ML17317B467

Forwards Updated LERs 78-065/03X-1,79-022/03X-1, 79-030/03X-1,79-038/03L-0 & 79-039/03L-0

ML17317B467
Person / Time
Site:	Cook
Issue date:	08/15/1979
From:	Shaller D INDIANA MICHIGAN POWER CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17317B468	List: ML17317B467 ML17317B471 ML17317B473 ML17317B474 ML17317B475 ML19249A279
References
NUDOCS 7908210517
Download: ML17317B467 (17)

Text

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D C 8 D COJP+Q/g DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 I

August 15, 1979 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-58 Docket No. 50-315

Dear Mr. Keppler:

Pursuant to the requirements of the Appendix A Technical Specifications the following report/s are submitted:

R0.78-065/03X-1 RO 79-022/03X-1 RO 79-030/03X-1 RO 79-038/03L-0 RO 79-039/03L-0 Sincerely, D.V. Shaller Plant Manager cc: JOE. Dolan R.W. Jurgensen R.F. Kroeger R. Kilburn R.J. Vollen BPI R.E. Masse 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 AUG 20 t979 Dir., IE (30 copies)

Dir., MIPC (3 copies)

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"UPDATF~PORT PREVIOUS REPORT SUBMIT+ 1gl6$ 9 EVENT REPORT 'tLICENSEE CONTROL BLOCK: Q1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

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7 8 9 M I D LICENSEE CODE C C 1 14 Q2 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 Op 264 1 LICENSE 1 1 TYPE'0 1 0~ps 57 CAT 58 CON'T

[os] " " ~l-Qs 0 5 0 0 0 3 1 5 Q1 1 2 2 9 7 8 Qs 0 9 I 5 7 9 Q9 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES ~10 ON 12-29-78 INDI'CATION FOR PRESSURIZER LEVEL CHANNEL TWO WAS FOUND TO BE READING APPROX IMATELY5 PER CENT LOWERTHAN CHANNE;L-ONE AND APPROX IMATELY3 PER CENT LOWER THAN CHANNEL THREE. THE CHANNEL TWO BISTABLES WERE PLACED IN THE TRIP MODE PURSUANT STOT.S.TABLE 3.3-3 I'TEM1 0 ACTION STATEMENT 148,SIMILAR OCCURRENCES INCLUDE RO 050-315/78-10,41,59 AND 050-315/78-61,

~O7

~OS 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENTCODE SUBCODE SUBCODE

~OB ~IB 9 10 Q11 X Q12 ~Z Q13 13 I N S T R U Q14 18

~T 19 Q15 ~Z 20 Qls 7 8 11 12 SEQUENTIAL OCCURRENCE REPORT R EV I 8 I ON Q11 LF RiRO Rsooov ACTION FUTURE EVENT YEAR

~78 21 22 EFFECT

+

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~06 24 REPORT NO.

5 26 Q~

27

~03 28 ATTACHMENT CODE 29 NPRDQ TYPE QX 30 PRIME COMP.

[J 31 NO.

32 1

COMPONENT

~ ~ ~ ~

SHUTDOWN TAKEN ACTION ON PJ,ANT ME'DIOD HQURS (222 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER gJQ19 Q19 Q29 Q21 QJ Q23 Q24 ~N Qos 8 D 8 0 Q25 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 THROUGH INVESTIGATION IT WAS DISCOVERED THAT CHANNEL ONE, NOT CHANNEL TWO WAS THE INOPERABLE CHANNEL. UPON DISCOVERY, THE CHANNEL TWO BISTABLES WERE RESTORED TO NORMAL AND CHANNEL ONE WAS PLACED IN TRI'P, THE CAUSE OF THE HIGH INDICATION WAS ATT R I B U T E D TO A G AS P 0 C KE T L0 CAT E D IN T H E S E IN S I N G L I N E AN D U P 0 N R E PA I RAND 3

RESTORATION INDICATION RETURNED TO NORMAL. SEE SUPPLEMENT, 7 8 9 80 FACILITY METHOD OF QBO 7

5, 8

STATUS 9

D Q29 ~Q29 10 Yo 0

POWER 0 0 12 13 OTHER STATUS NA 44 DISCOVERY

~BQ31 45 CHANNEL CHECK DISCOVERY DESCRIPTION Q32 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q LOCATION OF RELEASE Q 7 8

~Z Q" ~Q34 9 '0 PERSONNEL EXPOSURES 11 44 45 NA 80 NUMBER TYPE DESCRIPTION Q39

~l7 ~00 0 Q31 ~ZQ39 13 NA 80 7 8 9 11 12 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY Q43 7 8 9 z

Q 10 NA 80 O

ISSUED

~NQ4 PUBLICITY DESCRIPTION ~ NA NRC USE ONLY 19 94 49 2

7 8 9 10 68 69 80 49 T. P. Beilman 616-465-5901 0 0.

