ML18219B538: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-316 REC: KEPPLER J G NRG-GRG: SHALLER D V IN 5 MI PWR DOCDATE: 04/25/78 DATE RCVD: 05/08f78 DOCTYPE: LETTER NOTARIZED:
{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
NO COPIES RECEIVED  
DISTRIBUTION FOR INCOMING MATERIAL                     50-316 REC: KEPPLER J     G               GRG: SHALLER D V               DOCDATE: 04/25/78 NRG-                                IN 5 MI PWR                  DATE RCVD: 05/08f78 DOCTYPE:     LETTER     NOTARIZED: NO                                 COPIES RECEIVED


==SUBJECT:==
==SUBJECT:==
LTR 1 ENCL FORWARDING LICENSEE EVENT REPT (RO 50-316/78-015/03L-0)
LTR 1   ENCL FORWARDING LICENSEE EVENT REPT (RO 50-316/78-015/03L-0) ON 03/22/78 CONCERNING DURING INITIAL PWR TESTING PROGRAM> ROD POSITION INDICATION FOR ROD D-12 WAS FOUND IN EXCESS OF THE PLUS MINUS 12 STEP LIMIT, GF TECH SPEC
ON 03/22/78 CONCERNING DURING INITIAL PWR TESTING PROGRAM>ROD POSITION INDICATION FOR ROD D-12 WAS FOUND IN EXCESS OF THE PLUS-MINUS 12 STEP LIMIT, GF TECH SPEC 3.i.3.2.PLANT NAME: COOK-UNIT 2 NOTES: i.SEND 3 COPIES OF ALL MATERIAL TO IZ.E INCIDENT REPORTS<DISTRIBUTION CODE A002)REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:~DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4++++<+<<<44+<<<<+
: 3. i. 3. 2.
FOR ACTION: INTERNAL: BR CH EF KNIEL++W/4 ENCL EG FILE<4 E CL.ENCL SCHROEDER/
PLANT NAME: COOK UNIT 2                                   REVIEWER DISTRIBUTOR  INITIAL:
IPPOLITO+4W/ENCL NOVAK/CHECK+4W/ENCL KNIGHT+4f Wf ENCL HANAUER~~fW/ENCL EISENHUT~f
                                                                                  ~
~W/ENCL SHAO++W/ENCL KREGER/J.COLLINS++W/ENCL K SEYFRIT/IE+4W/ENCL NRC PDR~~W/ENCL IIIPC+4W/3 ENCL HOUSTON4+W/ENCL EEB~+W/ENCL BUTLER++W/ENCL TEDESCO>+W/ENCL BAER~+W/ENCL VOLLMER/BUNCH+4W/ENCL ROSA4+Wf ENCL EXTERNAL: LPDR'S ST.JOSEPH'I++A/ENCL T I C+~W/ENCL NSIC~~W/ENCl ACRS CAT B~l 4W/16 ENCL DISTRIBUTION:
INITIAL: X JM DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4++++<+<<<44+<<<<+
LTR 45 ENCL 45 SIZE: iP+iP CONTROL NBR: 78128005 1 1 INDIANA&MICHIGAN PDNER CDMPANY DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 April 25, 1978 kf89<g<V nnpr CI cn~W&l MC7 P1~ca~~~ggJ~C Mr.J.G.Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevel t Road Glen Ellyn, IL 60137
NOTES:
: i. SEND 3 COPIES OF ALL MATERIAL TO IZ.E INCIDENT REPORTS
    <DISTRIBUTION CODE A002)
FOR ACTION:         BR CH EF   KNIEL++W/4 ENCL INTERNAL:            EG FILE<4   E CL .         NRC PDR~~W/ENCL ENCL              IIIPC+4W/3 ENCL SCHROEDER/ IPPOLITO+4W/ENCL    HOUSTON4+W/ENCL NOVAK/CHECK+4W/ENCL            EEB~+W/ENCL KNIGHT+4fWfENCL                BUTLER++W/ENCL HANAUER~~fW/ENCL                TEDESCO>+W/ENCL EISENHUT~f ~W/ENCL             BAER~+W/ENCL SHAO++W/ENCL                   VOLLMER/BUNCH+4W/ENCL KREGER/J. COLLINS++W/ENCL   ROSA4+Wf ENCL K  SEYFRIT/IE+4W/ENCL EXTERNAL:           LPDR'S ST. JOSEPH'I ++A/ENCL T I C+~W/ENCL NSIC~~W/ENCl ACRS   CAT B~l 4W/16 ENCL DISTRIBUTION:       LTR 45     ENCL 45                     CONTROL NBR:    78128005 SIZE: iP+iP


==Dear Me.Keppler:==
