ML18219C211

LER 1978-013-03L, LER 1978-014-03L, & LER 1978-015-03L Re Reducing Power from 75% to 47% in Preparation

ML18219C211
Person / Time
Site:	Cook
Issue date:	03/08/1978
From:	Shaller D Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-013-03L, LER 1978-014-03L, LER 1978-015-03L
Download: ML18219C211 (10)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEN (RIDS >

DISTRIBUTION FOR INCONING NATERIAL 50-315

'OPIES l>

REC: KEPPLER J G ORG: SHALLER D V DQCDATE: 03/08/78 NRC IN 5 NI PWR DATE RCVD: 03/14/78J2 DOCTYPE: LETTER NQTARIZED: NO RECEIVED

SUBJECT:

LTR 1 ENCL 1 LICENSEE EVENT REPT (RO 50-315/78-013/03L-0> ON 02/09/78 CONCERNING UNIT WAS IN NODE 1 REDUCING PWR FROM 75/ TO 47/ IN PREPARATION FOR ROOLING UNIT 2 HAIN TURBINE WITH UNIT 1 STEAN) WHEN AXIAL FLUX DIFFERENCE EXCEEDED PLUS NINUS 5/... WlATT LERS78-014 Oi&i PLANT NANE: COOK UNIT 1 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:PL DISTRIBUTION OF THIS NATERIAL IS AS FOLLOWS +44++<+<++++<4<<++

INCIDENT REPORTS (DISTRIBUTION CODE A002>

FOR ACTION: BR CHIEF SSH NCER++W/4 ENCL INTERNAL: REG FILE++W/EN NRC PDR++W/ENCL NIPC44W/3 ENCL SCHROEDER/IPPQL ITO++W/ENCL HOUSTON>+W/ENCL NOVAK/CHECK~H~WlENCL GR IMES++W/ENCL KNIGHT4 +W/ENCL BUTLER++W/ENCL HANAUER~~W/ENCL TEDESC0~4W/ENCL EISENHUT++W/ENCL BAER~+W/ENCL SHAQ~~W/ENCI VOLLNER/BUNCH4+W/ENCL KREGER/J. COLLINS++W/ENCL ROSA++M/ENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR S ST. JOSEPH'I ++W/ENCL TI C++W/ENCL NS I C++W/ENCL ACRS CAT B+4W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 7807400 3 SIZE: 1P+1P+2P

%%%%4 %%0l %91 6%4 %%4%8! 4 %%%%%%%%%%%%%w%% THE END  %%%%4 %%%%%%9l%%%%%% 4 4 %% %%%% %%4 %%%%%%

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Wmerlcan leatrla INDIANA5 MICHIGANPOt/I/ER COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 March 8, 1978 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United-States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen El lyn, IL 60137 Operating License DPR-58 Docket No. 50-315

Dear Mr. Keppler:

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

RO 78-013/03L-0 RO 78-014/03L-0 RO 78-015/03L-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.

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

Dir., MIPC (3 copies)

~ ' k h

pl V

NRC FORM 366 S. NUCLEAR REGULATORY COMMISSION (7-'41,7)

LlCENSEE EVENT REPORT CONTROL BLOCK Q1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

[OOi]

7 8 14 Q2 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 0 25 Q3 26 4 1 1 1 LICENSE TYPE 1

30 Q ~QE 57 CAT CON'T

~O 7 8 sovRGE MLQe 60 61 0 5 0 0 0 DOCKET NUMBER 3 1 5 68 0 69 EVENT DATE

• 74 QB 0 75 3 0 7 REPORT DATE 7 8 80 QB EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 UNIT WAS IN MODE 1 REDUCING POWER FR

~O3 MAIN TURBINE WITH UNIT 1 STEAM. AXIAL FLUX DIFFERENCE AFD E C +-

4 TION OF APPENDIX A TECHNICAL SPECIFICATIONS 3.2.1. U

~O6 FOR A TOTAL OF 52 MINUTES.