NAME OF PREPARER 49

SUPPLEMENT TO LER g 78-065/03X-1 SUPPLEMENT TO CAUSE DESCRIPTION THE EVENT ORIGINALLY REPORTED UNDER RO-050-315/78-065, REVISION 0 AND AS AMMENDED IN THXS REPORT IS NOT LONGER A REPORTABLE OCCURRENCE AS DEFINED BY T.S. PARAGRAPH 6.9.1.9 DUE TO A RECENT T.S. AMMEND-MENT WHICH DELETED ALL PRESSURXZER LOW LEVEL OPERABILITY REQUIRE-MENTS.

THE DESXGN CHANGE (RFC-12-1598) WHICH WAS PREPARED TO CORRECT THE RECURRENT PRESSURXZER LEVEL PIPING PROBLEM HAS BEEN CANCELLED DUE TO THE T.S. AMMENDMENT AND RESULTING PLANT MODIFICATXONS.

NRC FORM 366 U. S UCLEAR REGULATORY COMMISSION I7-77 I ~ "UPDATQaiREPORT - PREVIOUS REPORT DATE 4 79"

~lCENSEE EVENT REPORT I

CONTROL BLOCK: Q1 {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6

~01 7 8 9 LICENSEE CODE G 0 1Q2 14 15 0 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0Q24 25 26 1 1 LICENSE TYPE 1 1Q4~Qs 30 57 CAT 58 CON'T

[OD1] REP RT IL 1~60 5 0 0 0 3 1 5 Q70 QS 0 S Z 5 7 9 Qe SOURCE 80 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Qlo DURING A BATTERY EQUALIZING CHARGE OF THE CD BATTERIES, TWO 120 VOLT

~03 A.C.'ITAL BUSSES FAILED NEARLY SIMULTANEOUSLY CAUSXNG A REACTOR TRIP

~04 AND SAFETY INJECTION. THE RESTORATION TIME LIMIT SPECIFIED BY

~06 T.S. 3.8.2.1 ' WAS. OBSERVED WHILE THE VITAL BUSSES WERE REPAIRED AND RETURNED TO SERVICE.

~06

~07

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

~EE A ~AQ2 G E N E R A 7, 8 9 10 Q>>

11 Q2 12 SEQUENTIAL 13 18 OCCURRENCE Q14 ~FQ10 19 REPORT

~Z 20 Q10 REVISION 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP. COMPONENT TAKEN ACTION pJQ12 33 pJ 34 Q19 ON PLANT

~~Q20 35 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS ~27

~

METHOD 36 Q21 37 HOURS +22 E

40 SUBMITTED pf 41 Q22 FORM SUB.

~~Q24 42 SUPPLIER

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43 Qss 0 44 MANUFACTURER Z 0 0 47 Qs O

THE BATTERY EQUALIZING CHARCR WAS APPARENTLY IN EXCESS OF THE DC XNPUT LIMXT. INVERTER FAILURE OCCURRED UPON MALFUNCTION OF SEVERAL INTERNAL, ELECTRONIC PARTS. THE PARTS WERE REPLACED AND THE INVERTERS WERE RETURNED TO SERVXCE AFTER VERIFYING PROPER OPERATXON.

S SEE SUPPLEMENT.

