05000316/LER-2078-010-03, Letter Licensee Event Report

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)

LER-2078-010, Letter Licensee Event Report

Event date:
Report date:
3162078010R03 - NRC Website

text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>

DISTRIBUTION FOR INCOMING MATERIAL 50-3i6 REC:

KEPPLER J G

NRC ORG:

SHALLER D V IN 8. MI PWR l~

DOCDATE: 05/48/78 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:

XJM 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:

INTERNAL:

EXTERNAL:

B~H.IEF YiN.

+4~W/4 ENCL REG FILE44W/ENCL

~~t4WMN SCHROEDER/I PPOLI TO+4 W/ENCL NOVAK/CHECK++M/ENCL KNIGHT++W/ENCL HANAUER++W/ENCL EISENHUT44 W/ENCL SHAO++W/ENCL KREGER/J.

COLLINS++W/ENCL K SEYFRIT/IE++W/ENCL LPDR'S ST.

JOSEPHr MI4'+W/ENCL TIC+~W/ENCL NS ICE% W/ENCL ACRS CAT 8>+W/16 ENCL NRC PDR4~W/ENCL MIPC+~W/3 ENCL HOUSTON+<W/ENCL EEB~~W/ENCL BUTLER++W/ENCL TEDESCO+4W/ENCL BAER44W/ENCL VOLLMER/BUNCH++W/ENCL ROSA+4W/ENCL DISTRIBUTION:

LTR 45 ENCL 45 SIZE:

1P+ir+iP CONTROL NBR:

781380/23 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 III 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 1en'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

{7-77)

U. S. NUCLEAR REGULATORY COMMISSION 7

8 CON'T

~01 7

8 c

CONTROL BLOCK SOURCE L~JQB 0

5 Q

60 61 DOCKET NUMBER 68 69 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 Durin surveillance test 20HP 4030.STP.007 Qs 0

5 I

2 7

8 Qs EVENT DATE 74 75 REPORT DATE 80 no flow was indicated throu h check valve LICENSEE EVENT REPORT Qi (PLEASE PRINT OR TYPE AI.LREQUIRED INFORMATION)

I 6

ii 1

0 C

C 2QR 0

0

0 0

0 0

0 0 0Q04 1

1 1

1 Q4~QR 9

LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58

~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 7

8 9

80 7

8 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~sH Q11 x

Q17

~x O z

z z

z z

z Q14

~zO10

~z O70 9

10 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LF RIBO EVENTYEAR REPORT NO.

COD6 TYPE No.

Q17 RRPRR7 ~7)

~

~02 4

Q~

~gg

~i

~

/P 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATI'ACHMENT NPROQ PRIME COMP.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.

SUPPLIER MANUFACTURER

~S~Q

~Q2O

~Q21 QN.. Q>>

~NQ24

+ZORR Z

9 9

Oss 33 34 35 36 37 40 41 42 43 44 47 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 f1 ow test indicated f1 ow throu h

4 the-check valve.

Th'e reason for the no flow indication could not be determ'ined;-=-

CH ACTIVITY CONTENT RELEASEO OF RELEASE AMOUNTOF ACTIVITYQ

~Z Q33

~ZQ34 N A 7

8 9

10 11 44 PERSONNEL. EXPOSURES NUMBER TYPE DESCRIPTION Q39

~00 0

Q07 ~ZQ>>

N A 7

8 9

11 12 13 PERSONNEL INJURIES NUMBER OESCRIPTIONQ41 s

~OO OQ40 NA 80 LOCATION OF RELEASE Q N A 80 45 80 80 9

11 12 LOSS OF OR DAMAGETO FACILITY 43 TYPE

DESCRIPTION

0 Q42 N A 7

8 80 NRC USE ONLY 44 CR 7

804 40 0

7 8

9 10 P U8 L ICITY ISSUED DESCRIPTION ~S

~NQ44 N/A 9

10 O

GB 69 616-465-5901 7

8 NAME OF PREPARER 7

8 9

FACILITY

~3O METHOD OF STATUS

% POWER OTHER STATUS ~

DISCOVERY DISCOVERY DESCRIPTION Q32 1

0

~EQs

~05 0

Qs N A

~BQR1 Survei1 lance Testin 8

9 10 12 13 44 45 46

~

r, ~'

t

NRC FORM 366 (7.77)

U. S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT Q1 (PLEASE PRINT OR TYPE ALLREOUIRED INFORMATION) 2 Qs 0

0 0

0 0

0 0

0 0

0 0

Qs 4

1 1

1 IQo~Qs 14 15 LICENSE NUMBER 25 26 I.ICENSE TYPE 30 57 CAT 58

~

i ~'s~

~ 'so,1o CONTROL BLOCK:

I

~01 7

8 CON'T

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I D

C C

LICENSEE CODE 7

8 so'ROE ~LQ6 0

5 0

0 0

3 1

6 Q 3

B QB0 5

1 2

7 8 Q 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 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

~oe SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE "SUBCODE SUBCODE Q11 I(

Qls ~ /13 Q14

~C Q15

~Z Q16 7

8 9

10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERiRP EVENTYEAR REPORT NO.

CODE TYPE NO.

Qo ss'osI'78 Q

~01 0

QP

~03 QL Q

QO 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDC PRIME COMP.

~

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.

SUPPLIER MANUFACTURER

~ES~Zge

~AQ

~CQ 0

0 0

9

+NQ

~NQ24

~XQ25 B

4 5

5 Q 33 34 35 36 37 40 41 42 43 44 47 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

FACILITY STATUS BG POWER OTHER STATUS QBO [ii~]

8 Qs

~0 2

0 Qs VALVE TESTING 7

8 9

10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ 6

~Z Q33 Z Q34 NA 7

8 9

10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~00 0 O~ZQss NA 7

8 9

11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 s

~00 0

Qso NA 7

8 9

11 12 LOSS OF OR DAMAGETO FACILITYQ43 TYPE

DESCRIPTION

e Z

Q42 NA 7

8 9

10 PUBLICITY ISSUED DESCRIPTIONQ BIG L~JQ44 NA 8

9 10 NAME OF PREPARER. S.

KE:ITH 80 80 80 80 80 80 NRC USE ONLY s

80 g 0

V 68 69 (616) 465-5901 METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32

~PA' OPERATOR OBSERVATION 45 46 LOCATIONOF RELEASE Q NA 45

0 K

T l