ML18219B531

05/12/1978 Letter Licensee Event Report

ML18219B531
Person / Time
Site:	Cook
Issue date:	05/12/1978
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 1978-010-03L, LER 1978-024-03L
Download: ML18219B531 (7)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>

DISTRIBUTION FOR INCOMING MATERIAL 50-3i6 l~

REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 05/48/78 NRC IN 8. MI PWR DATE RCVD: 05/i8/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-010) ON 03/25/78 CONCERNING UNIT WAS AT 20 PERCENT CONDUCTING TURBINE STOP AND CONTROL TESTS. CONTROL VALVE A OPENED EXCESSIVELY WHILE CONTROL VALVE D. TAVG DECREASED TO LESS .THAN 541 DEGREE F. VIOLATING TECH 4MB p,.(. m/ A>7 C,O - o~ f/0 Z l Q PLANT NAME: COOK UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:

DISTRIBUTION OF, THIS MATERIAL IS AS FOLLOWS 4<44<<<+++<+++<+<+

NOTES:

1. SEND 3 COPIES OF ALL MATERIAL TO IS.E INCIDENT REPORTS (DISTRIBUTION CODE AOOZ)

FOR ACTION: B~H.IEF YiN. +4~W/4 ENCL INTERNAL: REG FILE44W/ENCL NRC PDR4~W/ENCL

~~t4WMN MIPC+~W/3 ENCL HOUSTON+<W/ENCL SCHROEDER/I PPOLI TO+4 W/ENCL NOVAK/CHECK++M/ENCL EEB~~W/ENCL KNIGHT++W/ENCL BUTLER++W/ENCL HANAUER++W/ENCL TEDESCO+4W/ENCL EI SENHUT44 W/ENCL BAER44W/ENCL SHAO++W/ENCL VOLLMER/BUNCH++W/ENCL KREGER/J. COLL INS++W/ENCL ROSA+4W/ENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR'S ST. JOSEPHr MI4'+W/ENCL TI C+~W/ENCL NS ICE% W/ENCL ACRS CAT 8>+W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 781380/23 SIZE: 1P+ir+iP p 4~

THE END %4%%4%%%%%%4'%4%4'4'4'%%%%%%%%%4%+%44'

II ND ANA & MICH GAN PDNER COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Blidgman, Michigan 49106 May 12, 1978 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region II I 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-74 Docket No. 50-316

Dear Mr. Keppler:

l Pursuant to the requirements of the Appendix A Technical Specifications the following reports are submitted:

RO 78-010/03L-O, and RO 78-024/03L-O.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan R.W. Jurgensen R.F. Kroeger R. Kilburn R.J Vol 1 en'PI

~

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)

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION

{7-77)

LICENSEE EVENT REPORT c

CONTROL BLOCK Qi (PLEASE PRINT OR TYPE AI.L REQUIRED INFORMATION)

I 6 ii 1 0 C C 2QR 14 15 0 0 0 0 0 0 LICENSE NUMBER 0 - 0 0Q04 25 26 1 1 LICENSE TYPE 1 1 30 Q4~QR57 CAT 58 7 8 9 LICENSEE CODE CON'T

~01 SOURCE L~JQB 0 5 Q Qs 0 5 I 2 7 8 Qs 68 69 EVENT DATE 74 75 REPORT DATE 80 7 8 60 61 DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 Durin surveillance test 20HP 4030.STP.007 no flow was indicated throu h check valve

~O3 CTS-120E. This constituted an inoperable spray additive flow path as re uired by

~o4 Technical Specification 4.6.2.2. This section of the containment s ray system was

~o 6 ta ged out for investigation and repairs.

~O6

~O7

~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 8

~sH 9 10 Q11 x Q17 ~x 12 O 13 z z z z z z 18 Q14 ~zO10 19

~z 20 O70 7

SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LF RIBO RRPRR7 ACTION FUTURE EVENT YEAR

~7) 21 22 EFFECT

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23 SHUTDOWN

~02 24 REPORT NO.

4 26 Q~

27

~gg 28 ATI'ACHMENT COD6 29 NPROQ TYPE

~i 30 PRIME COMP.

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31 No.