7 8 9 80 FACILITY Q METHOD OF 7

s 8

~

STATUS 9

E Qss ACTIVITY CONTENT

~Q20 1

10

% POWE R 0 0 12 13 OTHER STATUS NA 44 DISCOVERY

~AQsl 45 46 OPERATIONAL EVER DISCOVERY DESCRIPTION Q32 80

'ss RELEASED OF RELEASE AMOUNTOF ACTIVITY Q LOCATION OF RELEASE Q EKI 7 8 9 WQ34 10 NA 44 45 NA 80 PERSONNEL EXPOSURES 7 8 9 11 12 13 80 PERSONNEL INJURIES 7 8'9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z

Q42 7 8 9 10 80 PUBLICITY NRC USE ONLY m2 cV a

mIQ44 7 8 9 10 68 69 80 a T. P. Beilman PHONE 616-465-5901 0 NAME OF PREPARER

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ATTACHMENT TO LER 479-022/03X-1 SUPPLEMENT TO CAUSE'ESCRIPTION TO PREVENT RECURRENCE, THE BATTERY EQUALIZING CHARGE HAS BEEN REDUCED FROM 280 VOLTS TO 275 VOLTS WHICH PROVIDES A MORE'ONSERVATXVE MARGIN BETWEEN CHARGE VOLTAGE AND THE INVERTER'D.C. INPUT LIMIT. ADDITIONALL'Y A DESXGN CHANGE (RFC-12-1729) HAS BEEN REQUESTED TO PROVXDE AN OVER-VOLTAGE ALARM ON THE BATTERY CHARGER OUTPUT TO ALERT OPERATORS IF THE CHARGE VOLTAGE EXCEEDS 2 8 0 VOLTS i WHICH IS THE MANUFACTURERS UPPER D.C. XNPUT LXMXT,

NRC FORM 366 U. S UCLEAR REGULATORY COMMISSION I7-77) ~ "UPDATE ~RTtCENSEE PREVIOUS REPORT DATE 5/16 Qf EVENT REPORT CONTROL BLOCK: QE {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6 7 8 9 M I D C C zQ20 14 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 25 QE 26 LICENSE TYPE "3 QC~QE30 57 CAT 58 LICENSEE CODE CON'T 7 8 REPDRT

~LQB 0 60 61 5 0 0 0 DOCKET NUMBER 3 1 5 68 Q70 69 4 1 EVENT PATE 74 QS 0 75 8 1 5 REPORT DATE 7 9 80 Q

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 WHILE PERFORMING A ROUTINE SURVETLL'ANCE TEST ON THE AB DIESEL GENERATOR IN ACCORDANCE WXTH T . S . 4 . 8 . 1 . 1 . 2 . b . 3 THE LOAD CONSERVAT ON I 4

CXRCU ITRY D ID NOT FULLY FUNCTION AS REQUXRED ~

~06

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[779 J 21 22 EFFECT ~

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~03 28 ATTACHMENT CODE 29 NPRDQ TYPE

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TQKEN ACTION 33 Q16 ~Q19 34 ON /LANT

~Q20 35 CAUSE DESCRIPTION AND CORRECTIVE "ACTIONS MET)IOD

~Q21 36 37 Q27 HOUR/ i+22 40

~

SUBMITTED 41 Q23 FORM SUB.

PJQ24 42 SUPPLIER

~Q25 43 44 MANUFACTURER 47 Q26 INVEST IGATXON REVEALED I THAT A RELAY FA LED TO SUCCESSFULLY SEAL IN ALLOWING THE CIRCUXT TO MAINTAIN VARIOUS NON-ESSENTIAL LOADS WHICH SHOULD HAVE DEENERGXZED DURING A NORMAL SEQUENCE. AS PREVENTATIVE ACTION DESIGN CHANGE .RFC-DC-12-2384 WAS SUCCESSFULLY XNSTALLED IN

~13 7

~16 7

8 8

8 9

9 FACILITY STATUS ACTIVITY Q22 ~

BOTH UNITS ONE AND TWO TO PROVIDE REDUNDANCY FOR THE AFFECTED RELAYS.