~oe

~O7

~OS 80 7, 8 SYSTEM CA'USE CAUSE COMP. VALVE.

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~RB Q>> ~XQ72 ~ZQ72 Z Z Z Z Z Z Q4 ~ZQPE ~Z 20 QE 7 8 9 10 11 12 13 18 19

~3 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LfR/RP REP0RT ACTION FUTURE

~o EVENT YEAR 21 22 EFFECT

~

23 SHUTDOWN 24 REPORT NO.

26

~~

27 28 ATTACHMENT CODE LILIl~ 29 NPRDX

~

TYPE 30 PRIME COMP.

31 NO.

Lo 32 I

COMPONENT TAKEN ACTION ON PLANT ~ METHOD HOURS 22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER LJxQER LJZQEE LJZQEE ~ZQ>> o o o o ~NQE ~NQ24 ~zQEE z QE 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q2/

o OPERATION OUTSIDE OF TARGET BAND ON UICK CHANGES I P W CONDITION. AFTER POWER WAS REDUCED TO 47% THE CONTROL RODS WERE ADJU THE AFD TO THE TARGET BAND.

3 4

7,8 9 FACILITY 3P METHOD OF 80 STATUS  % POWER OTHERSTATUS DISCOVERY DISCOVERY DESCRIPTION E LLIQEE LJ~LLIQER NA LAJQ>> DURING POWER REDUCTIO 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT Q

4 RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Z Q33 ~ZQ34 NA A 7 TB 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE'ESCRIPTION EKI LoOoo IQLzJS 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION 41 LoOOo JQ42 A 80 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43

~ZQ42 NA 7 8 9 10 80 PUBLICITY ISSUED DESCRIPTION Q NRC USE ONLY HH 8 L~IQ44 9 10 NA 68 69 80 ER 0

NAME OF PREPARER PHDNE. 616 465.5901 L

I NRC FORM,366 WS. NUCLEAR REGULATORY COMMISSION l7.7,7) ~

LlCENSEE EVENT REPORT CONTROL BLOCK: Q1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6

~O 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 0 0 0 0 OQR 25 26 4 1 1 LICENSE TYPE 1 1QE~QE 30 57 CAT 58 CON'T

~O 7 8 soURGE LLJQB 60 61 0 5 0 0 0 DOCKET NUMBER 3 1 5 68 Q 69 0 2 1 EVENT DATE 4 " B 74 Q 75 0 3 o REPORT DATE 7 7 B 80 Q

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 PP D D IS LATED AT

~03 1211. THIS RESULTED IN THE LOSS OF THE PREFERRED RESERVE AUXILIARY POWER SOURCE.

~o4 THIS SOURCE WAS IN "STANDBY" WITH NO LOAD CONNECTED. THIS WAS IN VIOLATION OF

~os TECHNICAL SPECIFICATION 3.8.l.la WHICH RE UIRES TWO OFFSITE POWER SOURCES.

~OB

~O7

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

~EA10 Q>> C Q>> L~JO>> 'Z Z 'Z.'ZP 'Z! Z'4 ~ZO>> ~Z QR 7 8 9 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION QlT LERIRP REPORT ACTION FUTURE EVENT YEAR

+Q 21 22 EFFECT

+

23 SHUTDOWN

~01 24 REPORT NO.

4 26

+~

27 ATTACHMENT 28 CODE L!LID 29 NPRDP TYPE LiJ 30 PRIME COMP.

LJ 31 NO.

32 COMPONENT TAKEN ACTION ON Pl ANT 'ETHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER Q)BL>lQ>> ~>Q2o MZQ>> 0 0 0 0 N Q23 ~NQ24 MAQ26 A 5 0 0 Q26 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o CAUSE OF THE TRIP WAS A DIFFERENTIAL CURRENT TRIP ON PHASE 1. INSPECTION FOUND A 345KV SUPPORT INSULATOR HAD FLASHED OVER TO GROUND. THE INSULATOR WAS CLEANED AND THE TRANSFORMER WAS RETURNED TO SERVICE. THE PREFERRED RESERVE AUXILIARY POWER SOURCE WAS RETURNED TO "STANDBY" CONDITION AT 1941 THE SAME DAY.

