                              ~
23 SHUTDOWN
                                                                          ~01 24 REPORT NO.
6 26
                                                                                                    ~~
27
                                                                                                                  ~03 28 ATTACHMENT CODE 29 NPRDX TYPE
                                                                                                                                          ~L 30
 
31 PRIME CohIP.
                                                                                                                                                                        ~P NO.
32 COMPONENT TAKEN ACTION                    ON PLANT            METHOD                  HOURS ~22        SUBMITTED          FORM'SUB.          SUPPLIER              MAiNUFACTURER
              ~HS~ZQ 33          34 L~JQ20 35 LZJO 36            37                    40
                                                                                                              ~023 41
                                                                                                                                  ~Q24 42 MQ26 43                44            47 Q26 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 027 o        THE EVENT WAS CAUSED BY THE UNIT SUPERVISOR                                              FAILING      TO RE UIRE HAVING THE BREAKER ALIGNMENT VERIFIED.                            THE    SHIFT OPERATING ENGINEER REINSTRUCTED THE UNIT                                                P THE REQUIREMENTS FOR REMOVING VITAL EQUIPMENT FROM SERVICE WITH RESPECT TO PERFORM-3          ING SURVEILLANCE AS DIRECTED BY THE TECH. SPECS.                                                AND OPERATING DEPARTMENT INSTRUCTIONS 4
80 7        8    9 FACILITY STATUS 6  Oss      ~io
                                  % POWER o    OE>>A OTHER STATUS    ~
                                                                                    ~30      hIETHOO OF DISCOVERY
                                                                                                ~AQ>>        P  ANT STAT DISCOVERY DESCRIPTION Q32 Y
8    9              10                12      13                            44      45                                                                                  Bo 7
ACTIVITY      CONTENT                                                                                                                                    ENG  INEER RELEASED OF REI.EASE                          AhIOUNT OF ACTIVITY~36                                                      LOCATION OF RELEASE        Q Z    Q33    ~ZQ34                NA 7      8    9              10            11                                          44            45                                                                            80 PERSONNEL EXPOSURES 0
NUi4IBER            TYPE          DESCRIPTION Q3B
~77 8
              ~00            0 12 Z    Oss 13 NA 80 7            9                11 PERSONNEL INJURIES 7        8    9                11        12                                                                                                                                        80 LOSS OF OR OAhIAGE TO FACILITY TYPE        DESCRIPTION                    Q43
~IB                                                                                                                                                                                  80 7        8    9          10 ISSUED
              ~O44 PUBLICITY DESCRIPTION        ~                                                                                                                  NRC USE ONLY 7        8    9          10                                                                                                                      68    69                          80  ER 0
NAME OF PREPARER                    R. S. Keith                                                      PHDNE.        61 6    465 5901
 
h  ~.
RECEIVEO OOCUVFN~
CO>CIRCE    BESIDE U.S. NRC DIS TRIBUTION SERVICES BRANCH
 
CoP /
/W>ee~
L, i~Nolcw I
        ~
NIGHIG    8 PDIYE4  coN    IN DONALD C. COOK NUCLEAR PLANT P.O. Box 456, Bridgman, Michigan 49106 March 14, 1978 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Comnission 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 the following report is submitted:
RO 78-016/03L-O.
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.
R. Walsh, Esq.
G. Charnoff, Esq.                                     i~~ ~l, )S78 G. Olson J.M. Hennigan PNSRC J.F. Stietzel Dir.,   IE (30 copies)
Dir.,   MIPC (3 copies)
 