1 1 kf89<g<V nnpr INDIANA& MICHIGANPDNER CDMPANY                            CI DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106                              cn~
Operating License DPR-74 Docket No.50-316 Pursuant to the requirements of the Appendix A Technical Specifications, the fol loAing repor t i s submitted:
W&l MC7 April 25,    1978                                                            P1~
RO 78-015/03L-0 Sin ce rely, D.V.Shaller Plant Manager/pk cc: J.E.Dolan R.W.Jurgensen R.F.Kroeger R.Kilburn R.J.Vollen BPI K.R.Baker RO:III R.C.Callen MPSC P.W.Steketee, Esq.R.Wal sh, Esq.G.Charnoff, Esq.J.M.Hennigan G.Olson PNSRC J.F.Stietzel Dir., IE (30 copies)Dir., MIPC (3 copies)78i280053 4 APR'P 8'j978lI,o c a a 1 Et NRC FORM 366 U.S.NUCLEAR REGULATORY COMMISSION (7-77)LICENSEE EVENT REPORT CONTROL BLOCK: Qi (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
ca~~
I 6~ol M I D C C 2 Qo 0 0 0 0 0 0 0 0 0 0 0 Qo 4 1 1 1 1 Q4~Q5 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE'0 57 CAT 58 CON'T 555~5'5 MLOO 1 6 QO 3 2 2 7 8 QO 4 Q 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10[oa~j DURING THE INITIAL POWER TESTING PROGRAM.ROD P SI FOUND TO BE IN EXCESS OF THE+12 STEP LIMIT OF T.S.3.1.3.2.PREVIOUS OCCURRENCE
                                                                            ~ ggJ
~os NUMBERS INCLUDE: RO-050/315-78-07-04,77-34,33,28,27, 76-54,44,13 050/316-78-08,07.
                                                                            ~C Mr. J. G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region  III 799 Roosevel    t  Road Glen Ellyn,    IL 60137 Operating License DPR-74 Docket No. 50-316
~O6~O7~OS 80 7 8 9 7l 8 RODS IN THIS BANK.THE SIGNAL CONDITIONING MODULE WAS ADJUSTED FOR PROPER RPI ALIGNMENT.
 
THE ACTION REQUIREMENTS OF T.S.WERE FULFILLED.
==Dear Me. Keppler:==
3 4 80 7 8 9 FACILITY 3P METHOD OF STATUS 56 POWER OTHER STATUS~DISCOVERY~lg 8 Qog~00 7 Q29 NA'~AQgl 7 8 9 10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY~I-g-g z Q33 LzlQ34 NA 7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
 
~39~00 0 Q"~2Qgg NA 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41
Pursuant to the requirements of the Appendix   A Technical Specifications, the fol loAing repor t i s submitted:
~OO OQ NA DISCOVERY DESCRIPTION Q32 OPERATOR OBSERVATION 80 LOCATION OF RELEASE Q NA 80 80 7 8 80 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION z Q4.9 10 PUBLICITY ISSLIED DESCRIPTION
RO   78-015/03L-0 Sin ce rely, D. V. Shaller Plant Manager
~~~Q44 9 10 NA 80 7 8 NRC USE ONLY 5 80 o 0 o 68 69 616-465-5901 8 JOCk pjqChlj,ng NAME OF PREPARER SYSTEM CAUSE, CAUSE COMP.VALVE, CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~OB~IE Qll E Q12~EQu I N S T R U Qlg~YQ5~Z Q'5 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RP EVENT YEAR REPORT NO.CODE TYPE NO.Qlv Rgoogv~78~~01 5~~~03~L~~0 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDX PRIME COMP.COMPONENT TAKEN ACTION ON PLANT~METHOD HOURS O22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER
/pk cc: J. E. Dolan R. W. Jurgensen R. F. Kroeger R. Kilburn R. J. Vollen BPI K. R. Baker RO:III R. C. Callen MPSC P. W. Steketee, Esq.