4 80 7

~l8 8 9 FACILITY STATUS

~l0

% POWER 0 MA OTHER STATUS ~

~3P METHOD OF DISCOVERY

~AQEE POWER SOURCE DISCOVERY DESCRIPTION Q32 FAILURE AUDIBLE ALARM

[JJQ28 Q28 .

7 8 9 10 12 13 44 45 46 80 EKI

~ ACTIVITY CONTENT RELEASED OF RELEASE LZl Q33 LZIQ34 AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES OiZ 7 8 bZaLJQRT ZIO>>

9 11 12 13 80 PERSONNEL INJURIE S 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION 9 WQ42 7 8 9 10 80 O

PUBLICITY ISSUED

~ZS DESCRIPTION NA

~ NRC USE ONI.Y 8 9 10 68 69 80 g 0

NAME OF PREPARER PHoNE. 616-465-5901

J II

,Wl

NRQ FORIVlo366 JLS. NUCLEAR REGULATORY COMMISSION 17.77)

LICENSEE EVENT REPORT

~

CONTROL BLOCK: (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6 Q4~

I

[OOi] M I D C C 1Q20 0 0 0 0 0 0 0 0 03 Qs 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T

~01 ,",'"";, ~LQ60 5 0 0 0 Q7 74 QB 75 REPORT DATE 80 QB 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Qlo DURING NORMAL OPERATION AND WHILE CONDUCTI G S DISCOVERED THAT THE DIESEL DRIVEN FIRE PUMP TEST VALVE 1-FP-241 WAS I 4 POSITION. THIS VALVE BEING OPEN PREVENTED HAVING AN OPERAB E

~OS BY APPENDIX A TECHNICAL SPECIFICATION 3.7.9.1 SINCE FULL PRESSURE COULD NOT BE

~OB DEVELOPED ON THE FIRE WATER SYSTEM.

~07

~OB 80 7 8 SYSTEM CAUSE CAUSE COMP VALVE 7 8 9 CODE 10 Q11 CODE I Q12 ~

SUBCODE 12 Q12 SEQUENTIAL 13 CO MPONENT CODE 18 OCCURRENCE Q14 SUBCODE L2I 19 Q15 REPORT

~

SUBCODE 20 Q15 REVISION Q11 LF R~RP RRRRR2 EVENT YEAR

~7/

21 22 EFFECT 1

~

23

~DI 24 REPORT NO.

5 26 L~l ATTACHMENT CODE le.B NPRDQ TYPE W

PRIME COMP.

le NO.

COMPONENT l

ACTION FUTURE SHUTDOWN TAKEN ACTION ON PLANT ~ METHOD HOURS ~22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~Q18 LLIQ19 ~Q20 ~Q21 40 41 Q" ~Q24 42 MQ26 43 44 Z g 47 Q

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 o INVESTIGATION REVEALED THE TEST VAL E PUMP RUNNING. TO PREVENT RECURRE C COMPLETION OF SURVEILLANCE TESTING.

4 80 7

~15 8 9 FACILITY STATUS E Q28 ~l0

% POWER D Q29 NA OTHER STATUS ~

~SO METHOD OF DISCOVERY

~BQ21 DISCOVERY DESCRIPTION Q32 NHILE CONDUCTING SURVEILLANCE TEST 8 9 10 12 13 44 45 46 80

~16 ACTIVITY CONTENT RELEASED OF RELEASE Z Q>> LZJQ34 AMOUNTOF ACTIVITY ~ LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION ZO2 ~DD D Q2~2QRR 13 NA 80 7 .. 8 9 11 12 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 8 ~OO D Q4o NA 80 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION WQ42 7 8 9 10 80 P U8 L I CITY NRC USE ONLY ISSUED DESCRIPTION ~4 94 a

O ~Q44 68 69 80 g 0

616-465-5g01

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