I t
    'I ~
II
        ~
I'
'li
 
NRC FORM 366                                                                                                                          U. S. NUCLEAR REGULATORY COMMISSION
{7-77) +~~ ~-
LICENSEE EVENT REPORT CONTROL BLOCK:                                                  O1                 {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I                                  6
~0 7      8 M    I      D LICENSEE CODE C    C      1Qs 14      15 0   0   0     0     0   0   0.0         0     0     0 25 Qs4 26 1     1   1 I.ICENSE'TYPE 1
30 Q4~Qs 57 CAT 58 CON'T
~0 7        8 SOURCE       L~JQ 60           61             DOCKET NUMBER               68 69       EVENT DATE                74      75      REPORT DATE        80 0
EVENT DESCRIPTION AND PROBABI.E CONSEQUENCES QIO UNIT     WAS OPERATING NORMALLY                         IN     ODE   1.
~03               FROM SERVICE AT 01                   30 HOURS         ON 2     1 5 78 FOR MAIl TENANCE.                       THE
~04             TION AS         RE     UIRED BY APPENDIX A TECH. SPEC
~os             HOUR.         THE CORRECT BREAKER ALIGNMENT WAS VERIFIED AT                                               1       5       UR
~06             REMAINED AT STE                   D
~0   7         CALLED UP
~OB                                                                                                                                                                                 80 7       8 9 SYSTEM               CAUSE         CAUSE                                                           COMP.           VALVE.
CODE               CODE       SUBCODE                 COMPONENT CODE                         SVBCODE         SUBCODE 7
g 8
                                  ~ZZ 9          10 Q>>
11 A Q>>       ~AQ>>
12              l3 Z   Z     Z     Z     Z     Z 18 Qs       ~ZQs 19
                                                                                                                                                          ~ZQs 20 SEaUENTIAL                           OCCURRENCE               REPORT                       REVISION EVENT YEAR                                 REPORT NO.                               CODE                   TYPE                         NO.
Q17 LERIRP REpoRT         ~78 21        22 Q
23
                                                                          ~01 24 6
26 Qx 27
                                                                                                                    ~03 28          29 QL 30
[J 31 QQ 32 ACTION FUTURE                   EFFECT           SHUTDOWN                                   ATTACHMENT             NPRDP         PRIME COMP.             COMPONENT TAKEN ACTION                   ON PLANT     ~
METHOD                   HOURS Q22         SUBMITTED           FORM SUB.         SUPPLIER           MANUFACTURER
              ~HO>>~ZO>>                       ~ZO20             &O21                                         MQss                 LzLIQ4           [zJQss                           O26 33         34                 35                 36             37                   40     41                   42               43             44             47
          ,   CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 027 o         THE EVENT WAS CAUSED BY THE UNIT SUPERVISOR FAILING TO RE UIRE HAVING THE BREAKER ALIGNMENT VERIFIED.                           THE     SHIFT OPERATING ENGINEER REINSTRUCTED THE UNIT                                             S P THE REQUIREMENTS FOR REMOVING VITAL EQUIPMENT FROM SERVICE WITH RESPECT TO PERFORM 1 3         ING SURVEILLANCE AS DIRECTED BY THE TECH. SPECS.                                                 AND OPERATING DEPARTMENT INSTRUCTIONS 4
80 7       8     9 FACILITY STATUS 6 Q>>         ~l0
                                  % POWER 0     Qss         NA OTHER STATUS      0 M30      METHOD OF DISCOVERY
                                                                                          'AQ>i PLA T                         T DISCOVERY DESCRIPTION 032 R
8   9               10               12     13                               44     45         46                                                                       80 ENGINEER ACTIVITY       CONTENT RELEASED OF REI.EASE Z   Q33     Z     Q34         NA AMOUNT OF ACTIVITY        ~                                                    LOCATION OF RELEASE        Q 7     8     9               10                                                       44           45                                                                           80 PERSONNEL EXPOSURES TYPE         DESCRIPTION Q3g 7      8
            ~00 9
NUMBER 0$11       12 ZQss 13 NA 80 PERSONNEL INJURIES 7       8   9                 11       12                                                                                                                                         80 LOSS OF OR DAMAGE TO FACILITY TYPE       DESCRIPTION                   Q43 7      8 IrJQs 9           10                                                                                                                                                       80 PUB L I CITY                                                                                                                                   NRC USE ONLY ISSUED       DESCRIPTION ~4.
o      ~Q44 7       8     9           10                                                                                                                       68  69                        80 o 0
R" S   ~ Ke'I th                                                     PHoNE'16               465-5901                     L NAMF PF PREPARER                                                                                                                                              0
 
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Revision as of 18:53, 20 October 2019

LER 1978-016-03L. Re Removal of Emergency Diesel Generator from Service for Maintenance
ML18219C210
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 03/14/1978
From: Shaller D
Indiana Michigan Power Co
To: James Keppler
NRC/RGN-III
References
LER 1978-016-03L
Download: ML18219C210 (9)


Text

REGULATORY I NFORI"IATION DISTRIBUTION, SYSTEN ( R IDS)

DISTRIBUTION FOR INCONING NATERIAL 50-315 REC: NRC QRG: SHALLER D V DOCDATE: 03/14/78 NRC IN 8c NI PWR DATE RCVD: 03/ 20/ 78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 LICENSEE EVENT REPT (RO 50-315/78-016l03L-0) ON 02/15/78 CONCERNING 1AB ENERGENCY DIESEL GENERATOR WAS REI"IOVED FROM SERVICE FOR MAINTENANCE AND THE BREAKER ALIGNMENT VERIFICATION AS REQUIRED BY TECH SPEC 4. 8. 1. 1. 1A WAS NOT PERFORNED WITHIN ONE HOUR.