~EQlg~ZQlg~ZQoo~ZQ21 0 0 0 0+N Qgg~YQ55~NQ25 W 1 2 0 Qog 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o INVESTIGATION REVEALED THAT THE COIL STACK VOLTAGE OF D-12 IIAS IDENTICAL TO OTHER I C I'}}
R. Wal sh, Esq.
G. Charnoff, Esq.
J. M. Hennigan G. Olson PNSRC J. F. Stietzel                                 78i280053 Dir.,   IE (30 copies)
Dir.,   MIPC (3 copies) 4 APR 'P 8'j978    lI,o c
 
a a 1
Et
 
NRC FORM 366                                                                                                                           U. S. NUCLEAR REGULATORY COMMISSION (7-77)
LICENSEE EVENT REPORT CONTROL BLOCK:                                                 Qi                   (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I                                 6
~ol       8    9 M     I     D     C LICENSEE CODE C     2 14 Qo 15 0   0   0     0     0     0 LICENSE NUMBER 0     0     0     0     0 25 Qo 26 4     1   1 LICENSE 1
TYPE'0 1 Q4~Q5 57 CAT 58 CON'T 7        8 555~5'5     MLOO 60            61              DOCKET NUMBER 1     6 68 QO 69 3     2     2 EVENT DATE 7     8 74 QO75        4 REPORT DATE         80 Q
EVENT DESCRIPTION AND PROBABLE CONSEQUENCES                               Q10
[oa~j           DURING THE             INITIAL POWER TESTING                     PROGRAM.             ROD P       SI FOUND TO BE IN EXCESS OF THE + 12 STEP                                         LIMIT OF         T. S.       3.1.3.2.           PREVIOUS OCCURRENCE
~os NUMBERS INCLUDE:                     RO-050/315-78-07-04,77-34,33,28,27,                                     76-54,44,13                     050/316-78-08,07.
~O6
~O7
~OS                                                                                                                                                                                   80 7         8 9 SYSTEM CODE CAUSE,SUBCODECAUSE COMPONENT CODE COMP.            VALVE, CODE                                                                        SUBCODE          SUBCODE
~OB 7l       8                       9
                                    ~IE        10 Qll 11 E    Q12  ~EQu 12                13 I    N    S    T    R    U 18 Qlg      ~YQ5 19
                                                                                                                                                            ~Z 20 Q'5 SEQUENTIAL                              OCCURRENCE              REPORT                      REVISION Qlv LER/RP Rgoogv ACTION FUTURE EVENT YEAR
                                    ~78 21          22 EFFECT
                                                            ~
23 SHUTDOWN
                                                                          ~01 24 REPORT NO.
5 26
                                                                                                      ~~
27
                                                                                                                      ~03 28 ATTACHMENT CODE 29 NPRDX TYPE
                                                                                                                                              ~L 30 PRIME COMP.
                                                                                                                                                              ~
31
                                                                                                                                                                        ~0 NO.
32 COMPONENT TAKEN ACTION                  ON PLANT    ~
METHOD                    HOURS O22          SUBMITTED          FORM SUB.        SUPPLIER          MANUFACTURER
                ~EQlg ~ZQlg                    ~ZQoo            ~ZQ21              0    0    0      0        +N      Qgg        ~YQ55            ~NQ25            W    1    2 0    Qog 33        34                  35                36            37                      40      41                  42              43            44              47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o        INVESTIGATION REVEALED THAT THE COIL STACK VOLTAGE OF D-12 IIAS IDENTICAL TO OTHER RODS     IN THIS BANK.                   THE SIGNAL CONDITIONING MODULE WAS ADJUSTED FOR PROPER                                                   RPI ALIGNMENT.               THE ACTION REQUIREMENTS OF                           T. S.       WERE     FULFILLED.