10 0

R%%d CONTENT RELEASED OF. RELEASE

~zQ33 ~zQ34 9 10 POWER 0 0 12 Q29 13 OTHER STATUS Qso NA AMOUNTOF ACTIVITY NA Q

44 44 METHOD OF DISCOVERY

( B )~31 45 45 46 SURVEILLANCE TEST DISCOVERY DESCRIPTION Q32 LOCATION OF RELEASE QB 80 80 80 PERSONNEL EXPOSURES 8 9 13 80

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8 9 Q 10 80 PUBLICITY NRC USE ONLY EP DESCRIPTION QB ~2 zc]

7 8

~we 9 IO 68 69 80 CC CR ER T. P. Beilman 616-465-5901 0 L

NAME OF PREPARER 29 4

4 ll

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ATTACHMENT TO LER 5 79-030/03X-l SUPPLEMENT TO CAUSE DESCRIPTION J

PRIOR TO THIS EVENT A DESIGN CHANGE WAS INSTALLED IN BOTH UNITS ONE AND TWO WHXCH INADVERTANTLY REDUCED THE TIME (CYCLES) AVAXL-ABLE FOR THXS RELAY TO PERFORM ITS SEAL-IN FUNCTION. THIS DESIGN CHANGE, COUPLED WITH RELAY DEGRADATXON CAUSED- THE RELAY TO REACT SLOWER DURXNG SEQUENCING.'S THERE ARE FOUR RELAYS PERFORMXNG THIS FUNCTION ON SEPARATE TRAINS (TWO PER UNIT) THE REMAINING THREE WERE TESTED WITH SATXSFACTORY RESULTS.

DUE TO THE SUCCESSFUL II TESTS ON THE REMA N NG THREE RELAYS g THE CAUSE OF THE ORIGINAL EVENT'WAS ATTRIBUTED TO COMPONENT. DEGRADATION, HOWEVER DESIGN CHANGE RFC l2-2384 WAS XNSTALLED IN ALL FOUR CIRCUITS AS A PREVENTATIVE MEASURE, THE DESXGN CHANGE PROVXDES A REDUNDANT RELAY XN PARALLEL WITH EACH ORXGXNAL'RELAY TO ASSURE PROPER OPERATION NO ADDXTXONAL ACTION IS CURRENTLY PLANNED.

NRC FORM 366 U. NUCLEAR REGULATORY COMMISSION L[CENSEE EVENT REPORT CONTROL' LOCK: Q1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

~01' + I 0 C C 1 QR 0 00 0 0 0 0 0 0 0 0QR4 1 1 1 1QR~QR 7 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 I

CON'T

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~LQO 0 5 0 0 0 3 1 5 Qp 0 7 1 7 7 8 Qo 0 8 1 5 7 9 QO 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10

[oO~J WHILE IN MODE TWO IT WAS DISCOVERED THAT THE XNDXCATED POSITION OF CONTROL RODS N- 1 3 AND H- 6 EXCEEDED THE TWELVE STEP LIMIT IMPOSED BY 4 T S~ 3 1 3 2 SIMILAR OCCURRENCES INCLUDE 050 315/76 13 i 44 i 54 i 315/77 27 i 28 i 33 34 315/78 04 077 38 i 40 i 46 315/79 01 14 23 24 37 6050316/7807g08g223lg414864 75 84 93 AND 316/79-14 ~

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LF RgRP RERRR4' ACTION FUTURE EVENT YEAR 21 22 EFFECT

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8 26

/A 27 28 ATTACHMENT CODE 29 NPRDX

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TYPE 30 PRIME COMP.

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COMPONENT TPEN 33 Q16 ACTI(N

~Q19 34 ON )LANT

~Q20 35 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 MET(OD

~Q 36 37 fgURQ +22 40

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SUBMITTED 41 Q23 FORM SUB.

~Q24 42 SUPPLIER

~Q26 43 44 MANUFACTURER W 1 2 '0 47 Q26 o

ACTUAL ROD POSITION WAS DETERMINED TO BE CONSISTENT WXTH DEMAND POSITION THROUGH SECONDARY COIL VOLTAGE MEASUREMENTS. THE EVENT CAUSE WAS TRACED TO EA'CH OF THE RESPECTXVE RODS SIGNAL CONDITIONING MODULE WHICH HAD DRXFTED. FOLLOWING ADJUSTMENT BOTH INDXCATORS 3

FUNCTIONED PROPERLY. SEE SUPPLEMENT."