/P 32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

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~NQ24 42

+ZORR 43 44 Z 9 9 47 Oss CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o C faces was satisfactory. Flow indicator IFI-200 was disassembled and ins ected. No abnormalities were found. The containment s ra check valve CTS-120E and IFI-200 were 3 re-assembl ed and returned to service. "A subse uent f ow 1 test indi cated f ow 1 throu h 4 the-check valve. Th'e reason for the no flow indication could not be determ'ined;-=-

7 8 9 FACILITY STATUS  % POWER OTHER STATUS ~

~3O METHOD OF DISCOVERY Survei1 lance Testin DISCOVERY DESCRIPTION Q32 CH 1 0 8

~EQs 9

~05 10 0 Qs 12 13 N A 44

~BQR1 45 46 80 ACTIVITY RELEASEO OF RELEASE CONTENT AMOUNT OF ACTIVITY Q LOCATION OF RELEASE Q

~Z Q33 ~ZQ34 N A N A 7 8 9 10 11 44 45 80 PERSONNEL. EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 8

~00 9

0 11 Q07 ~ZQ>>

12 13 N A 80 PERSONNEL INJURIES NUMBER OESCRIPTIONQ41 s ~OO OQ40 NA .

80 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION 0 Q42 N A 7 8 9 10 80 P U 8 L I CITY NRC USE ONLY ISSUED DESCRIPTION ~S 44 CR O ~NQ44 N/A 7 GB 69 804 40 7 8 9 10 616-465-5901 0 NAME OF PREPARER

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NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7.77)

LICENSEE EVENT REPORT

~ i

~ 's~ ~ 'so,1o CONTROL BLOCK: Q1 (PLEASE PRINT OR TYPE ALL REOUIRED INFORMATION)

I 7

~01 8

M I D LICENSEE CODE C C 2 14 Qs 15 0 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 25 Qs 26 4 1 1 I.ICENSE TYPE 1 IQo~Qs 30 57 CAT 58 CON'T

~o 7 8 so'ROE ~LQ6 60 61 0 5 0 0 0 DOCKET NUMBER 3 1 6 68 Q 69 3

EVENT DATE B

74 QB0 75 5 1 2 REPORT DATE 7 8 Q EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 UNIT WAS AT 20 PERCENT POWER CONDUCTING TURBINE STOP AND CONTRO TESTS.

CONTROL VALVE A OPENED EXCESSIVELY WHILE TESTING CONTROL VALVE D. TiAVG

~O4 DECREASED TO LESS THAN 541 F IN VIOLATION OF APPENDIX A TECH. SPEC. 3.1

~O5 .1.5. THE REACTOR TRIPPED ON LO-LO STEAM GENERATOR LEVEL BEFORE ELECTRI

~OB CAL LOAD COULD BE DECREASED AND TAVG RESTORED TO GREATER THAN 541 F. AL

~o 7 L PROTECTION SYSTEMS FUNCTIONED PROPERLY AND THERE WAS NO ADVERSE EFFEC T ON THE HEALTH AND SAFETY OF THE PUBLIC.

7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE

~oe 7 8 9 CODE 10 Q11 CODE 11 I( Qls ~

SUBCODE 12

/13 SEQUENTIAL 13 COMPONENT CODE 18 OCCURRENCE Q14 "SUBCODE

~C 19 REPORT Q15 SUBCODE

~Z 20 Q16 REVISION EVENTYEAR REPORT NO. CODE TYPE NO.

Qo LERiRP ss'osI'78 21 22 Q

23

~01 24 0

26 QP 27

~03 28 29 QL 30 Q31 QO 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDC PRIME COMP. ~ COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~ES~Zge 33 34

~AQ ~CQ 35 36 37 0 0 0 9 40

+NQ 41

~NQ24 42

~XQ25 43 44 B 4 5 5 47 Q

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o THE CAP NUT FOR THE ADJUSTING SCREW FOR THE CONTROL VALVE SERVO VA VE OOSENED ENABLING THE ADJUSTING SCREW TO VIBRATE OUT OF DJ STME ORRECT THE PROBLEM ALL CONTROL VALVES WERE RESTROKED TO ASSURE PROPER A 3 DJUSTMENT AND THE CAP NUTS WERE VERIFIED AS BEING'IGHTENED~

4 7 8 9 80 FACILITY METHOD OF STATUS BG POWER OTHER STATUS QBO DISCOVERY DISCOVERY DESCRIPTION Q32

[ii~]

7 8 9 8 Qs ~0 10 2 0 Qs 12 13 VALVE TESTING 44

~PA' 45 46 OPERATOR OBSERVATION 80 ACTIVITY CONTENT 6

RELEASED OF RELEASE Z NA AMOUNT OF ACTIVITY Q NA LOCATION OF RELEASE Q

~Z Q33 Q34 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~00 0 O~ZQss 13 NA 80 7 8 9 11 12 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 7

s 8

~00 9

0 11 Qso 12 NA 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 e Z Q42 NA 7 8 9 10 80 PUBLICITY ISSUED DESCRIPTION Q NRC USE ONLY BIG 8 L~JQ44 9 10 NA 68 69 s

80 g 0

NAME OF PREPARER. S. KE:ITH (616) 465-5901 V

0 K T l