3 4
8                                                                                                                                                                          80 9
                                                                                  ~
7 FACILITY                                                               3P       METHOD OF STATUS             56 POWER                       OTHER STATUS               DISCOVERY                                  DISCOVERY DESCRIPTION Q32
                                                                                        '
~lg 8
Qog     ~00 10 7   Q29           NA 44
                                                                                                ~AQgl 45 OPERATOR OBSERVATION 80 7             9                               12     13                                                   46 I-g-g ACTIVITY     CONTENT RELEASED OF RELEASE z   Q33     LzlQ34 AMOUNTOF ACTIVITY NA
                                                                                ~                                    NA LOCATION OF RELEASE      Q 7       8   9             10           11                                         44             45                                                                           80 PERSONNEL EXPOSURES NUMBER               TYPE         DESCRIPTION ~39
              ~00           0 Q" ~2Qgg                           NA 80 7         8   9               11       12           13 PERSONNEL INJURIES NUMBER               DESCRIPTIONQ41 7        8
              ~OO 9
OQ 11      12 NA 80 LOSS OF OR DAMAGE TO FACILITY TYPE       DESCRIPTION                     Q43 z   Q4.                                           NA 7        8    9         10                                                                                                                                                         80 o
PUBLICITY ISSLIED
              ~~Q44 DESCRIPTION        ~                                                                                                                   NRC USE ONLY 5
8    9          10                                                                                                                        68    69                        80 o JOCk      pjqChlj,ng                                                            616-465-5901                       0 NAME OF PREPARER
 
I C
I'}}

Revision as of 19:56, 20 October 2019

04/25/1978 Letter Licensee Event Report
ML18219B538
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 04/25/1978
From: Shaller D
American Electrtic Power System, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To: James Keppler
NRC/IE, NRC/RGN-III
References
LER 1978-015-03L
Download: ML18219B538 (6)


Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-316 REC: KEPPLER J G GRG: SHALLER D V DOCDATE: 04/25/78 NRG- IN 5 MI PWR DATE RCVD: 05/08f78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL FORWARDING LICENSEE EVENT REPT (RO 50-316/78-015/03L-0) ON 03/22/78 CONCERNING DURING INITIAL PWR TESTING PROGRAM> ROD POSITION INDICATION FOR ROD D-12 WAS FOUND IN EXCESS OF THE PLUS MINUS 12 STEP LIMIT, GF TECH SPEC

3. i. 3. 2.

PLANT NAME: COOK UNIT 2 REVIEWER DISTRIBUTOR INITIAL:

~

INITIAL: X JM DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4++++<+<<<44+<<<<+

NOTES:

i. SEND 3 COPIES OF ALL MATERIAL TO IZ.E INCIDENT REPORTS

<DISTRIBUTION CODE A002)

FOR ACTION: BR CH EF KNIEL++W/4 ENCL INTERNAL: EG FILE<4 E CL . NRC PDR~~W/ENCL ENCL IIIPC+4W/3 ENCL SCHROEDER/ IPPOLITO+4W/ENCL HOUSTON4+W/ENCL NOVAK/CHECK+4W/ENCL EEB~+W/ENCL KNIGHT+4fWfENCL BUTLER++W/ENCL HANAUER~~fW/ENCL TEDESCO>+W/ENCL EISENHUT~f ~W/ENCL BAER~+W/ENCL SHAO++W/ENCL VOLLMER/BUNCH+4W/ENCL KREGER/J. COLLINS++W/ENCL ROSA4+Wf ENCL K SEYFRIT/IE+4W/ENCL EXTERNAL: LPDR'S ST. JOSEPH'I ++A/ENCL T I C+~W/ENCL NSIC~~W/ENCl ACRS CAT B~l 4W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 78128005 SIZE: iP+iP

1 1 kf89<g<V nnpr INDIANA& MICHIGANPDNER CDMPANY CI DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 cn~

W&l MC7 April 25, 1978 P1~

ca~~

~ ggJ

~C Mr. J. G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevel t Road Glen Ellyn, IL 60137 Operating License DPR-74 Docket No. 50-316

Dear Me. Keppler:

Pursuant to the requirements of the Appendix A Technical Specifications, the fol loAing repor t i s submitted:

RO 78-015/03L-0 Sin ce rely, D. V. Shaller Plant Manager

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