PLANT MANE: COOK UNIT 1 REVIEWER INITIAL: X JN DISTRIBUTOR INITIAL: g, A

+~~~~~~~~~HI ~~~~~~~ DISTR I BUT ION OF THIS NATERIAL IS AS FOLLOWS +++~~~~~~~~~~~~~~~

INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION: EI4CER++W/4 ENCL INTERNAL: REG FILE4+W NCL NRC PDR++Wf ENCL NIPC++4f/3 ENCL SCHRQEDER/ IPPQL I TO+4 M/ENCL HOUSTQN4+W/ENCL NQVAK/CHECK++W/ENCL GRINES++W/ENCL KNIGHT44W/ENCL BUTLER++W/ENCL HANAUER++W/ENCL TEDESCO++W/ENCL EI SENHUT~+W/ENCL BAER44 WfENCL SHAO++W/ENCL VOLLMER/BUNCH++W/ENCL KREGER/ J. COLL INS4 +I Jf ENCL ROSA'WfENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR S ST. JOSEPH'I ++l JlENCL TIC++W/ENCL NSIC+4l J/ ENCL ACRS CAT B+4 W/1 6 ENCL I COPIES NOT SUBMITTED PER REGUIATORY GUIDE 10. 1 DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 780810 5 SIZE: iP+iP THE END

0 I 1

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Mmertoan OI HA 8 NICHIGAIlIPOIEER CONPAIIIY DONALD C. COOK NUCLEAR PLANT IE>gQig)P P()

~li ~f'I'frn

'8 P.O. Bov 458, Bridgman, Michigan 49106 u,s '"mc p 79pg March 14, 1978 COAIAIEGGEO

'~~ESS Qa l~

Hr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Comnission Region III 799 Roosevelt, Road Glen Ellyn, IL 60137 C'perating License DPR-58 Docket No. 50-315

Dear Hr. Keppler:

Pursuant to the requirements of Appendix A Technical Specifications the following report is submitted:

RO 78-016/03L-O.

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: I I I R.C. Callen HPSC P.W. Steketee, Esq.

R. Walsh, Esq.

G. Charnoff, Esq.

G. Olson J.M. Hennigan 780810015 PNSRC J.F. Stietzel Dir., IE (30 copies)

Dir., HIPC (3 copies)

]gooa./~ %

/ji

R NRC FRORhl 366 I7.77)

LlCENSEE EVENT REPORT CONTROL BLOCK: {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

~01 8 9 N I 0 C C LICENSEE CODE 1QE 14 15 0 0 0 0 0 0 0 LICENSE NUhIBER 0 0 0 0 25 QE4 26 1 1 1 LICENSE TYPE 1

30 OR~OR 57 CAT 58 CON'T

~01 7 8 SOU CE L~JQG 60 61 0

DOCKET NUMBER 68 Q 69 EVENT DATE 74 QB 75 REPORT DATE 80 OB EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 UNIT WAS OPERATING NORMALLY IN M D 1. T

~03 FROM SERVICE AT 0130 HOURS ON 2 15 78 FOR MAIf]TENANCE. H R TION AS RE UIRED BY APPENDIX A TECH. SPEC. 4... W

~OG HOUR. THE CORRECT BREAKER ALIGNMENT WAS VERIFIED AT 10 5 H UR

~OG REMAINED AT STEADY

~07 CALLED UPO . T

~OB 80 7 8 SYSTE'M CAUSE CAUSE COMP. VALVE.

CODE CODE SUBCODE COMPOiVENTCODE SUBCODE SUBCODE 8

~ZZ 9 10 Q>> ~AQ>>

11

~AQ>>

12 13 Z Z Z Z Z Z 18 Qi ~ZQEE 19

~Z 20 Q's 7

SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LER)RO RERRRE ACTION FUTURE EVENT YEAR

~78 21 22 EFFECT

~

23 SHUTDOWN

~01 24 REPORT NO.

6 26

~~

27

~03 28 ATTACHMENT CODE 29 NPRDX TYPE

~L 30

31 PRIME CohIP.

~P NO.

32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~22 SUBMITTED FORM'SUB. SUPPLIER MAiNUFACTURER

~HS~ZQ 33 34 L~JQ20 35 LZJO 36 37 40

~023 41

~Q24 42 MQ26 43 44 47 Q26 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 027 o THE EVENT WAS CAUSED BY THE UNIT SUPERVISOR FAILING TO RE UIRE HAVING THE BREAKER ALIGNMENT VERIFIED. THE SHIFT OPERATING ENGINEER REINSTRUCTED THE UNIT P THE REQUIREMENTS FOR REMOVING VITAL EQUIPMENT FROM SERVICE WITH RESPECT TO PERFORM-3 ING SURVEILLANCE AS DIRECTED BY THE TECH. SPECS. AND OPERATING DEPARTMENT INSTRUCTIONS 4

80 7 8 9 FACILITY STATUS 6 Oss ~io

% POWER o OE>>A OTHER STATUS ~

~30 hIETHOO OF DISCOVERY

~AQ>> P ANT STAT DISCOVERY DESCRIPTION Q32 Y

8 9 10 12 13 44 45 Bo 7

ACTIVITY CONTENT ENG INEER RELEASED OF REI.EASE AhIOUNT OF ACTIVITY~36 LOCATION OF RELEASE Q Z Q33 ~ZQ34 NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 0