7 8 9 80 FACILITY STATUS  % POWER ' OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32

~lo 7 8 9 C QR ~QRR 10 0 0 1 12 13 NA 44

~A, 45 Q31 46 OPERATIONAL EVENT 80 ACTIVITY CONTENT Q Q 0

RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 6 ~~ Q33 ~iQ34 NA 7 8 9 10 44 45 80 PERSONNEL EXPOSURES L0 0 ~0~

NUMBER 0 IQo4 TYPE z Qoo DESCRIPTION Q39 Nk 7 8 9 11 12 13 80 PERSONNEL INJURIES

~05 0 Qoo 904 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43

~~Q42 NA 7 8 9 10 80 PUBLICITY NRC USE ONLY ISSIJED DESCRIPTION ~4 O NA 44 8 9 10 68 69 80 4R 616-465-5901 0 NAME OF PREPARER

SUPPLEMENT TO LER 0 79-038/03L-0 SUPPLEMENT TO 'CAUSE DESCRIPTION AN ENGXNEERING REVIEW XS IN PROGRESS TO DETERMXNE THE CAUSE OF '.,

THXS RECURRING PROBLEM.

I NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION 4

I7.77) lCENSEE EVENT REPORT tPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

CONTROL BLOCK:

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~0 7 8 9 LICENSEE CODE 14 QO 15 LICENSE NUMBER 25 Q 26 LICENSE TYPE 30 Q4~ 57 CAT 58 Q,

4 CON'T

~o 7 8 SOURCE LLJQ6 60 61 DOCKET NUMBER 68 Q 69 'VENT DATE 74 QB 75 0 8 1 5 REPORT DATE 7 9 Q9 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 WHILE OPERATING AT A CONSTANT 48 PERCENT POWER LEVEL WITH THE CONTROL RODS IN

~03 MANUAL TO DO CORE FLUX MAPPING, TOO MUCH BORIC ACID WAS INTRODUCED INTO THE RCS WHEN MAKING A TEMPERATURE ADJUSTMENT. THIS CAUSED TAVG TO DROP FURTHER THAN

~06 ANTICIPATED AND, CONTRARY TO T.S. 3.2.5, RESULTED IN PRESSURIZER PRESSURE DIPPING

~06 TO 2195 PSIA. WITHIN TWO MINUTES THE PRESSURE WAS INCREASED ABOVE THE T.S.

MINIMUM OF 2220 PSIA. PREVIOUS OCCURRENCE 79 021.

~08 80 7 8 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE, SUBCODE SUBCODE

~09 Q11 8 Q12 ~B Q73 Q14 ~B Qis ~Z 20 Q19 7 8 9 10 11 12 13 18 19 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT NO. CODE TYPE NO.

LEAlRP Q17 REPO117

~79 21 22 23 24 26 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD 0

HOURS 0 0 0 Q22 SUBMITTED FORM SUB.

~NQ24 SUPPLIER

~NQ2s MANUFACTURER F I 8 0

~BQ79 ~ZQ19 ~ZQ20 2 Q>> Y Q23 Qos 33 34 35 36 37 40 41 42 43 44 47

• CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 o THE OPERATOR COMPENSATED FOR THE EXCESS IV CONTROL RODS AND BY INITIATING RCS DILUT BORIC ACID FLOWMETER WHICH HAD RECENTLY BEEN REPLACED WAS NOT PROPERLY CALIBRATED ~

3 THIS CAUSED THE BLENDER TO DELIVER A MUCH LARGER UANTITY OF ACID TO THE RCS THAN 4 HAD BEEN DIALED INTO THE CONTROL SYSTEM BY THE OPERATOR. CONTINUED

~Q 7 8 9 80 FACILITY STATUS  % POWER OTHER STATUS Q30 DISCOVERY DESCRIPTION I 5 'Z Q28 0 4 8 29 NA OPERATOR OBSERVATION 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q LOCATION OF RELEASE NA Q

6 ~Z Q33 ~ZQ34 NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 ~00 0 Q37 ~Z Q39 13 NA 80 7 8 9 11 12 PERSONNEL INJURIES 7

s 8

~OO 9 '1 NUMBER O Q4o DESCRIPTIONQI 12 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 NA 80 9 Z Q42 NA 7 8 9 10 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION Q NA 44 LNJQ44 2 9 10 68 69 80 o 8

NAME OF PREPARER H. M. CHADWELL (616) 465-5901 X-316

0 0 ~

I

ATTACHMENT TO LER 0: 79-039/03L-0 PAGE Tll0 2 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS:

THE SYSTEM HAS BEEN REPAIRED. NO FURTHER ACTION IS PLANNED.

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