R. Wal sh, Esq.

G. Charnoff, Esq.

J. M. Hennigan G. Olson PNSRC J. F. Stietzel 78i280053 Dir., IE (30 copies)

Dir., MIPC (3 copies) 4 APR 'P 8'j978 lI,o c

a a 1

Et

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7-77)

LICENSEE EVENT REPORT CONTROL BLOCK: Qi (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

~ol 8 9 M I D C LICENSEE CODE C 2 14 Qo 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 0 25 Qo 26 4 1 1 LICENSE 1

TYPE'0 1 Q4~Q5 57 CAT 58 CON'T 7 8 555~5'5 MLOO 60 61 DOCKET NUMBER 1 6 68 QO 69 3 2 2 EVENT DATE 7 8 74 QO75 4 REPORT DATE 80 Q

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10

[oa~j DURING THE INITIAL POWER TESTING PROGRAM. ROD P SI FOUND TO BE IN EXCESS OF THE + 12 STEP LIMIT OF T. S. 3.1.3.2. PREVIOUS OCCURRENCE

~os NUMBERS INCLUDE: RO-050/315-78-07-04,77-34,33,28,27, 76-54,44,13 050/316-78-08,07.

~O6

~O7

~OS 80 7 8 9 SYSTEM CODE CAUSE,SUBCODECAUSE COMPONENT CODE COMP. VALVE, CODE SUBCODE SUBCODE

~OB 7l 8 9

~IE 10 Qll 11 E Q12 ~EQu 12 13 I N S T R U 18 Qlg ~YQ5 19

~Z 20 Q'5 SEQUENTIAL OCCURRENCE REPORT REVISION Qlv LER/RP Rgoogv ACTION FUTURE EVENT YEAR

~78 21 22 EFFECT

~

23 SHUTDOWN

~01 24 REPORT NO.

5 26

~~

27

~03 28 ATTACHMENT CODE 29 NPRDX TYPE

~L 30 PRIME COMP.

~

31

~0 NO.

32 COMPONENT TAKEN ACTION ON PLANT ~

METHOD HOURS O22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~EQlg ~ZQlg ~ZQoo ~ZQ21 0 0 0 0 +N Qgg ~YQ55 ~NQ25 W 1 2 0 Qog 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o INVESTIGATION REVEALED THAT THE COIL STACK VOLTAGE OF D-12 IIAS IDENTICAL TO OTHER RODS IN THIS BANK. THE SIGNAL CONDITIONING MODULE WAS ADJUSTED FOR PROPER RPI ALIGNMENT. THE ACTION REQUIREMENTS OF T. S. WERE FULFILLED.

3 4

8 80 9

~

7 FACILITY 3P METHOD OF STATUS 56 POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q32

'

~lg 8

8 Qog ~00 10 7 Q29 NA 44

~AQgl 45 OPERATOR OBSERVATION 80 7 9 12 13 46 I-g-g ACTIVITY CONTENT RELEASED OF RELEASE z Q33 LzlQ34 AMOUNTOF ACTIVITY NA

~ NA LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION ~39

~00 0 Q" ~2Qgg NA 80 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 7 8

~OO 9

OQ 11 12 NA 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 z Q4. NA 7 8 9 10 80 o

PUBLICITY ISSLIED

~~Q44 DESCRIPTION ~ NRC USE ONLY 5

8 9 10 68 69 80 o JOCk pjqChlj,ng 616-465-5901 0 NAME OF PREPARER

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