NUi4IBER TYPE DESCRIPTION Q3B

~77 8

~00 0 12 Z Oss 13 NA 80 7 9 11 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR OAhIAGE TO FACILITY TYPE DESCRIPTION Q43

~IB 80 7 8 9 10 ISSUED

~O44 PUBLICITY DESCRIPTION ~ NRC USE ONLY 7 8 9 10 68 69 80 ER 0

NAME OF PREPARER R. S. Keith PHDNE. 61 6 465 5901

h ~.

RECEIVEO OOCUVFN~

CO>CIRCE BESIDE U.S. NRC DIS TRIBUTION SERVICES BRANCH

CoP /

/W>ee~

L, i~Nolcw I

~

NIGHIG 8 PDIYE4 coN IN DONALD C. COOK NUCLEAR PLANT P.O. Box 456, Bridgman, Michigan 49106 March 14, 1978 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Comnission 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 the following report is submitted:

RO 78-016/03L-O.

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.

R. Walsh, Esq.

G. Charnoff, Esq. i~~ ~l, )S78 G. Olson J.M. Hennigan PNSRC J.F. Stietzel Dir., IE (30 copies)

Dir., MIPC (3 copies)

I t

'I ~

II

~

I'

'li

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION

{7-77) +~~ ~-

LICENSEE EVENT REPORT CONTROL BLOCK: O1 {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

~0 7 8 M I D LICENSEE CODE C C 1Qs 14 15 0 0 0 0 0 0 0.0 0 0 0 25 Qs4 26 1 1 1 I.ICENSE'TYPE 1

30 Q4~Qs 57 CAT 58 CON'T

~0 7 8 SOURCE L~JQ 60 61 DOCKET NUMBER 68 0 69 EVENT DATE 74 75 REPORT DATE 80 0

EVENT DESCRIPTION AND PROBABI.E CONSEQUENCES QIO UNIT WAS OPERATING NORMALLY IN ODE 1.

~03 FROM SERVICE AT 01 30 HOURS ON 2 1 5 78 FOR MAIl TENANCE. THE

~04 TION AS RE UIRED BY APPENDIX A TECH. SPEC

~os HOUR. THE CORRECT BREAKER ALIGNMENT WAS VERIFIED AT 1 5 UR

~06 REMAINED AT STE D

~0 7 CALLED UP

~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE.

CODE CODE SUBCODE COMPONENT CODE SVBCODE SUBCODE 7

g 8

~ZZ 9 10 Q>>

11 A Q>> ~AQ>>

12 l3 Z Z Z Z Z Z 18 Qs ~ZQs 19

~ZQs 20 SEaUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT NO. CODE TYPE NO.

Q17 LERIRP REpoRT ~78 21 22 Q

23

~01 24 6

26 Qx 27

~03 28 29 QL 30

[J 31 QQ 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDP PRIME COMP. COMPONENT TAKEN ACTION ON PLANT ~

METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~HO>>~ZO>> ~ZO20 &O21 MQss LzLIQ4 [zJQss O26 33 34 35 36 37 40 41 42 43 44 47

, CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 027 o THE EVENT WAS CAUSED BY THE UNIT SUPERVISOR FAILING TO RE UIRE HAVING THE BREAKER ALIGNMENT VERIFIED. THE SHIFT OPERATING ENGINEER REINSTRUCTED THE UNIT S P THE REQUIREMENTS FOR REMOVING VITAL EQUIPMENT FROM SERVICE WITH RESPECT TO PERFORM 1 3 ING SURVEILLANCE AS DIRECTED BY THE TECH. SPECS. AND OPERATING DEPARTMENT INSTRUCTIONS 4

80 7 8 9 FACILITY STATUS 6 Q>> ~l0

% POWER 0 Qss NA OTHER STATUS 0 M30 METHOD OF DISCOVERY

'AQ>i PLA T T DISCOVERY DESCRIPTION 032 R

8 9 10 12 13 44 45 46 80 ENGINEER ACTIVITY CONTENT RELEASED OF REI.EASE Z Q33 Z Q34 NA AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE Q 7 8 9 10 44 45 80 PERSONNEL EXPOSURES TYPE DESCRIPTION Q3g 7 8

~00 9

NUMBER 0$11 12 ZQss 13 NA 80 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 7 8 IrJQs 9 10 80 PUB L I CITY NRC USE ONLY ISSUED DESCRIPTION ~4.

o ~Q44 7 8 9 10 68 69 80 o 0

R" S ~ Ke'I th PHoNE'16 465-5901 L NAMF PF PREPARER 0

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